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1

Ethanol production from spent sulfite liquor fortified by hydrolysis of pulp mill primary clarifier sludge  

SciTech Connect (OSTI)

Some low-yield sulfite pulping operations ferment spent sulfite liquor (SSL) to remove biochemical oxygen demand associated with dissolved sugars while at the same time generating ethanol as a salable product. Simultaneous saccharification and fermentation (SSF) of primary clarifier sludge in a medium of SSL was proposed as a means of reducing the amount of sludge to be disposed of while at the same time increasing ethanol productivity. In this article, the option of fortifying existing SSL fermenting processes with the sugars produced via in situ enzymatic hydrolysis of sulfite primary clarifier sludge (PCS) has been explored. In 100% SSL PCS hydrolysis rates as high as 3.4 g/(L{center_dot}h) were observed at an initial enzyme loading of 10 filter paper units (FPU)/g PCS. To reduce the deleterious effects of glucose inhibition, single-stage SSF was carried out using cellulose enzymes and Saccharomyces cerevisiae. The production rate of ethanol in SSL was increased by as much as 25% through the SSF process. 12 refs., 4 figs., 2 tabs.

Moritz, J.W.; Duff, S.J.B. [Univ. of British Columbia, Vancouver (Canada)

1996-12-31T23:59:59.000Z

2

Kraft black liquor combustion: Advancement in fundamental understanding  

SciTech Connect (OSTI)

Self-generated fuel streams plus purchased fossil fuel and power supply the pulp and paper industry with its energy requirements. The total industry energy use for 1986 was approximately 2.3 Quad (2300 trillion Btus). Self-generated and residue fuels accounted for 57% of the energy requirements. Spent pulping liquors provide the single largest self-generated energy source, approximately one Quad (900 trillion Btus). The pulp and paper industry also leads the nation in cogeneration performance. In 1986 eighty-nine percent (89%) of the 46 billion KWHs generated were produced by cogeneration. Spent pulping liquors supply the single largest fuel source (35%) to these cogeneration facilities. Spent pulping liquors consist of solubilized wood organics, spent inorganic chemicals, and water. Since kraft pulp dominates the North American market, 74%, kraft black liquor is the dominant spent pulping liquor. Effective recovery of high level energy and chemicals from black liquor contributes heavily toward dominance of kraft pulping. The kraft chemical recovery cycle centers around the recovery boiler. Kraft recovery boilers have been commercially available for over 50 years. The potential still exists, however, for significant improvements in energy recovery and black liquor throughput. Potential energy benefits from black liquor combustion research amount to 30 trillion Btus. Energy recovery increases often are an additional benefit from modifications made to increase black liquor throughput. Capacity increases of at least 5% are often achievable. Increased energy productivity of the kraft chemical recovery boiler will come by incorporation of improved fundamental knowledge into the technology used for boiler upgrades and new boiler construction. 5 refs., 9 figs.

Clay, D.T.

1987-10-01T23:59:59.000Z

3

Lowering kraft black liquor viscosity of ultrafiltration  

SciTech Connect (OSTI)

High viscosity is a major factor limiting the percentage total dissolved solids (%TDS) to which kraft black liquor (KBL), a spent pulping liquor, can be concentrated before it is burned to recover its fuel value and its inorganic chemicals. The effect on black liquor viscosity of removing high molecular weight lignin by ultrafiltration of 16% and 24% TDS liquors was studied. Viscosities of ultrafiltration permeates were reduced relative to feed black liquors. When a permeate was concentrated to higher %TDS levels, its viscosity decreased yet further relative to feed samples evaporated to similar solids levels. Retentate viscosity was very high relative to both feed and permeate. Ultrafiltration was carried out at 75/degrees/C using polysulfone membranes in a plate-and-frame or hollow fiber system. Flux rates varied greatly depending upon the specific liquor used. Flux was enhanced by increased temperature and increased linear velocity. The membrane molecular weight cutoff (MWCO) typically used was 50,000; increasing 100,000 or 200,000 did not enhance flux.

Hill, M.K.; Violette, D.A.; Woerner, D.L.

1988-10-01T23:59:59.000Z

4

Kraft Liquor Corrosion Margaret Gorog  

E-Print Network [OSTI]

1 Kraft Liquor Corrosion Margaret Gorog Federal Way, WA Pulp and Paper Corrosion Symposium Georgia Tech Renewable Bioproducts Institute November 2014 · Brown Stock Corrosion · Alkaline Liquor Corrosion · Black Liquor Corrosion ­ Evaporators ­ Research · High Solids Black Liquor Corrosion of Stainless Steel

Das, Suman

5

Gasification of black liquor  

SciTech Connect (OSTI)

A process is described for treating a concentrated aqueous black liquor carbonaceous material and alkali metal sulfur compounds to form a combustible gas and a sulfide-rich melt comprising: (a) providing a gasifier vessel maintained at a pressure of from about 1 to 50 atmospheres and containing a relatively shallow molten salt pool at its bottom within a sump equipped with an overflow discharge; (b) introducing into the top of the drying zone the concentrated aqueous black liquor containing carbonaceous material and alkali metal sulfur compounds; (c) evaporating water from the concentrated aqueous black liquor in the drying zone by direct contact of the aqueous black liquor with the hot gas rising from the gasification zone to produce dried black liquor solids; (d) introducing a first portion of an oxygen-containing gas into the gas space in the gasification zone located below the drying zone immediately above the molten salt pool to partially oxidize and gasify a fraction of the carbonaceous material in the dried black liquor solids falling through the zone to form a hot combustible gas; (e) introducing a second portion of the oxygen-containing gas beneath the surface of the molten salt pool in an amount sufficient to cause gasification of essentially all carbonaceous material entering the pool from the gasification zone but not sufficient to create oxidizing conditions in the pool; (f) withdrawing the cooled combustible gas having a higher heating value of at least about 90 Btu/scf (dry basis) from an upper portion of the drying zone; and (g) withdrawing from the overflow discharge in the molten salt reduction zone a melt in which the sulfur content is predominantly in the form of alkali metal sulfide.

Kohl, A.L.

1987-07-28T23:59:59.000Z

6

Gasification of black liquor  

DOE Patents [OSTI]

A concentrated aqueous black liquor containing carbonaceous material and alkali metal sulfur compounds is treated in a gasifier vessel containing a relatively shallow molten salt pool at its bottom to form a combustible gas and a sulfide-rich melt. The gasifier vessel, which is preferably pressurized, has a black liquor drying zone at its upper part, a black liquor solids gasification zone located below the drying zone, and a molten salt sulfur reduction zone which comprises the molten salt pool. A first portion of an oxygen-containing gas is introduced into the gas space in the gasification zone immediatley above the molten salt pool. The remainder of the oxygen-containing gas is introduced into the molten salt pool in an amount sufficient to cause gasification of carbonaceous material entering the pool from the gasification zone but not sufficient to create oxidizing conditions in the pool. The total amount of the oxygen-containing gas introduced both above the pool and into the pool constitutes between 25 and 55% of the amount required for complete combustion of the black liquor feed. A combustible gas is withdrawn from an upper portion of the drying zone, and a melt in which the sulfur content is predominantly in the form of alkali metal sulfide is withdrawn from the molten salt sulfur reduction zone.

Kohl, Arthur L. (Woodland Hills, CA)

1987-07-28T23:59:59.000Z

7

Gasification of black liquor  

DOE Patents [OSTI]

A concentrated aqueous black liquor containing carbonaceous material and alkali metal sulfur compounds is treated in a gasifier vessel containing a relatively shallow molten salt pool at its bottom to form a combustible gas and a sulfide-rich melt. The gasifier vessel, which is preferably pressurized, has a black liquor drying zone at its upper part, a black liquor solids gasification zone located below the drying zone, and a molten salt sulfur reduction zone which comprises the molten salt pool. A first portion of an oxygen-containing gas is introduced into the gas space in the gasification zone immediately above the molten salt pool. The remainder of the oxygen-containing gas is introduced into the molten salt pool in an amount sufficient to cause gasification of carbonaceous material entering the pool from the gasification zone but not sufficient to create oxidizing conditions in the pool. The total amount of the oxygen-containing gas introduced both above the pool and into the pool constitutes between 25 and 55% of the amount required for complete combustion of the black liquor feed. A combustible gas is withdrawn from an upper portion of the drying zone, and a melt in which the sulfur content is predominantly in the form of alkali metal sulfide is withdrawn from the molten salt sulfur reduction zone. 2 figs.

Kohl, A.L.

1987-07-28T23:59:59.000Z

8

Combustion of black liquor  

SciTech Connect (OSTI)

This patent describes an improvement in the combustion of black liquor in an existing Tomlison recovery boiler unit in which black liquor is sprayed into a furnace in which it is successively dried, pyrolyzed and converted to a bed of solid carbonaceous residue, using a primary air stream and a secondary air stream and the residue is subsequently converted to a smelt. The improvement comprises: the addition of between an effective amount up to 5% oxygen by volume to the primary air stream directed at the bed of solid carbonaceous residue, the amount of oxygen added being sufficient to increase the adiabatic flame temperature, the combustion rate of the solid carbonaceous material, the rate of pyrolysis, the temperature in the lower portion of the furnace, the the drying rate of black liquor droplets, and to decrease the temperature of the gases entering the heat transfer surfaces in the upper portion of the furnace and the rate of deposit formation on the surfaces and wherein the amount of black liquor combusted is increased as compared with the amount combusted in the same furnace operated without the addition of oxygen to the primary air.

Mullen, W.T.

1989-08-15T23:59:59.000Z

9

Proceedings of the black liquor research program review fifth meeting  

SciTech Connect (OSTI)

On June 14--17, 1988 the participants and invited guests of the Cooperative Program in Kraft Recovery gathered in Charleston, South Carolina, to review progress on four major black liquor research programs being executed at the Institute of Paper Chemistry, the University of Maine, the National Bureau of Standards, and the University of Florida. These programs include: (1) Black Liquor Properties; (2) Black Liquor Droplet Formation; (3) Black Liquor Nozzle Evaluation; and (4) Black Liquor Combustion. In addition to the objectives of previous meetings, this meeting made a direct attempt to gather ideas on how to improve our ability to move from new technology concepts to commercial implementation. Also attached is the agenda for the Charleston meeting. The first two days were involved with updates and reviews of the four major black liquor programs. A half day was spent discussing pathways to implementation and developing thoughts on what industry, DOE and academia could do to facilitate commercial implementation of the research results. This publication is a summary of the presentations made in Charleston and the industry responses to the research work. Readers are cautioned that the contents are in-progress updates on the status of the research and do not represent referred technical papers. Any questions regarding the content should be referred to the principal investigators of the project.

Not Available

1988-09-01T23:59:59.000Z

10

Kraft black liquor delivery systems  

SciTech Connect (OSTI)

Improvement of spray nozzles for black liquor injection into kraft recovery furnaces is expected to result from obtaining a controlled, well-defined droplet size distribution. Work this year has centered on defining the capabilities of commercial black liquor nozzles currently in use. Considerations of the observed mechanism of droplet formation suggest a major revision is needed in the theory of how droplets form from these nozzles. High resolution, high sensitivity video has been shown to be superior to flash x-ray as a technique for measuring the droplet size distribution as well as the formation history. An environmentally sound spray facility capable of spraying black liquor at temperatures up to normal firing conditions is being constructed before data acquisition continues. Preliminary correlations have been developed between liquor properties, nozzle design, and droplet size. Three aspects of nozzle design have been investigated: droplet size distribution, fluid sheet thickness, and flow and pressure drop characteristics. The standard deviation about the median droplet size for black liquor is nearly the same as the for a wide variety of other fluids and nozzle types. Preliminary correlation for fluid sheet thickness on the plate of a splashplate nozzle show the strong similarities of black liquor to other fluids. The flow and pressure drop characteristic of black liquor nozzle, follow a simple two-term relationship similar to other flow devices. This means that in routine mill operation of black liquor nozzles only the fluid acceleration in the nozzle is important, viscous losses are quiet small. 21 refs., 53 figs., 10 tabs.

Adams, T.N.; Empie, H.L.; Obuskovic, N.; Spielbauer, T.M.

1990-02-01T23:59:59.000Z

11

Combustion properties of Kraft Black Liquors  

SciTech Connect (OSTI)

In a previous study of the phenomena involved in the combustion of black liquor droplets a numerical model was developed. The model required certain black liquor specific combustion information which was then not currently available, and additional data were needed for evaluating the model. The overall objectives of the project reported here was to provide experimental data on key aspects of black liquor combustion, to interpret the data, and to put it into a form which would be useful for computational models for recovery boilers. The specific topics to be investigated were the volatiles and char carbon yields from pyrolysis of single black liquor droplets; a criterion for the onset of devolatilization and the accompanying rapid swelling; and the surface temperature of black liquor droplets during pyrolysis, combustion, and gasification. Additional information on the swelling characteristics of black liquor droplets was also obtained as part of the experiments conducted.

Frederick, W.J. Jr.; Hupa, M. (Aabo Akademi, Turku (Finland))

1993-04-01T23:59:59.000Z

12

National Dioxin Study Tier 4 - combustion sources: final test report - Site 8, Black-liquor boiler BLB-C  

SciTech Connect (OSTI)

This report summarizes the results of a dioxin/furan emissions test of a black-liquor recovery boiler equipped with a drybottom electrostatic precipitator for particulate emissions control. Black-liquor recovery boilers are used at kraft pulp mills to produce process steam and to reclaim inorganic chemicals from spent wood pulping liquors. The dioxin/furan emissions test was conducted under Tier 4 of the National Dioxin Study. The primary objective of Tier 4 is to determine if various combustion sources are sources of dioxin and/or furan emissions. If any of the combustion sources are found to emit dioxin or furan, the secondary objective of Tier 4 is to quantify these emissions. Black-liquor recovery boilers are one of 8 combustion-source categories that have been tested in the Tier 4 program. The tested black-liquor boiler, BLB-C, was selected for the test after an initial information screening and a one-day pretest survey visit. Boiler BLB-C is considered representative of black-liquor recovery boilers with dry-bottom electrostatic precipitators. The amount of chloride present in the black-liquor circuit at this site is considered intermediate to high relative to that found at other kraft pulp mills. Data presented in the report include dioxin (tetra through octa homologue +2378 TCDD) and furan (tetra through octa homologue +2378 TCDF) results for both stack samples and ash samples. In addition, process data collected during sampling are also presented.

Jamgochian, C.L.; Keller, L.E.

1987-04-01T23:59:59.000Z

13

Black Liquor Research Program symposium: proceedings  

SciTech Connect (OSTI)

In the paper pulp industry's recovery boilers, black liquor is sprayed in through nozzle guns near the top of the furnace. This report includes eight papers. (DLC)

Emerson, D.B.; Whitworth, B.A.

1985-03-01T23:59:59.000Z

14

Highly Energy Efficient Directed Green Liquor Utilization (D...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

Highly Energy Efficient Directed Green Liquor Utilization (D-GLU) Pulping Highly Energy Efficient Directed Green Liquor Utilization (D-GLU) Pulping This factsheet describes a...

15

Causticizing for Black Liquor Gasifiers  

SciTech Connect (OSTI)

The cost-benefit outlook of black liquor gasification (BLG) could be greatly improved if the smelt causticization step could be achieved in situ during the gasification step. Or, at a minimum, the increase in causticizing load associated with BLG could be mitigated. A number of chemistries have been proven successful during black liquor combustion. In this project, three in situ causticizing processes (titanate, manganate, and borate) were evaluated under conditions suitable for high temperature entrained flow BLG, and low temperature steam reforming of black liquor. The evaluation included both thermodynamic modeling and lab experimentation. Titanate and manganate were tested for complete direct causticizing (to thus eliminate the lime cycle), and borates were evaluated for partial causticizing (to mitigate the load increase associated with BLG). Criteria included high carbonate conversion, corresponding hydroxide recovery upon hydrolysis, non process element (NPE) removal, and economics. Of the six cases (three chemistries at two BLG conditions), only two were found to be industrially viable: titanates for complete causticizing during high temperature BLG, and borates for partial causticizing during high temperature BLG. These two cases were evaluated for integration into a gasification-based recovery island. The Larsen [28] BLG cost-benefit study was used as a reference case for economic forecasting (i.e. a 1500 tpd pulp mill using BLG and upgrading the lime cycle). By comparison, using the titanate direct causticizing process yielded a net present value (NPV) of $25M over the NPV of BLG with conventional lime cycle. Using the existing lime cycle plus borate autocausticizing for extra capacity yielded a NPV of $16M.

Scott Sinquefeld; James Cantrell; Xiaoyan Zeng; Alan Ball; Jeff Empie

2009-01-07T23:59:59.000Z

16

REFRACTORY FOR BLACK LIQUOR GASIFIERS  

SciTech Connect (OSTI)

The University of Missouri-Rolla will identify materials that will permit the safe, reliable and economical operation of combined cycle gasifiers by the pulp and paper industry. The primary emphasis of this project will be to resolve the material problems encountered during the operation of low-pressure high-temperature (LPHT) and low-pressure low-temperature (LPLT) gasifiers while simultaneously understanding the materials barriers to the successful demonstration of high-pressure high-temperature (HPHT) black liquor gasifiers. This study will define the chemical, thermal and physical conditions in current and proposed gasifier designs and then modify existing materials and develop new materials to successfully meet the formidable material challenges. Resolving the material challenges of black liquor gasification combined cycle technology will provide energy, environmental, and economic benefits that include higher thermal efficiencies, up to three times greater electrical output per unit of fuel, and lower emissions. In the near term, adoption of this technology will allow the pulp and paper industry greater capital effectiveness and flexibility, as gasifiers are added to increase mill capacity. In the long term, combined-cycle gasification will lessen the industry's environmental impact while increasing its potential for energy production, allowing the production of all the mill's heat and power needs along with surplus electricity being returned to the grid. An added benefit will be the potential elimination of the possibility of smelt-water explosions, which constitute an important safety concern wherever conventional Tomlinson recovery boilers are operated. Developing cost-effective materials with improved performance in gasifier environments may be the best answer to the material challenges presented by black liquor gasification. Refractory materials may be selected/developed that either react with the gasifier environment to form protective surfaces in-situ; are functionally-graded to give the best combination of thermal, mechanical, and physical properties and chemical stability; or are relatively inexpensive, reliable repair materials. This report covers Task 1.3, Simulative corrosion of candidate materials developed by refractory producers and in the laboratory based on the results of Task 1.1 and Task 1.2. Refractories provided by in-kind sponsors were tested by cup testing, density/porosity determinations, chemical analysis and microscopy. The best performing materials in the cup testing were fused cast materials. However, 2 castables appear to outperforming any of the previously tested materials and may perform better than the fused cast materials in operation. The basis of the high performance of these materials is the low open porosity and permeability to black liquor smelt.

William L. Headrick Jr; Musa Karakus; Jun Wei

2005-03-01T23:59:59.000Z

17

REFRACTORY FOR BLACK LIQUOR GASIFIERS  

SciTech Connect (OSTI)

The University of Missouri-Rolla will identify materials that will permit the safe, reliable and economical operation of combined cycle gasifiers by the pulp and paper industry. The primary emphasis of this project will be to resolve the material problems encountered during the operation of low-pressure high-temperature (LPHT) and low-pressure low-temperature (LPLT) gasifiers while simultaneously understanding the materials barriers to the successful demonstration of high-pressure high-temperature (HPHT) black liquor gasifiers. This study will define the chemical, thermal and physical conditions in current and proposed gasifier designs and then modify existing materials and develop new materials to successfully meet the formidable material challenges. Resolving the material challenges of black liquor gasification combined cycle technology will provide energy, environmental, and economic benefits that include higher thermal efficiencies, up to three times greater electrical output per unit of fuel, and lower emissions. In the near term, adoption of this technology will allow the pulp and paper industry greater capital effectiveness and flexibility, as gasifiers are added to increase mill capacity. In the long term, combined-cycle gasification will lessen the industry's environmental impact while increasing its potential for energy production, allowing the production of all the mill's heat and power needs along with surplus electricity being returned to the grid. An added benefit will be the potential elimination of the possibility of smelt-water explosions, which constitute an important safety concern wherever conventional Tomlinson recovery boilers are operated. Developing cost-effective materials with improved performance in gasifier environments may be the best answer to the material challenges presented by black liquor gasification. Refractory materials may be selected/developed that either react with the gasifier environment to form protective surfaces in-situ; are functionally-graded to give the best combination of thermal, mechanical, and physical properties and chemical stability; or are relatively inexpensive, reliable repair materials. Material development will be divided into 2 tasks: Task 1, Development and property determinations of improved and existing refractory systems for black liquor containment. Refractory systems of interest include magnesium aluminate and barium aluminate for binder materials, both dry and hydratable, and materials with high alumina contents, 85-95 wt%, aluminum oxide, 5.0-15.0 wt%, and BaO, SrO, CaO, ZrO{sub 2} and SiC. Task 2, Finite element analysis of heat flow and thermal stress/strain in the refractory lining and steel shell of existing and proposed vessel designs. Stress and strain due to thermal and chemical expansion has been observed to be detrimental to the lifespan of existing black liquor gasifiers. The thermal and chemical strain as well as corrosion rates must be accounted for in order to predict the lifetime of the gasifier containment materials.

William L. Headrick Jr; Musa Karakus; Xiaoting Liang; Alireza Rezaie

2004-10-01T23:59:59.000Z

18

Refractory for Black Liquor Gasifiers  

SciTech Connect (OSTI)

The University of Missouri-Rolla will identify materials that will permit the safe, reliable and economical operation of combined cycle gasifiers by the pulp and paper industry. The primary emphasis of this project will be to resolve the material problems encountered during the operation of low-pressure high-temperature (LPHT) and low-pressure low-temperature (LPLT) gasifiers while simultaneously understanding the materials barriers to the successful demonstration of high-pressure high-temperature (HPHT) black liquor gasifiers. This study will define the chemical, thermal and physical conditions in current and proposed gasifier designs and then modify existing materials and develop new materials to successfully meet the formidable material challenges. Resolving the material challenges of black liquor gasification combined cycle technology will provide energy, environmental, and economic benefits that include higher thermal efficiencies, up to three times greater electrical output per unit of fuel, and lower emissions. In the near term, adoption of this technology will allow the pulp and paper industry greater capital effectiveness and flexibility, as gasifiers are added to increase mill capacity. In the long term, combined-cycle gasification will lessen the industry's environmental impact while increasing its potential for energy production, allowing the production of all the mill's heat and power needs along with surplus electricity being returned to the grid. An added benefit will be the potential elimination of the possibility of smelt-water explosions, which constitute an important safety concern wherever conventional Tomlinson recovery boilers are operated. Developing cost-effective materials with improved performance in gasifier environments may be the best answer to the material challenges presented by black liquor gasification. Refractory materials may be selected/developed that either react with the gasifier environment to form protective surfaces in-situ; are functionally-graded to give the best combination of thermal, mechanical, and physical properties and chemical stability; or are relatively inexpensive, reliable repair materials. Material development will be divided into 2 tasks: Task 1, Development and property determinations of improved and existing refractory systems for black liquor containment. Refractory systems of interest include magnesium aluminate and barium aluminate for binder materials, both dry and hydratable, and materials with high alumina contents, 85-95 wt%, aluminum oxide, 5.0-15.0 wt%, and BaO, SrO, CaO, ZrO2 and SiC. Task 2, Finite element analysis of heat flow and thermal stress/strain in the refractory lining and steel shell of existing and proposed vessel designs. Stress and strain due to thermal and chemical expansion has been observed to be detrimental to the lifespan of existing black liquor gasifiers. The thermal and chemical strain as well as corrosion rates must be accounted for in order to predict the lifetime of the gasifier containment materials.

William L. Headrick; Musa Karakus; Alireza Rezaie

2004-03-30T23:59:59.000Z

19

REFRACTORY FOR BLACK LIQUOR GASIFIERS  

SciTech Connect (OSTI)

The University of Missouri-Rolla will identify materials that will permit the safe, reliable and economical operation of combined cycle gasifiers by the pulp and paper industry. The primary emphasis of this project will be to resolve the material problems encountered during the operation of low-pressure high-temperature (LPHT) and low-pressure low-temperature (LPLT) gasifiers while simultaneously understanding the materials barriers to the successful demonstration of high-pressure high-temperature (HPHT) black liquor gasifiers. This study will define the chemical, thermal and physical conditions in current and proposed gasifier designs and then modify existing materials and develop new materials to successfully meet the formidable material challenges. Resolving the material challenges of black liquor gasification combined cycle technology will provide energy, environmental, and economic benefits that include higher thermal efficiencies, up to three times greater electrical output per unit of fuel, and lower emissions. In the near term, adoption of this technology will allow the pulp and paper industry greater capital effectiveness and flexibility, as gasifiers are added to increase mill capacity. In the long term, combined-cycle gasification will lessen the industry's environmental impact while increasing its potential for energy production, allowing the production of all the mill's heat and power needs along with surplus electricity being returned to the grid. An added benefit will be the potential elimination of the possibility of smelt-water explosions, which constitute an important safety concern wherever conventional Tomlinson recovery boilers are operated. Developing cost-effective materials with improved performance in gasifier environments may be the best answer to the material challenges presented by black liquor gasification. Refractory materials may be selected/developed that either react with the gasifier environment to form protective surfaces in-situ; are functionally-graded to give the best combination of thermal, mechanical, and physical properties and chemical stability; or are relatively inexpensive, reliable repair materials. Material development will be divided into 2 tasks: Task 1, Development and property determinations of improved and existing refractory systems for black liquor containment. Refractory systems of interest include magnesium aluminate and barium aluminate for binder materials, both dry and hydratable, and materials with high alumina contents, 85-95 wt%, aluminum oxide, 5.0-15.0 wt%, and BaO, SrO, CaO, ZrO{sub 2} and SiC. Task 2, Finite element analysis of heat flow and thermal stress/strain in the refractory lining and steel shell of existing and proposed vessel designs. Stress and strain due to thermal and chemical expansion has been observed to be detrimental to the lifespan of existing black liquor gasifiers. The thermal and chemical strain as well as corrosion rates must be accounted for in order to predict the lifetime of the gasifier containment materials.

William L. Headrick Jr; Musa Karakus; Xiaoting Liang; Alireza Rezaie

2004-07-01T23:59:59.000Z

20

Refractory for Black Liquor Gasifiers  

SciTech Connect (OSTI)

The University of Missouri-Rolla identified materials that permit the safe, reliable and economical operation of combined cycle gasifiers by the pulp and paper industry. The primary emphasis of this project was to resolve the material problems encountered during the operation of low-pressure high-temperature (LPHT) and low-pressure low-temperature (LPLT) gasifiers while simultaneously understanding the materials barriers to the successful demonstration of high-pressure high-temperature (HPHT) black liquor gasifiers. This study attempted to define the chemical, thermal and physical conditions in current and proposed gasifier designs and then modify existing materials and develop new materials to successfully meet the formidable material challenges. Resolving the material challenges of black liquor gasification combined cycle technology will provide energy, environmental, and economic benefits that include higher thermal efficiencies, up to three times greater electrical output per unit of fuel, and lower emissions. In the near term, adoption of this technology will allow the pulp and paper industry greater capital effectiveness and flexibility, as gasifiers are added to increase mill capacity. In the long term, combined-cycle gasification will lessen the industry's environmental impact while increasing its potential for energy production, allowing the production of all the mill's heat and power needs along with surplus electricity being returned to the grid. An added benefit will be the potential elimination of the possibility of smelt-water explosions, which constitute an important safety concern wherever conventional Tomlinson recovery boilers are operated. Developing cost-effective materials with improved performance in gasifier environments may be the best answer to the material challenges presented by black liquor gasification. Refractory materials were selected/developed that either react with the gasifier environment to form protective surfaces in-situ; and were functionally-graded to give the best combination of thermal, mechanical, and physical properties and chemical stability; or are relatively inexpensive, reliable repair materials. Material development were divided into 2 tasks: Task 1, Development and property determinations of improved and existing refractory systems for black liquor containment. Refractory systems of interest include magnesium aluminate and barium aluminate for binder materials, both dry and hydratable, and materials with high alumina contents, 85-95 wt%, aluminum oxide, 5.0-15.0 wt%, and BaO, SrO, CaO, ZrO{sub 2} and SiC. Task 2, Finite element analysis of heat flow and thermal stress/strain in the refractory lining and steel shell of existing and proposed vessel designs. Stress and strain due to thermal and chemical expansion has been observed to be detrimental to the lifespan of existing black liquor gasifiers. The thermal and chemical strain as well as corrosion rates must be accounted for in order to predict the lifetime of the gasifier containment materials.

William L. Headrick Jr; Musa Karakus; Xiaoting Liang

2005-10-01T23:59:59.000Z

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21

REFRACTORY FOR BLACK LIQUOR GASIFIERS  

SciTech Connect (OSTI)

The University of Missouri-Rolla will identify materials that will permit the safe, reliable and economical operation of combined cycle gasifiers by the pulp and paper industry. The primary emphasis of this project will be to resolve the materials problems encountered during the operation of low-pressure high-temperature (LPHT) and low-pressure low-temperature (LPLT) gasifiers while simultaneously understanding the materials barriers to the successful demonstration of high-pressure high-temperature (HPHT) black liquor gasifiers. This study will define the chemical, thermal and physical conditions in current and proposed gasifier designs and then modify existing materials and develop new materials to successfully meet the formidable material challenges. Resolving the material challenges of black liquor gasification combined cycle technology will provide energy, environmental, and economic benefits that include higher thermal efficiencies, up to three times greater electrical output per unit of fuel, and lower emissions. In the near term, adoption of this technology will allow the pulp and paper industry greater capital effectiveness and flexibility, as gasifiers are added to increase mill capacity. In the long term, combined-cycle gasification will lessen the industry's environmental impact while increasing its potential for energy production, allowing the production of all the mill's heat and power needs along with surplus electricity being returned to the grid. An added benefit will be the potential elimination of the possibility of smelt-water explosions, which constitute an important safety concern wherever conventional Tomlinson recovery boilers are operated. Developing cost-effective materials with improved performance in gasifier environments may be the best answer to the material challenges presented by black liquor gasification. Refractory materials may be selected/developed that either react with the gasifier environment to form protective surfaces in-situ; are functionally-graded to give the best combination of thermal, mechanical, and physical properties and chemical stability; or are relatively inexpensive, reliable repair materials. Material development will be divided into 2 tasks: Task 1, Development and property determinations of improved and existing refractory systems for black liquor containment. Refractory systems of interest include magnesium aluminate and barium aluminate spinels for binder materials, both dry and hydratable, and materials with high alumina contents, 85-95 wt%, aluminum oxide, 5.0-15.0 wt%, and BaO, SrO, CaO, ZrO{sub 2} and SiC. Task 2, Finite element analysis of heat flow and thermal stress/strain in the refractory lining and steel shell of existing and proposed vessel designs. Stress and strain due to thermal and chemical expansion has been observed to be detrimental to the lifespan of existing black liquor gasifiers. The thermal and chemical strain as well as corrosion rates must be accounted for in order to predict the lifetime of the gasifier containment materials.

William L. Headrick Jr.; Alireza Rezaie

2004-04-01T23:59:59.000Z

22

REFRACTORY FOR BLACK LIQUOR GASIFIERS  

SciTech Connect (OSTI)

The University of Missouri-Rolla will identify materials that will permit the safe, reliable and economical operation of combined cycle gasifiers by the pulp and paper industry. The primary emphasis of this project will be to resolve the material problems encountered during the operation of low-pressure high-temperature (LPHT) and low-pressure low-temperature (LPLT) gasifiers while simultaneously understanding the materials barriers to the successful demonstration of high-pressure high-temperature (HPHT) black liquor gasifiers. This study will define the chemical, thermal and physical conditions in current and proposed gasifier designs and then modify existing materials and develop new materials to successfully meet the formidable material challenges. Resolving the material challenges of black liquor gasification combined cycle technology will provide energy, environmental, and economic benefits that include higher thermal efficiencies, up to three times greater electrical output per unit of fuel, and lower emissions. In the near term, adoption of this technology will allow the pulp and paper industry greater capital effectiveness and flexibility, as gasifiers are added to increase mill capacity. In the long term, combined-cycle gasification will lessen the industry's environmental impact while increasing its potential for energy production, allowing the production of all the mill's heat and power needs along with surplus electricity being returned to the grid. An added benefit will be the potential elimination of the possibility of smelt-water explosions, which constitute an important safety concern wherever conventional Tomlinson recovery boilers are operated. Developing cost-effective materials with improved performance in gasifier environments may be the best answer to the material challenges presented by black liquor gasification. Refractory materials may be selected/developed that either react with the gasifier environment to form protective surfaces in-situ; are functionally-graded to give the best combination of thermal, mechanical, and physical properties and chemical stability; or are relatively inexpensive, reliable repair materials. Material development will be divided into 2 tasks: Task 1, Development and property determinations of improved and existing refractory systems for black liquor containment. Refractory systems of interest include magnesium aluminate and barium aluminate for binder materials, both dry and hydratable, and materials with high alumina contents, 85-95 wt%, aluminum oxide, 5.0-15.0 wt%, and BaO, SrO, CaO, ZrO{sub 2} and SiC. Task 2, Finite element analysis of heat flow and thermal stress/strain in the refractory lining and steel shell of existing and proposed vessel designs. Stress and strain due to thermal and chemical expansion has been observed to be detrimental to the lifespan of existing black liquor gasifiers. The thermal and chemical strain as well as corrosion rates must be accounted for in order to predict the lifetime of the gasifier containment materials.

William L. Headrick Jr; Musa Karakus; Xiaoting Liang; Jun Wei

2005-04-01T23:59:59.000Z

23

REFRACTORY FOR BLACK LIQUOR GASIFIERS  

SciTech Connect (OSTI)

The University of Missouri-Rolla will identify materials that will permit the safe, reliable and economical operation of combined cycle gasifiers by the pulp and paper industry. The primary emphasis of this project will be to resolve the material problems encountered during the operation of low-pressure high-temperature (LPHT) and low-pressure low-temperature (LPLT) gasifiers while simultaneously understanding the materials barriers to the successful demonstration of high-pressure high-temperature (HPHT) black liquor gasifiers. This study will define the chemical, thermal and physical conditions in current and proposed gasifier designs and then modify existing materials and develop new materials to successfully meet the formidable material challenges. Resolving the material challenges of black liquor gasification combined cycle technology will provide energy, environmental, and economic benefits that include higher thermal efficiencies, up to three times greater electrical output per unit of fuel, and lower emissions. In the near term, adoption of this technology will allow the pulp and paper industry greater capital effectiveness and flexibility, as gasifiers are added to increase mill capacity. In the long term, combined-cycle gasification will lessen the industry's environmental impact while increasing its potential for energy production, allowing the production of all the mill's heat and power needs along with surplus electricity being returned to the grid. An added benefit will be the potential elimination of the possibility of smelt-water explosions, which constitute an important safety concern wherever conventional Tomlinson recovery boilers are operated. Developing cost-effective materials with improved performance in gasifier environments may be the best answer to the material challenges presented by black liquor gasification. Refractory materials may be selected/developed that either react with the gasifier environment to form protective surfaces in-situ; are functionally-graded to give the best combination of thermal, mechanical, and physical properties and chemical stability; or are relatively inexpensive, reliable repair materials. Material development will be divided into 2 tasks: Task 1, Development and property determinations of improved and existing refractory systems for black liquor containment. Refractory systems of interest include magnesium aluminate and barium aluminate for binder materials, both dry and hydratable, and materials with high alumina contents, 85-95 wt%, aluminum oxide, 5.0-15.0 wt%, and BaO, SrO, CaO, ZrO{sub 2} and SiC. Task 2, Finite element analysis of heat flow and thermal stress/strain in the refractory lining and steel shell of existing and proposed vessel designs. Stress and strain due to thermal and chemical expansion has been observed to be detrimental to the lifespan of existing black liquor gasifiers. The thermal and chemical strain as well as corrosion rates must be accounted for in order to predict the lifetime of the gasifier containment materials.

William L. Headrick Jr; Musa Karakus; Xiaoting Liang

2005-07-01T23:59:59.000Z

24

REFRACTORY FOR BLACK LIQUOR GASIFIERS  

SciTech Connect (OSTI)

The University of Missouri-Rolla will identify materials that will permit the safe, reliable and economical operation of combined cycle gasifiers by the pulp and paper industry. The primary emphasis of this project will be to resolve the material problems encountered during the operation of low-pressure high-temperature (LPHT) and low-pressure low-temperature (LPLT) gasifiers while simultaneously understanding the materials barriers to the successful demonstration of high-pressure high-temperature (HPHT) black liquor gasifiers. This study will define the chemical, thermal and physical conditions in current and proposed gasifier designs and then modify existing materials and develop new materials to successfully meet the formidable material challenges. Resolving the material challenges of black liquor gasification combined cycle technology will provide energy, environmental, and economic benefits that include higher thermal efficiencies, up to three times greater electrical output per unit of fuel, and lower emissions. In the near term, adoption of this technology will allow the pulp and paper industry greater capital effectiveness and flexibility, as gasifiers are added to increase mill capacity. In the long term, combined-cycle gasification will lessen the industry's environmental impact while increasing its potential for energy production, allowing the production of all the mill's heat and power needs along with surplus electricity being returned to the grid. An added benefit will be the potential elimination of the possibility of smelt-water explosions, which constitute an important safety concern wherever conventional Tomlinson recovery boilers are operated. Developing cost-effective materials with improved performance in gasifier environments may be the best answer to the material challenges presented by black liquor gasification. Refractory materials may be selected/developed that either react with the gasifier environment to form protective surfaces in-situ; are functionally-graded to give the best combination of thermal, mechanical, and physical properties and chemical stability; or are relatively inexpensive, reliable repair materials. Material development will be divided into 2 tasks: Task 1, Development and property determinations of improved and existing refractory systems for black liquor containment. Refractory systems of interest include magnesium aluminate and barium aluminate for binder materials, both dry and hydratable, and materials with high alumina contents, 85-95 wt%, aluminum oxide, 5.0-15.0 wt%, and BaO, SrO, CaO, ZrO{sub 2} and SiC. Task 2, Finite element analysis of heat flow and thermal stress/strain in the refractory lining and steel shell of existing and proposed vessel designs. Stress and strain due to thermal and chemical expansion has been observed to be detrimental to the lifespan of existing black liquor gasifiers. The thermal and chemical strain as well as corrosion rates must be accounted for in order to predict the lifetime of the gasifier containment materials.

William L. Headrick Jr; Musa Karakus; Xiaoting Liang; Jun Wei

2005-01-01T23:59:59.000Z

25

Refractory for Black Liquor Gasifiers  

SciTech Connect (OSTI)

The University of Missouri-Rolla will identify materials that will permit the safe, reliable and economical operation of combined cycle gasifiers by the pulp and paper industry. The primary emphasis of this project will be to resolve the materials problems encountered during the operation of low-pressure high-temperature (LFHT) and low-pressure low-temperature (LPLT) gasifiers while simultaneously understanding the materials barriers to the successful demonstration of high-pressure high-temperature (HPHT) black liquor gasifiers. This study will define the chemical, thermal and physical conditions in current and proposed gasifier designs and then modify existing materials and develop new materials to successfully meet the formidable material challenges. Resolving the material challenges of black liquor gasification combined cycle technology will provide energy, environmental, and economic benefits that include higher thermal efficiencies, up to three times greater electrical output per unit of fuel, and lower emissions. In the near term, adoption of this technology will allow the pulp and paper industry greater capital effectiveness and flexibility, as gasifiers are added to increase mill capacity. In the long term, combined-cycle gasification will lessen the industry's environmental impact while increasing its potential for energy production, allowing the production of all the mill's heat and power needs along with surplus electricity being returned to the grid. An added benefit will be the potential elimination of the possibility of smelt-water explosions, which constitute an important safety concern wherever conventional Tomlinson recovery boilers are operated. Developing cost-effective materials with improved performance in gasifier environments may be the best answer to the material challenges presented by black liquor gasification. Refractory materials may be selected/developed that either react with the gasifier environment to form protective surfaces in-situ; are functionally-graded to give the best combination of thermal, mechanical, and physical properties and chemical stability; or are relatively inexpensive, reliable repair materials. Material development will be divided into 2 tasks: Task 1, Development and property determinations of improved and existing refractory systems for black liquor containment. Refractory systems of interest include magnesia aluminate and baria aluminate spinels for binder materials, both dry and hydratable, and materials with high alumina contents, 85-95 wt%, aluminum oxide, 5.0-15.0 wt%, and BaO, SrO, CaO, ZrO and SiC. Task 2, Finite element analysis of heat flow and thermal stress/strain in the refractory lining and steel shell of existing and proposed vessel designs. Stress and strain due to thermal and chemical expansion has been observed to be detrimental to the lifespan of existing black liquor gasifiers. The thermal and chemical strain as well as corrosion rates must be accounted for in order to predict the lifetime of the gasifier containment materials.

William L. Headrick Jr; Alireza Rezaie

2003-12-01T23:59:59.000Z

26

Refractory for Black Liquor Gasifiers  

SciTech Connect (OSTI)

The University of Missouri-Rolla identified materials that permit the safe, reliable and economical operation of combined cycle gasifiers by the pulp and paper industry. The primary emphasis of this project was to resolve the material problems encountered during the operation of low-pressure high-temperature (LPHT) and low-pressure low-temperature (LPLT) gasifiers while simultaneously understanding the materials barriers to the successful demonstration of high-pressure high-temperature (HPHT) black liquor gasifiers. This study attempted to define the chemical, thermal and physical conditions in current and proposed gasifier designs and then modify existing materials and develop new materials to successfully meet the formidable material challenges. Resolving the material challenges of black liquor gasification combined cycle technology will provide energy, environmental, and economic benefits that include higher thermal efficiencies, up to three times greater electrical output per unit of fuel, and lower emissions. In the near term, adoption of this technology will allow the pulp and paper industry greater capital effectiveness and flexibility, as gasifiers are added to increase mill capacity. In the long term, combined-cycle gasification will lessen the industry's environmental impact while increasing its potential for energy production, allowing the production of all the mill's heat and power needs along with surplus electricity being returned to the grid. An added benefit will be the potential elimination of the possibility of smelt-water explosions, which constitute an important safety concern wherever conventional Tomlinson recovery boilers are operated. Developing cost-effective materials with improved performance in gasifier environments may be the best answer to the material challenges presented by black liquor gasification. Refractory materials were selected or developed that reacted with the gasifier environment to form protective surfaces in-situ; and were functionally-graded to give the best combination of thermal, mechanical and physical properties and chemical stability; and are relatively inexpensive, reliable repair materials. Material development was divided into 2 tasks: Task 1 was development and property determinations of improved and existing refractory systems for black liquor containment. Refractory systems of interest include magnesium aluminate and barium aluminate for binder materials, both dry and hydratable, and materials with high alumina contents, 85-95 wt%, aluminum oxide, 5.0-15.0 wt%, and BaO, SrO, CaO, ZrO2 and SiC. Task 2 was finite element analysis of heat flow and thermal stress/strain in the refractory lining and steel shell of existing and proposed vessel designs. Stress and strain due to thermal and chemical expansion has been observed to be detrimental to the lifespan of existing black liquor gasifiers. The thermal and chemical strain as well as corrosion rates must be accounted for in order to predict the lifetime of the gasifier containment materials.

William L. Headrick Jr; Alireza Rezaie; Xiaoting Liang; Musa Karakus; Jun Wei

2005-12-01T23:59:59.000Z

27

REFRACTORY FOR BLACK LIQUOR GASIFIERS  

SciTech Connect (OSTI)

The University of Missouri-Rolla will identify materials that will permit the safe, reliable and economical operation of combined cycle gasifiers by the pulp and paper industry. The primary emphasis of this project will be to resolve the materials problems encountered during the operation of low-pressure high-temperature (LFHT) and low-pressure low-temperature (LPLT) gasifiers while simultaneously understanding the materials barriers to the successful demonstration of high-pressure high-temperature (HPHT) black liquor gasifiers. This study will define the chemical, thermal and physical conditions in current and proposed gasifier designs and then modify existing materials and develop new materials to successfully meet the formidable material challenges. Resolving the material challenges of black liquor gasification combined cycle technology will provide energy, environmental, and economic benefits that include higher thermal efficiencies, up to three times greater electrical output per unit of fuel, and lower emissions. In the near term, adoption of this technology will allow the pulp and paper industry greater capital effectiveness and flexibility, as gasifiers are added to increase mill capacity. In the long term, combined-cycle gasification will lessen the industry's environmental impact while increasing its potential for energy production, allowing the production of all the mill's heat and power needs along with surplus electricity being returned to the grid. An added benefit will be the potential elimination of the possibility of smelt-water explosions, which constitute an important safety concern wherever conventional Tomlinson recovery boilers are operated. Developing cost-effective materials with improved performance in gasifier environments may be the best answer to the material challenges presented by black liquor gasification. Refractory materials may be selected/developed that either react with the gasifier environment to form protective surfaces in-situ; are functionally-graded to give the best combination of thermal, mechanical, and physical properties and chemical stability; or are relatively inexpensive, reliable repair materials. Material development will be divided into 2 tasks: Task 1, Development and property determinations of improved and existing refractory systems for black liquor containment. Refractory systems of interest include magnesia aluminate and baria aluminate spinels for binder materials, both dry and hydratable, and materials with high alumina contents, 85-95 wt%, aluminum oxide, 5.0-15.0 wt%, and BaO, SrO, CaO, ZrO and SiC. Task 2, Finite element analysis of heat flow and thermal stress/strain in the refractory lining and steel shell of existing and proposed vessel designs. Stress and strain due to thermal and chemical expansion has been observed to be detrimental to the lifespan of existing black liquor gasifiers. The thermal and chemical strain as well as corrosion rates must be accounted for in order to predict the lifetime of the gasifier containment materials.

William L. Headrick Jr.; Alireza Rezaie

2003-12-01T23:59:59.000Z

28

Refractory for Black Liquor Gasifiers  

SciTech Connect (OSTI)

The University of Missouri-Rolla will identify materials that will permit the safe, reliable and economical operation of combined cycle gasifiers by the pulp and paper industry. The primary emphasis of this project will be to resolve the materials problems encountered during the operation of low-pressure high-temperature (LFHT) and low-pressure low-temperature (LPLT) gasifiers while simultaneously understanding the materials barriers to the successful demonstration of high-pressure high-temperature (HPHT) black liquor gasifiers. This study will define the chemical, thermal and physical conditions in current and proposed gasifier designs and then modify existing materials and develop new materials to successfully meet the formidable material challenges. Resolving the material challenges of black liquor gasification combined cycle technology will provide energy, environmental, and economic benefits that include higher thermal efficiencies, up to three times greater electrical output per unit of fuel, and lower emissions. In the near term, adoption of this technology will allow the pulp and paper industry greater capital effectiveness and flexibility, as gasifiers are added to increase mill capacity. In the long term, combined-cycle gasification will lessen the industry's environmental impact while increasing its potential for energy production, allowing the production of all the mill's heat and power needs along with surplus electricity being returned to the grid. An added benefit will be the potential elimination of the possibility of smelt-water explosions, which constitute an important safety concern wherever conventional Tomlinson recovery boilers are operated. Developing cost-effective materials with improved performance in gasifier environments may be the best answer to the material challenges presented by black liquor gasification. Refractory materials may be selected/developed that either react with the gasifier environment to form protective surfaces in-situ; are functionally-graded to give the best combination of thermal, mechanical, and physical properties and chemical stability; or are relatively inexpensive, reliable repair materials. Material development will be divided into 2 tasks: Task 1, Development and property determinations of improved and existing refractory systems for black liquor containment. Refractory systems of interest include magnesia aluminate and baria aluminate spinels for binder materials, both dry and hydratable, and materials with high alumina contents, 85-95 wt%, aluminum oxide, 5.0-15.0 wt%, and BaO, SrO, CaO, ZrO and SiC. Task 2, Finite element analysis of heat flow and thermal stress/strain in the refractory lining and steel shell of existing and proposed vessel designs. Stress and strain due to thermal and chemical expansion has been observed to be detrimental to the lifespan of existing black liquor gasifiers. The thermal and chemical strain as well as corrosion rates must be accounted for in order to predict the lifetime of the gasifier containment materials.

William L. Headrick Jr; Alireza Rezaie

2003-08-01T23:59:59.000Z

29

Refractory for Black Liquor Gasifiers  

SciTech Connect (OSTI)

The University of Missouri-Rolla will identify materials that will permit the safe, reliable and economical operation of combined cycle gasifiers by the pulp and paper industry. The primary emphasis of this project will be to resolve the materials problems encountered during the operation of low-pressure high-temperature (LFHT) and low-pressure low-temperature (LPLT) gasifiers while simultaneously understanding the materials barriers to the successful demonstration of high-pressure high-temperature (HPHT) black liquor gasifiers. This study will define the chemical, thermal and physical conditions in current and proposed gasifier designs and then modify existing materials and develop new materials to successfully meet the formidable material challenges. Resolving the material challenges of black liquor gasification combined cycle technology will provide energy, environmental, and economic benefits that include higher thermal efficiencies, up to three times greater electrical output per unit of fuel, and lower emissions. In the near term, adoption of this technology will allow the pulp and paper industry greater capital effectiveness and flexibility, as gasifiers are added to increase mill capacity. In the long term, combined-cycle gasification will lessen the industry's environmental impact while increasing its potential for energy production, allowing the production of all the mill's heat and power needs along with surplus electricity being returned to the grid. An added benefit will be the potential elimination of the possibility of smelt-water explosions, which constitute an important safety concern wherever conventional Tomlinson recovery boilers are operated. Developing cost-effective materials with improved performance in gasifier environments may be the best answer to the material challenges presented by black liquor gasification. Refractory materials may be selected/developed that either react with the gasifier environment to form protective surfaces in-situ; are functionally-graded to give the best combination of thermal, mechanical, and physical properties and chemical stability; or are relatively inexpensive, reliable repair materials. Material development will be divided into 2 tasks: Task 1, Development and property determinations of improved and existing refractory systems for black liquor containment. Refractory systems of interest include magnesia aluminate and baria aluminate spinels for binder materials, both dry and hydratable, and materials with high alumina contents, 85-95 wt%, aluminum oxide, 5.0-15.0 wt%, and BaO, SrO, CaO, ZrO and SiC. Task 2, Finite element analysis of heat flow and thermal stress/strain in the refractory lining and steel shell of existing and proposed vessel designs. Stress and strain due to thermal and chemical expansion has been observed to be detrimental to the lifespan of existing black liquor gasifiers. The thermal and chemical strain as well as corrosion rates must be accounted for in order to predict the lifetime of the gasifier containment materials.

Robert E. Moore; William L. Headrick; Alireza Rezaie

2003-03-31T23:59:59.000Z

30

Mill Integration-Pulping, Stream Reforming and Direct Causticization for Black Liquor Recovery  

SciTech Connect (OSTI)

MTCI/StoneChem developed a steam reforming, fluidized bed gasification technology for biomass. DOE supported the demonstration of this technology for gasification of spent wood pulping liquor (or 'black liquor') at Georgia-Pacific's Big Island, Virginia mill. The present pre-commercial R&D project addressed the opportunities as well as identified negative aspects when the MTCI/StoneChem gasification technology is integrated in a pulp mill production facility. The opportunities arise because black liquor gasification produces sulfur (as H{sub 2}S) and sodium (as Na{sub 2}CO{sub 3}) in separate streams which may be used beneficially for improved pulp yield and properties. The negative aspect of kraft black liquor gasification is that the amount of Na{sub 2}CO{sub 3} which must be converted to NaOH (the so called causticizing requirement) is increased. This arises because sulfur is released as Na{sub 2}S during conventional kraft black liquor recovery, while during gasification the sodium associated Na{sub 2}S is partly or fully converted to Na{sub 2}CO{sub 3}. The causticizing requirement can be eliminated by including a TiO{sub 2} based cyclic process called direct causticization. In this process black liquor is gasified in the presence of (low sodium content) titanates which convert Na{sub 2}CO{sub 3} to (high sodium content) titanates. NaOH is formed when contacting the latter titanates with water, thereby eliminating the causticizing requirement entirely. The leached and low sodium titanates are returned to the gasification process. The project team comprised the University of Maine (UM), North Carolina State University (NCSU) and MTCI/ThermoChem. NCSU and MTCI are subcontractors to UM. The principal organization for the contract is UM. NCSU investigated the techno-economics of using advanced pulping techniques which fully utilize the unique cooking liquors produced by steam reforming of black liquor (Task 1). UM studied the kinetics and agglomeration problems of the conversion of Na{sub 2}CO{sub 3} to (high sodium) titanates during gasification of black liquor in the presence of (low sodium) titanates or TiO{sub 2} (Task 2). MTCI/ThermoChem tested the performance and operability of the combined technology of steam reforming and direct causticization in their Process Development Unit (PDU) (Task 3). The specific objectives were: (1) to investigate how split sulfidity and polysulfide (+ AQ) pulping can be used to increase pulp fiber yield and properties compared to conventional kraft pulping; (2) to determine the economics of black liquor gasification combined with these pulping technologies in comparison with conventional kraft pulping and black liquor recovery; (3) to determine the effect of operating conditions on the kinetics of the titanate-based direct causticization reaction during black liquor gasification at relatively low temperatures ({le} 750 C); (4) to determine the mechanism of particle agglomeration during gasification of black liquor in the presence of titanates at relatively low temperatures ({le} 750 C); and (5) to verify performance and operability of the combined technology of steam reforming and direct causticization of black liquor in a pilot scale fluidized bed test facility.

Adriaan van Heiningen

2007-06-30T23:59:59.000Z

31

Refractory for Black Liquor Gasifiers  

SciTech Connect (OSTI)

The University of Missouri-Rolla will identify materials that will permit the safe, reliable and economical operation of combined cycle gasifiers by the pulp and paper industry. The primary emphasis of this project will be to resolve the material problems encountered during the operation of low-pressure high-temperature (LPHT) and low-pressure low-temperature (LPLT) gasifiers while simultaneously understanding the materials barriers to the successful demonstration of high-pressure high-temperature (HPHT) black liquor gasifiers. This study will define the chemical, thermal and physical conditions in current and proposed gasifier designs and then modify existing materials and develop new materials to successfully meet the formidable material challenges. Resolving the material challenges of black liquor gasification combined cycle technology will provide energy, environmental, and economic benefits that include higher thermal efficiencies, up to three times greater electrical output per unit of fuel, and lower emissions. In the near term, adoption of this technology will allow the pulp and paper industry greater capital effectiveness and flexibility, as gasifiers are added to increase mill capacity. In the long term, combined-cycle gasification will lessen the industry's environmental impact while increasing its potential for energy production, allowing the production of all the mill's heat and power needs along with surplus electricity being returned to the grid. An added benefit will be the potential elimination of the possibility of smelt-water explosions, which constitute an important safety concern wherever conventional Tomlinson recovery boilers are operated. Developing cost-effective materials with improved performance in gasifier environments may be the best answer to the material challenges presented by black liquor gasification. Refractory materials may be selected/developed that either react with the gasifier environment to form protective surfaces in-situ; are functionally-graded to give the best combination of thermal, mechanical, and physical properties and chemical stability; or are relatively inexpensive, reliable repair materials. This report covers Task 1.4, Industrial Trial of candidate materials developed by refractory producers and in the laboratory based on the results of Task 1.1, 1.2 and 1.3. Refractories provided by in-kind sponsors to industrial installations tested by cup testing, density/porosity determinations, chemical analysis and microscopy. None of the materials produced in this program have been tried in high temperature gasifiers, but the mortar developed Morcocoat SP-P is outperforming other mortars tested at ORNL. MORCO PhosGun M-90-O has shown in laboratory testing to be an acceptable candidate for hot and cold repairs of existing high temperature gasifiers. It may prove to be an acceptable lining material.

William L. Headrick Jr; Musa Karakus; Xiaoting Laing

2005-10-01T23:59:59.000Z

32

Black liquor gasifier/gas turbine cogeneration  

SciTech Connect (OSTI)

The kraft process dominates pulp and paper production worldwide. Black liquor, a mixture of lignin and inorganic chemicals, is generated in this process as fiber is extracted from wood. At most kraft mills today, black liquor is burned in Tomlinson boilers to produce steam for on-site heat and power and to recover the inorganic chemicals for reuse in the process. Globally, the black liquor generation rate is about 85,000 MW{sub fuel} (or 0.5 million tonnes of dry solids per day), with nearly 50% of this in North America. The majority of presently installed Tomlinson boilers will reach the end of their useful lives during the next 5 to 20 years. As a replacement for Tomlinson-based cogeneration, black liquor-gasifier/gas turbine cogeneration promises higher electrical efficiency, with prospective environmental, safety, and capital cost benefits for kraft mills. Several companies are pursuing commercialization of black liquor gasification for gas turbine applications. This paper presents results of detailed performance modeling of gasifier/gas turbine cogeneration systems using different black liquor gasifiers modeled on proposed commercial designs.

Consonni, S. [Politecnico di Milano (Italy). Dept. di Energetica; Larson, E.D.; Keutz, T.G. [Princeton Univ., NJ (United States); Berglin, N. [Chalmers Univ. of Technology, Goteborg (Sweden). Dept. of Heat and Power Technology

1998-07-01T23:59:59.000Z

33

Pulsed combustion process for black liquor gasification  

SciTech Connect (OSTI)

The objective of this project is to test an energy efficient, innovative black liquor recovery system on an industrial scale. In the MTCI recovery process, black liquor is sprayed directly onto a bed of sodium carbonate solids which is fluidized by steam. Direct contact of the black liquor with hot bed solids promotes high rates of heating and pyrolysis. Residual carbon, which forms as a deposit on the particle surface, is then gasified by reaction with steam. Heat is supplied from pulse combustor resonance tubes which are immersed within the fluid bed. A portion of the gasifier product gas is returned to the pulse combustors to provide the energy requirements of the reactor. Oxidized sulfur species are partially reduced by reaction with the gasifier products, principally carbon monoxide and hydrogen. The reduced sulfur decomposed to solid sodium carbonate and gaseous hydrogen sulfide (H{sub 2}S). Sodium values are recovered by discharging a dry sodium carbonate product from the gasifier. MTCI's indirectly heated gasification technology for black liquor recovery also relies on the scrubbing of H{sub 2}S for product gases to regenerate green liquor for reuse in the mill circuit. Due to concerns relative to the efficiency of sulfur recovery in the MTCI integrated process, an experimental investigation was undertaken to establish performance and design data for this portion of the system.

Durai-Swamy, K.; Mansour, M.N.; Warren, D.W.

1991-02-01T23:59:59.000Z

34

Improved recovery of tall oil from black liquors  

SciTech Connect (OSTI)

Applying a d.c. of less than 15 V to acidified black liquor separates a significant amount of tall oil remaining in the black liquor sludge. An apparatus with graphite electrodes for this process is described.

Zucker, J.

1980-12-09T23:59:59.000Z

35

In Situ Causticizing for Black Liquor Gasification  

SciTech Connect (OSTI)

Black liquor gasification offers a number of attractive incentives to replace Tomlinson boilers but it also leads to an increase in the causticizing load. Reasons for this have been described in previous reports (FY04 ERC, et.al.). The chemistries have also been covered but will be reviewed here briefly. Experimental results of the causticizing reactions with black liquor are presented here. Results of the modeling work were presented in detail in the Phase 1 report. They are included in Table 2 for comparison but will not be discussed in detail. The causticizing agents were added to black liquor in the ratios shown in Table 1, mixed, and then spray-dried. The mixture ratios (doping levels) reflect amount calculated from the stoichiometry above to achieve specified conversions shown in the table. The solids were sieved to 63-90 microns for use in the entrained flow reactors. The firing conditions are shown in Table 2. Pictures and descriptions of the reactors can be found in the Phase 1 annual report. Following gasification, the solids (char) was collected and analyzed by coulometric titration (for carbonate and total carbon), and by inductively coupled plasma emission spectroscopy (ICP) for a wide array of metals.

Scott Alan Sinquefield

2005-10-01T23:59:59.000Z

36

Electrochemical treatment of black liquor from straw pulping  

SciTech Connect (OSTI)

The conventional black liquor regeneration process is not always suitable for pulping plants of nonwood fibers due to the unfavorable ratio of organic to inorganic solids. This paper presents an alternative treatment based on an electrolysis process of the soda black liquor from straw pulping. This alternative method minimizes the environmental impact by recovering the caustic at the same time that the liquor is acidified, which favors the later separation of the lignin.

Blanco, M.A.; Negro, C.; Tijero, J. [Complutense Univ., Madrid (Spain)] [and others

1996-11-01T23:59:59.000Z

37

Thermal processing of black liquor from alkaline straw pulping  

SciTech Connect (OSTI)

Black liquor is the wastewater from the cooking of wood or straw in the production of pulp and paper. Nowadays new processes are being investigated as alternatives to the traditional recovery boiler used for black liquor treatment. One of the processes which appears to be more promising is gasification, for which further research is needed for its full industrial implementation. There is not much data about the behavior of soda black liquors from straw cooking in the literature. Therefore the thermal decomposition of one of these liquors has been studied in a thermobalance, in inert (N{sub 2}) atmosphere. The kinetic constants from isothermal experiments have been obtained.

Sanchez, J.L.; Garcia, L.; Gea, G.; Bilbao, R.; Arauzo, J. [Univ. of Zaragoza (Spain)

1996-12-31T23:59:59.000Z

38

Physical properties of Kraft Black Liquor. Interim report, Phase II  

SciTech Connect (OSTI)

Objectives are to determine the rheological, thermal, and surface properties of Kraft Black Liquors, and to relate these properties to the chemical composition and to pulping conditions. A four-variable, multi-level pulping experiment is being conducted. Pulping results are reported. Complete analyses of the liquors have been done. Thermal analyses have been done. DSC was employed to determine heat capacities of black liquors and lignins. Rheological (viscosity) studies are being conducted. Density and thermal expansion have been studied for seven liquors. Energy savings through more efficient recovery systems are appreciable.

Fricke, A.L.

1985-03-01T23:59:59.000Z

39

Fundamental studies of black liquor combustion  

SciTech Connect (OSTI)

The fundamentals of black liquor combustion are being studied in a project being carried out for the US Department of Energy by the Institute of Paper Science Technology (IPST, formerly the Institute of Paper Chemistry) and the National Institute of Science Technology (NIST, formerly the National Bureau of Standards). The project was divided into four phases. This report covers the completion of Phase 1 (in-flight processes), the results of all of the work on Phase 2 (char bed processes), Phase 3 (fume processes), and Phase 4 (furnace simulation). 41 refs., 62 figs., 30 tabs.

Clay, D.T.; Lien, S.J.; Grace, T.M.; Brown, C.A.; Empie, H.L.; Macek, A.; Amin, N.; Charangundla, S.R.

1990-03-01T23:59:59.000Z

40

Effect of pulping conditions and black liquor composition on Newtonian viscosity of high solids kraft black liquors  

SciTech Connect (OSTI)

The influence of black liquor composition and solids concentrations on the Newtonian viscosity of slash pine black liquors over wide ranges of temperature (up to 140 C) and solids concentrations (between 50% and 83% solids) has been studied. It was found that the zero shear rate viscosity of high solids black liquors depends strongly on the cooking conditions and/or black liquor composition. Not only is high solids viscosity affected by lignin molecular weight and lignin concentration in the liquor but other organic and inorganic constituents of black liquor also make a significant contribution to viscosity. The dependency of zero shear rate viscosity on solids concentrations, and temperature is defined. The Newtonian viscosities vary over a wide range depending on temperature, solids concentrations and solids composition. The results indicate that, at fixed levels of effective alkali and sulfidity, the zero shear rate viscosities can be described as a function of both lignin concentration and lignin molecular weight. The viscosity of black liquor is an increasing function of the organics-to-inorganics ratio and is a decreasing function of the concentration of sodium and chloride ions and pH of the liquor.

Zaman, A.A.; Fricke, A.L. [Univ. of Florida, Gainesville, FL (United States). Dept. of Chemical Engineering] [Univ. of Florida, Gainesville, FL (United States). Dept. of Chemical Engineering

1996-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Liquor Activity Reduction (LAR) Programme - 12397  

SciTech Connect (OSTI)

Waste material from the reprocessing of irradiated fuel has been stored under water for several decades leading to the water becoming highly radioactive. As a critical enabler to the decommissioning strategy for the Sellafield site, the Liquor Activity Reduction (LAR) programme has been established to provide a processing route for this highly radioactive liquor. This paper reviews the progress that has been made since the start of routine LAR transfer cycles (July 2010) and follows on from the earlier paper presented at WM2011. The paper focuses on the learning from the first full year of routine LAR transfer cycles and the application of this learning to the wider strategies for the treatment of further radioactive liquid effluents on the Sellafield site. During this period over 100,000 Curies of radioactivity has been safely removed and treated. The past year has witnessed the very successful introduction of the LAR programme. This has lead to hazard reduction at MSSS and demonstration that the SIXEP facility can meet the significantly increased challenge that the LAR programme represents. Part of the success has been the ability to predict and deliver a realistic production schedule with the availability of the MSSS, EDT and SIXEP facilities being central to this. Most importantly, the LAR programme has been successful in bringing together key stakeholders to deliver this work while integrating with the existing, day to day, demands of the Sellafield site. (authors)

Pether, Colin; Carrol, Phil; Birkett, Eddie; Kibble, Matthew [Sellafield Ltd, Cumbria (United Kingdom)

2012-07-01T23:59:59.000Z

42

Proceedings of the black liquor research program review fourth meeting held July 28--30, 1987  

SciTech Connect (OSTI)

Research programs, presented at the black liquor review meeting are described. Research topics include the following: Cooperative Program in Kraft Recovery; Black Liquor Physical Properties; Viscosity of Strong Black Liquor; Ultrafiltration of Kraft Black Liquor; Molecular Weight Distribution of Kraft Lignin; Black Liquor Droplet Formation Project; Fundamental Studies of Black Liquor Combustion; Black Liquor Combustion Sensors; Flash X-ray Imagining of Black Liquor Sprays; Laser Induced Fluorescence For Process Control In The Pulp and Paper Industry; Recovery Boiler Optimization; Black Liquor Gasification and Use of the Products in Combined-Cycle Cogeneration; Black Liquor Steam Plasma Automization; The B and W Pyrosonic 2000R System; Monsteras Boiler Control System; and Cooperative Program Project Reviews. Individual projects are processed separately for the data bases.

Emerson, D. B.; Whitworth, B. A.

1987-10-01T23:59:59.000Z

43

Char reactions during kraft black liquor pyrolysis  

SciTech Connect (OSTI)

The pyrolysis characteristics of dried black liquor particles were investigated at high heating rates in a laminar entrained-flow reactor at temperatures of 600-1100{degrees}C. Primary pyrolysis of the organic fraction occurred very rapidly, in less 0.5 seconds. Char yields at the end or volatiles evolution were 58-72%. The decreased with increasing reactor temperature to 900{degrees}C but remained constant at higher temperatures. 35-65% of the fuel nitrogen was volatilized, nearly all in less than 0.5 s. Relatively little fuel nitrogen was evolved from the char. Significant alkali metal chloride volatization from the char occurred at all temperatures, while additional sodium volatilization became important above 900{degrees}C. Reduction of sulfur species in the char increased rapidly with increasing temperature. A temperature-dependent delay time in the onset of Na{sub 2}S formation was observed.

Frederick, W.J.; Sricharoenchaikul, V.; Reis, V.V. [Oregon State Univ., Corvallis, OR (United States)

1995-12-01T23:59:59.000Z

44

Demonstration of Black Liquor Gasification at Big Island  

SciTech Connect (OSTI)

This Final Technical Report provides an account of the project for the demonstration of Black Liquor Gasification at Georgia-Pacific LLC's Big Island, VA facility. This report covers the period from May 5, 2000 through November 30, 2006.

Robert DeCarrera

2007-04-14T23:59:59.000Z

45

Drum drying of black liquor using superheated steam impinging jets  

SciTech Connect (OSTI)

A novel drum dryer for black liquor utilizing multiple impinging jets of superheated steam was designed and built to evaluate the performance characteristics and effects of various operating parameters thereon. Appropriate ranges of parameters such as steam jet temperature and velocity were examined experimentally to quantify the optimal operating conditions for the formation of black liquor film on the drum surface as well as the drying kinetics.

Shiravi, A.H.; Mujumdar, A.S.; Kubes, G.J. [McGill Univ., Montreal, Quebec (Canada)

1997-05-01T23:59:59.000Z

46

Controlled black liquor viscosity reduction through salting-in  

SciTech Connect (OSTI)

Black liquor viscosity increases exponentially with solids content and therefore causes processing problems for the paper industry by being a limiting factor in the Kraft pulp process. This study investigates a new approach for achieving viscosity reduction by salting-in black liquor through the addition of thiocyanate salts. These salts generally increase the solubility of the polymer constituents in black liquor, leading to a decrease in its viscosity. Several thiocyanate salts capable of reducing liquor viscosity by more than two orders of magnitude have been identified, with viscosity reduction greatest at high solids content. Salting-in of black liquor depends on the cation paired with the thiocyanate anion, as well as on solution pH and temperature. Comparative studies reveal the most effective viscosity-reducing agent of the series examined and that lignin plays an important role in the viscosity behavior of both unmodified and salted-in black liquor at high solids concentrations. These experimental findings are interpreted in terms of the underlying principles that describe salting-in and how it affects aqueous solution structure.

Roberts, J.E.; Khan, S.A.; Spontak, R.J. [North Carolina State Univ., Raleigh, NC (United States)] [North Carolina State Univ., Raleigh, NC (United States)

1996-08-01T23:59:59.000Z

47

Measurement of black liquor surface tension: Technical report No. 3. [Black liquor  

SciTech Connect (OSTI)

Surface tension and density of two kraft black liquors were measured at a series of temperatures, from a minimum value when gas bubbles can be blown into the liquor to a maximum value near the elevated boiling point of a particular sample. Available methods for the measurement of surface tension were evaluated critically and, as a result, the maximum bubble pressure method was selected. Varying the flow rate of the gas changes the frequency of bubble formation and thereby the age of the surface. The parameter has been utilized by many researchers to monitor the diffusion of low surface energy components (e.g., surfactants) to the liquid/air interface. The effect of bubble frequency when tested with a few pure liquids, indicated that the dynamics of bubble formation had to be further examined to separate out inertial and viscous effects from purely surface tension related pressure. The pressure versus flow rate data were extrapolated to zero flow rate and surface tension and density were calculated using these extrapolated values. As expected, surface tension decreased with increasing temperature for all the samples. Surface tension decreases with increasing solids content (when compared with the value for water) to a certain level (about 20%) and it starts to increase again. The decrease in surface tension in the dilute black liquor, is probably due to the decrease in the concentration of water, which has a high surface tension value. The occurrence of the minimum is probably due to the effect of inorganic components dominating over the effect of surfactants and other components. Reduction in the solubilities of the inorganics, promotion of micelles of the surfactants and reduction in the diffusion of surfactants to the surface, also could contribute to this phenomenon. 54 refs., 54 figs., 12 tabs.

Krishnagopalan, J.

1987-09-01T23:59:59.000Z

48

Recaustization of kraft black liquor via bipolar electrodialysis  

SciTech Connect (OSTI)

The US Department of Energy in conjunction with HPD Inc. supported a research program to perform a laboratory feasibility study with various black liquor samples for the recaustization of these samples via bipolar electrodialysis. The research was conducted at the HPD pilot plant facility in Plainfield, Illinois, beginning in April 1989. This report is a summary of the work completed thru November 1989. The program was designed to operate the electrodialyzer in order to obtain performance and engineering data such as current efficiency, power consumption per gram of NaOH produced, and assess fouling and/or membrane durability. Prior to the electrodialysis laboratory runs, the black liquor samples were pretreated in order to remove as much lignin as possible. The black liquor samples were air oxidized, acidified to pH = 9.0 and pH = 2.0 and later filtered via a Buchner funnel under vacuum. The filtrate was then utilized to become the feed to the electrodialysis stack. Initial test runs were performed with synthetic solutions of either sodium sulfate or sodium bicarbonate in order to determine acceptable operating current, power, current efficiencies, and fouling behavior. A second set of test were conducted with a series of four Southern Kraft black liquor samples. Based on the results of this study, it was determined that the use of bipolar electrodialysis for producing a caustic stream and an acidified black liquor stream is feasible and was demonstrated. 9 refs., 27 figs., 32 tabs.

Koumoundouros, J.A.; Oshen, S.; Lynch, J.D.

1990-05-01T23:59:59.000Z

49

Ultrafiltration of kraft black liquor: Final report, Phase 3  

SciTech Connect (OSTI)

Since 1981, a research program has been in progress to determine the physical properties of kraft black liquors and to develop methods for reduction of data and correlation of properties with pumping conditions. The basic premise that has been used to direct the research program is that kraft black liquor behaves as a polymer solution, particularly at high solids, and that the behavior is dominated by the characteristics of the lignin present. This premise is proving to be correct, and the principles that follow from this premise are proving to be successful for data reduction and correlation. The research has been a complex program involving experimental pulping, chemical analysis, lignin separation and characterization, thermal analysis, rheological measurements, and considerable equipment and methods development. Due to the complexity of the program, the unforeseen need to expend a great deal of effort in development of experimental techniques for analysis, and the fact that our liquors proved to be unstable at high temperatures and solids, all of the original objectives could not be accomplished. However, our program has added substantially to the body of knowledge of physical properties of black liquor. Our results indicate that the goal of developing correlations for physical properties of kraft black liquor is practical and can be realized through extension of the present work. 21 refs., 32 figs.

Hill, M.K.

1988-04-01T23:59:59.000Z

50

Black liquor gasification phase 2D final report  

SciTech Connect (OSTI)

This report covers work conducted by Rockwell International under Amendment 5 to Subcontract STR/DOE-12 of Cooperative Agreement DE-AC-05-80CS40341 between St. Regis Corporation (now Champion International) and the Department of Energy (DOE). The work has been designated Phase 2D of the overall program to differentiate it from prior work under the same subcontract. The overall program is aimed at demonstrating the feasibility of and providing design data for the Rockwell process for gasifying Kraft black liquor. In this process, concentrated black liquor is converted into low-Btu fuel gas and reduced melt by reaction with air in a specially designed gasification reactor.

Kohl, A.L.; Stewart, A.E.

1988-06-01T23:59:59.000Z

51

Advancement of High Temperature Black Liquor Gasification Technology  

SciTech Connect (OSTI)

Weyerhaeuser operates the world's only commercial high-temperature black liquor gasifier at its pulp mill in New Bern, NC. The unit was started-up in December 1996 and currently processes about 15% of the mill's black liquor. Weyerhaeuser, Chemrec AB (the gasifier technology developer), and the U.S. Department of Energy recognized that the long-term, continuous operation of the New Bern gasifier offered a unique opportunity to advance the state of high temperature black liquor gasification toward the commercial-scale pressurized O2-blown gasification technology needed as a foundation for the Forest Products Bio-Refinery of the future. Weyerhaeuser along with its subcontracting partners submitted a proposal in response to the 2004 joint USDOE and USDA solicitation - 'Biomass Research and Development Initiative'. The Weyerhaeuser project 'Advancement of High Temperature Black Liquor Gasification' was awarded USDOE Cooperative Agreement DE-FC26-04NT42259 in November 2004. The overall goal of the DOE sponsored project was to utilize the Chemrec{trademark} black liquor gasification facility at New Bern as a test bed for advancing the development status of molten phase black liquor gasification. In particular, project tasks were directed at improvements to process performance and reliability. The effort featured the development and validation of advanced CFD modeling tools and the application of these tools to direct burner technology modifications. The project also focused on gaining a fundamental understanding and developing practical solutions to address condensate and green liquor scaling issues, and process integration issues related to gasifier dregs and product gas scrubbing. The Project was conducted in two phases with a review point between the phases. Weyerhaeuser pulled together a team of collaborators to undertake these tasks. Chemrec AB, the technology supplier, was intimately involved in most tasks, and focused primarily on the design, specification and procurement of facility upgrades. Chemrec AB is also operating a pressurized, O2-blown gasifier pilot facility in Piteaa, Sweden. There was an exchange of knowledge with the pressurized projects including utilization of the experimental results from facilities in Piteaa, Sweden. Resources at the Georgia Tech Research Corporation (GTRC, a.k.a., the Institute of Paper Science and Technology) were employed primarily to conduct the fundamental investigations on scaling and plugging mechanisms and characterization of green liquor dregs. The project also tapped GTRC expertise in the development of the critical underlying black liquor gasification rate subroutines employed in the CFD code. The actual CFD code development and application was undertaken by Process Simulation, Ltd (PSL) and Simulent, Ltd. PSL focused on the overall integrated gasifier CFD code, while Simulent focused on modeling the black liquor nozzle and description of the black liquor spray. For nozzle development and testing Chemrec collaborated with ETC (Energy Technology Centre) in Piteae utilizing their test facility for nozzle spray investigation. GTI (Gas Technology Institute), Des Plains, IL supported the team with advanced gas analysis equipment during the gasifier test period in June 2005.

Craig Brown; Ingvar Landalv; Ragnar Stare; Jerry Yuan; Nikolai DeMartini; Nasser Ashgriz

2008-03-31T23:59:59.000Z

52

A comprehensive program to develop correlations for physical properties of kraft black liquor. Final report  

SciTech Connect (OSTI)

The overall objective of the program was to develop correlations to predict physical properties within requirements of engineering precision from a knowledge of pulping conditions and of kraft black liquor composition, if possible. These correlations were to include those relating thermodynamic properties to pulping conditions and liquor composition. The basic premise upon which the research was based is the premise that black liquor behaves as a polymer solution. This premise has proven to be true, and has been used successfully in developing data reduction methods and in interpreting results. A three phase effort involving pulping, analysis of liquor composition, and measurement of liquor properties was conducted.

Fricke, A.L.; Zaman, A.A.

1998-05-01T23:59:59.000Z

53

Report on the WORKSHOP ON COMMERCIALIZATION OF BLACK LIQUOR  

E-Print Network [OSTI]

Report on the WORKSHOP ON COMMERCIALIZATION OF BLACK LIQUOR AND BIOMASS GASIFICATION FOR GAS or industry cycle (BGCC) technologies for pulp and paper co~mitm~nt to the develo~ment of gasification systems (existing) technology with an greenhouse gas emissions mitigation measures. emerging (gasification

54

CHAMPAIGN-URBANA FOOD AND LIQUOR GUIDE 1. Introduction  

E-Print Network [OSTI]

(217) 352-7467. Excellent Mexican and Latin American- influenced food. Service can be a bit slowCHAMPAIGN-URBANA FOOD AND LIQUOR GUIDE 1. Introduction This is a short, incomplete, and personally. It is standard to tip 15-20% for reasonable service. A indicates a place that we like, and indicates a place we

Athreya, Jayadev

55

Sodium and sulfur release and recapture during black liquor burning  

SciTech Connect (OSTI)

The objective of this study was to provide data on sulfur and sodium volatilization during black liquor burning, and on SO2 capture by solid sodium carbonate and sodium chloride. This data was interpreted and modeled into rate equations suitable for use in computational models for recovery boilers.

Frederick, W.J.; Iisa, K.; Wag, K.; Reis, V.V.; Boonsongsup, L.; Forssen, M.; Hupa, M.

1995-08-01T23:59:59.000Z

56

In situ analysis of ash deposits from black liquor combustion  

SciTech Connect (OSTI)

Aerosols formed during combustion of black liquor cause a significant fire-side fouling problem in pulp mill recovery boilers. The ash deposits reduce heat transfer effectiveness, plug gas passages, and contribute to corrosion. Both vapors and condensation aerosols lead to the formation of such deposits. The high ash content of the fuel and the low dew point of the condensate salts lead to a high aerosol and vapor concentration in most boilers. In situ measurements of the chemical composition of these deposits is an important step in gaining a fundamental understanding of the deposition process. Infrared emission spectroscopy is used to characterize the composition of thin film deposits resulting from the combustion of black liquor and the deposition of submicron aerosols and vapors. New reference spectra of Na{sub 2}SO{sub 4}, K{sub 2}SO{sub 4}, Na{sub 2}CO{sub 3} and K{sub 2}CO{sub 3} pure component films were recorded and compared with the spectra of the black liquor deposit. All of the black liquor emission bands were identified using a combination of literature data and ab initio calculations. Ab initio calculations also predict the locations and intensities of bands for the alkali vapors of interest. 39 refs., 9 figs.

Bernath, P. [Sandia National Labs., Livermore, CA (United States). Combustion Research Facility]|[Univ. of Toronto, Ontario (Canada); Sinquefield, S.A. [Sandia National Labs., Livermore, CA (United States). Combustion Research Facility]|[Oregon State Univ., Eugene, OR (United States); Baxter, L.L.; Sclippa, G.; Rohlfing, C. [Sandia National Labs., Livermore, CA (United States). Combustion Research Facility; Barfield, M. [Sandia National Labs., Livermore, CA (United States). Combustion Research Facility]|[Univ. of Arizona, Tucson, AZ (United States)

1996-05-01T23:59:59.000Z

57

A comprehensive program to develop correlations for the physical properties of kraft black liquors  

SciTech Connect (OSTI)

Experimental work includes pulping, liquor analysis, lignin purification and characterization, vapor-liquid equilibria, heat capacity, heats of solution and combustion, and viscosity measurements. It is now possible to operate the digester as a closed, rotating reactor or as a batch reactor with liquor circulation. When operated with liquor circulation, temperatures within the chip bed can be monitored during cooking. Cooking is reproducible, and cooks are being performed to produce liquors for experimental studies. The digester could be further modified to permit them to conduct rapid exchange batch pulping or to permit them to simulate continuous pulping. Liquors are now routinely analyzed to determine all components, except higher molecular weight organic acids and extractives. Lignin determination by UV-visible means has been improved. Lignin purification from black liquor has been improved and lignin molecular weights are determined routinely. The paper describes the digestor, the large scale evaporation, liquor analysis, thermal studies, and viscosity results. 31 figs., 5 tabs.

Fricke, A.L.

1990-12-01T23:59:59.000Z

58

Recovery of solvent and by-products from organosolv black liquor  

SciTech Connect (OSTI)

The recovery of alcohol and by-products from ethanol-water and methanol-water pulping liquors was studied. The recovery system proposed consists of three stages: black liquor flashing, lignin precipitation, and precipitation distillation of mother liquor. At the flash stage, 47 and 51% of the alcohol in the black liquor are recovered for ethanol and methanol processes, respectively. The lignin recovery yield at the precipitation stage is 67% for ethanol black liquor and 73% for methanol black liquor. The distillation of precipitation mother liquors enables recovery of 98% ethanol and 96% methanol from this stream as distillate, whereas the distillation residue contains significant amounts of sugars, furfural, and acetic acid that can be recovered. The study concludes with the overall mass balance for the recovery system proposed.

Botello, J.I.; Gilarranz, M.A.; Rodriguez, F.; Oliet, M. [Univ. Complutense de Madrid (Spain). Dept. de Ingenieria Quimica] [Univ. Complutense de Madrid (Spain). Dept. de Ingenieria Quimica

1999-09-01T23:59:59.000Z

59

What is spent nuclear fuel?  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

What is Spent Nuclear Fuel? Spent nuclear fuel (SNF) is irradiated fuel or targets containing uranium, plutonium, or thorium that is permanently withdrawn from a nuclear reactor or...

60

Physical properties of kraft black liquor. Final report. Phase I  

SciTech Connect (OSTI)

Methods were selected, equipment installed, and procedures developed for determining rheological properties; for determining thermal properties (stability, density, thermal expansion, and heat capacity); for purification and characterization of lignin (glass transition, stability, weight average molecular weight, and number average molecular weight); and for performing chemical analyses (negative inorganic ions, positive inorganic ions, acid organic salts, lignin, and total solids). A strategy for pulping to supply test liquors was developed, and a statistically designed pulping experiment was specified for a Southern softwood species. Arrangements were made for performing initial pulping work in an industrial pilot plant, and a preliminary set of pulping experiments were conducted. Liquors from the preliminary pulping experiments were used to test procedures and to determine reproducibility of the experiment. Literature was also surveyed and preliminary selection of designs for a pilot digester, and for equipment to determine surface tension were made.

Fricke, A.L.

1983-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Conceptual design of a black liquor gasification pilot plant  

SciTech Connect (OSTI)

In July 1985, Champion International completed a study of kraft black liquor gasification and use of the product gases in a combined cycle cogeneration system based on gas turbines. That study indicated that gasification had high potential as an alternative to recovery boiler technology and offered many advantages. This paper describes the design of the plant, the construction of the pilot plant, and finally presents data from operation of the plant.

Kelleher, E. G.

1987-08-01T23:59:59.000Z

62

Freeze crystallization technology for Kraft black liquor concentration. Third report  

SciTech Connect (OSTI)

About 25% of the purchased energy in the pulp and paper industry is used to concentrate black liquor. The technical feasibility of using freeze concentration to supplement evaporation has been successfully demonstrated, and results indicate that energy consumption can be reduced 45%. After compiling a considerable data base on the characteristics of black liquor at low temperature and after developing a computer program to aid analysis, the process chosen was vacuum freezing-vapor absorption (VFVA). A pilot plant was built and operated; however, due to problems with crystallization of the absorbent and contamination, it was found that maintaining the conditions necessary for a continuous process was not practical at the present state of development. Therefore, indirect freezing was used for all subsequent work. This required the design and fabrication of a simple shuttle crystallizer to replace scraped surface units conventionally used. CSI also developed an integrated ice separation column that combined crystal growth, a concentration gradient, and washing all in one unit. Finally, extensive heat transfer coefficient data were collected so that a preliminary design could be completed for a 350 TPD industrial freeze concentration unit. An economic analysis was calculated in order to compare using evaporation and freeze concentration to process the increased liquor flow from a pulp mill expansion. A 200,000 lb/hr freezing unit used to preconcentrate the mill's entire stream up to 18.7% solids would save $10 to $16 per ton of pulp.

Johnson, W.E.; Rhodes, C.R.

1985-04-01T23:59:59.000Z

63

A comprehensive program to develop correlations for physical properties of kraft black liquor. Final report  

SciTech Connect (OSTI)

A wide variety of experimental techniques have been used in this work, and many of these have been developed completely or improved significantly in the course of the research done during this program. Therefore, it is appropriate to describe these techniques in detail as a reference for future workers so that the techniques can be used in future work with little additional effort or so that the results reported from this program can be compared better with future results from other work. In many cases, the techniques described are for specific analytical instruments. It is recognized that these may be superseded by future developments and improvements in instrumentation if a complete description of techniques used successfully in the past on other instrumentation is available. The total pulping and liquor preparation research work performed included chip and white liquor preparation, digestion, pulp washing, liquor and wash recovery, liquor sampling, weak liquor concentration in two steps to about 45--50% solids with an intermediate soap skimming at about 140F and 27--30% solids, determination of pulp yield and Kappa number, determination of total liquor solids, and a check on the total material balance for pulping. All other research was performed either on a sample of the weak black liquor (the combined black liquor and washes from the digester) or on the skimmed liquor that had been concentrated.

Fricke, A.L.; Zaman, A.A.; Stoy, M.O.; Schmidl, G.W.; Dong, D.J.; Speck, B.

1998-04-01T23:59:59.000Z

64

Ultrafiltration of Kraft Black Liquor: Phase II, Final report  

SciTech Connect (OSTI)

The major justification for examining ultrafiltration was to lower the viscosity of the Kraft Black Liquor by recovering it as an ultrafiltration permeate from which the highest MW lignin had been removed. The liquor could then be concentrated to a higher percentage solids before firing into the recovery boiler. Consequent energy savings for the 1000 ton/day pulp mill would be 2.05 x 10 Btu/y for each percentage increase in TDS (total dissolved solids) to the recovery boiler. This Phase II report gives data on viscosity with percentage solids of KBL permeates. Another favorable effect of ultrafiltration on the permeate properties is disproportionate removal of multivalent ions including the major scaling ion CaS . If this high-viscosity high-Ca retentate could be treated to lower its viscosity and to release the Ca in a non-scaling form, this would enhance the possibility that ultrafiltration might be useful in a mill situation. Included in this report are data on the results of treating the retentate fraction. Other justifications for this program included further information in KBL properties: lignin MW in the KBL at high pH; elemental and sugar analyses; and differential properties of lignins in the retentate and the permeate fractions. A preliminary economic analysis of ultrafiltration is contained in this report. These analyses indicate that with flux rates now attainable, ultrafiltration would not be economically justified at this time if the only justification is to lower KBL viscosity. For certain situations where high Ca liquors present a scaling problem, especially in an evaporator-limited mill, the economics are more favorable. There are also unsolved problems relating to the use of the high viscosity retentate.

Hill, M.K.

1987-09-01T23:59:59.000Z

65

DEMONSTRATION OF BLACK LIQUOR GASIFICATION AT BIG ISLAND  

SciTech Connect (OSTI)

This Technical Progress Report provides an account of the status of the project for the demonstration of Black Liquor Gasification at Georgia-Pacific Corporation's Big Island, VA facility. The report also includes budget information and a milestone schedule. The project to be conducted by G-P is a comprehensive, complete commercial-scale demonstration that is divided into two phases. Phase I is the validation of the project scope and cost estimate. Phase II is project execution, data acquisition and reporting, and consists of procurement of major equipment, construction and start-up of the new system. Phase II also includes operation of the system for a period of time to demonstrate the safe operation and full integration of the energy and chemical recovery systems in a commercial environment. The objective of Phase I is to validate the process design and to engineer viable solutions to any technology gaps. This phase includes engineering and planning for the integration of the full-scale MTCI/StoneChem PulseEnhanced{trademark} black liquor steam-reformer chemical recovery system into G-P's operating pulp and paper mill at Big Island, Virginia. During this phase, the scope and cost estimate will be finalized to confirm the cost of the project and its integration into the existing system at the mill. The objective of Phase II of the project is the successful and safe completion of the engineering, construction and functional operation of the fully integrated full-scale steam reformer process system. This phase includes installation of all associated support systems and equipment required for the enhanced recovery of both energy and chemicals from all of the black liquor generated from the pulping process at the Big Island Mill. The objective also includes operation of the steam reformer system to demonstrate the ability of the system to operate reliably and achieve designed levels of energy and chemical recovery while maintaining environmental emissions at or below the limits set by the environmental permits.

Robert DeCarrera

2003-10-20T23:59:59.000Z

66

Ultrafiltration of Kraft Black Liquor. Final report, Phase I  

SciTech Connect (OSTI)

Kraft Black Liquor (KBL) is ultrafiltered to favorably affect the properties of the KBL permeate. The major property to be changed is viscosity. If the high molecular weight lignin is removed by ultrafiltration, the KBL permeate should show a significant drop in viscosity. An objective of the work reported was to examine how much KBL viscosity is lowered relative to membrane and membrane pore size used in the ultrafiltration. Another objective was an initial evaluation of ultrafiltration equipment and membranes. Operating characteristics were determined for selected equipment and membranes. Decreases in KBL permeate viscosity were indeed seen. (LEW)

Hill, M.K.

1985-10-01T23:59:59.000Z

67

Freeze crystallization technology for black liquor concentration. Second interim report  

SciTech Connect (OSTI)

The pulp and paper industry is one of the largest consumers of energy. Concentration of black liquor (the stream resulting from the chemical separation of wood fibers in the pulping operation) uses 25% of the purchased energy to produce pulp, an equivalent of 33 million barrels of oil in 1982. Here it is shown that freeze concentration, an emerging concentration technology, has the potential of reducing the energy consumption by at least 45%. This amounts to a cost savings of $5 to $15 per ton of pulp depending on the cost of energy, geographical location, and method of application.

Not Available

1983-07-01T23:59:59.000Z

68

Vapor pressure and boiling point elevation of slash pine black liquors: Predictive models with statistical approach  

SciTech Connect (OSTI)

Vapor-liquid equilibria and boiling point elevation of slash pine kraft black liquors over a wide range of solid concentrations (up to 85% solids) has been studied. The liquors are from a statistically designed pulping experiment for pulping slash pine in a pilot scale digester with four cooking variables of effective alkali, sulfidity, cooking time, and cooking temperature. It was found that boiling point elevation of black liquors is pressure dependent, and this dependency is more significant at higher solids concentrations. The boiling point elevation data at different solids contents (at a fixed pressure) were correlated to the dissolved solids (S/(1 {minus} S)) in black liquor. Due to the solubility limit of some of the salts in black liquor, a change in the slope of the boiling point elevation as a function of the dissolved solids was observed at a concentration of around 65% solids. An empirical method was developed to describe the boiling point elevation of each liquor as a function of pressure and solids mass fraction. The boiling point elevation of slash pine black liquors was correlated quantitatively to the pulping variables, using different statistical procedures. These predictive models can be applied to determine the boiling point rise (and boiling point) of slash pine black liquors at processing conditions from the knowledge of pulping variables. The results are presented, and their utility is discussed.

Zaman, A.A.; McNally, T.W.; Fricke, A.L. [Univ. of Florida, Gainesville, FL (United States)] [Univ. of Florida, Gainesville, FL (United States)

1998-01-01T23:59:59.000Z

69

Effect of sulfidity on the corrosivity of white, green, and black liquors  

SciTech Connect (OSTI)

Corrosion testing was performed in white, green, and black liquors from a kraft mill. The liquors were modified in composition to simulate conditions of high (40%) sulfidity and low (30%) sulfidity, and then heated in laboratory autoclaves to the temperatures of the respective tanks from which the samples were taken. Specimens of carbon and stainless steels were exposed under free corrosion potential conditions, and their corrosion rates determined from weight loss measurements. In white, green, 45% solids black, and flash tank liquors, active corrosion rates for the carbon steels were typically 20 to 75% higher in the higher sulfidity liquors. In 15% solids weak black liquor there was no appreciable difference in corrosion rates, with carbon steels remaining passive in both low and high sulfidity. In 26% solids intermediate black liquor there were large increases in the corrosion rates of carbon steel between low and high sulfidity liquors, resulting from a change from passive to active conditions. Stainless steels UNS S30403, S32304, and S31803 had very low corrosion rates in all the liquors tested, regardless of sulfidity.

Wensley, A.; Champagne, P.

1999-07-01T23:59:59.000Z

70

A comprehensive program to develop correlations for the physical properties of kraft black liquors. Interim report No.3  

SciTech Connect (OSTI)

The black liquor properties program has conducted a systematic collection data of properties, liquor composition, and lignin characteristics. Complete data, except for some density data, has been collected for Slash Pine black liquors made by experimental pulping at a total of 25 different pulping conditions that cover the entire range used for commercial pulping. In addition, complete data has been collected for some mill liquors and partial properties or composition data has been collected on Slash Pine black liquors made at 16 different pulping conditions and some mill liquors. Data reduction methods have been developed or extended for correlation of viscosity, heat capacity, heat of dilution, and density. Correlation of properties to pulping conditions and of composition to pulping conditions has begun. In most cases, data reduction methods have been developed that are fundamentally based and that have been shown to be generally applicable to all black liquors. While it has not proven to be possible to include research for comprehensive correlations for properties for liquors from other species, we have shown that the behavior of liquors made from other species is similar to that which has been explored extensively for Slash Pine liquors. This report reviews the methods used, describes examples of data reduction methods that have been developed, and presents some preliminary results for correlation of liquor composition and properties to pulping conditions for Slash Pine black liquors.

Fricke, A.L.; Dong, D.J.; Schmidl, G.W.; Stoy, M.A.; Zaman, A.A.

1993-09-01T23:59:59.000Z

71

Nuclear Spent Fuel Program Drivers  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

was created to plan and coordinate the management of Department of Energy-owned spent nuclear fuel. It was established as a result of a 1992 decision to stop spent nuclear fuel...

72

National Spent Nuclear Fuel Program  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

need to safely and efficiently manage all DOE-owned spent nuclear fuel and high level waste and prepare it for disposal. The National Spent Nuclear Fuel Program is addressing...

73

Scintillator spent fuel monitor  

SciTech Connect (OSTI)

A monitor for rapidly measuring the gross gamma-ray flux immediately above spent fuel assemblies in underwater storage racks has been developed. It consists of a plastic scintillator, photomultiplier, collimator, and a small battery-powered electronics package. The crosstalk from an isolated fuel assembly to an adjacent void is only about 2%. The mean difference between the measured gamma-ray flux and the flux estimated from the declared burnup and cooling time with a simple formula is 22%.

Moss, C.E.; Nixon, K.V.; Bernard, W.

1980-01-01T23:59:59.000Z

74

INVESTIGATION OF FUEL CHEMISTRY AND BED PERFORMANCE IN A FLUIDIZED BED BLACK LIQUOR STEAM REFORMER  

SciTech Connect (OSTI)

The University of Utah project ''Investigation of Fuel Chemistry and Bed Performance in a Fluidized Bed Black Liquor Steam Reformer'' (DOE award number DE-FC26-02NT41490) was developed in response to a solicitation for projects to provide technical support for black liquor and biomass gasification. The primary focus of the project is to provide support for a DOE-sponsored demonstration of MTCI's black liquor steam reforming technology at Georgia-Pacific's paper mill in Big Island, Virginia. A more overarching goal is to improve the understanding of phenomena that take place during low temperature black liquor gasification. This is achieved through five complementary technical tasks: (1) construction of a fluidized bed black liquor gasification test system, (2) investigation of bed performance, (3) evaluation of product gas quality, (4) black liquor conversion analysis and modeling and (5) computational modeling of the Big Island gasifier. Four experimental devices have been constructed under this project. The largest facility, which is the heart of the experimental effort, is a pressurized fluidized bed gasification test system. The system is designed to be able to reproduce conditions near the black liquor injectors in the Big Island steam reformer, so the behavior of black liquor pyrolysis and char gasification can be quantified in a representative environment. The gasification test system comprises five subsystems: steam generation and superheating, black liquor feed, fluidized bed reactor, afterburner for syngas combustion and a flue gas cooler/condenser. The three-story system is located at University of Utah's Industrial Combustion and Gasification Research Facility, and all resources there are available to support the research.

Kevin Whitty

2003-12-01T23:59:59.000Z

75

Investigation of Fuel Chemistry and Bed Performance in a Fluidized Bed Black Liquor Steam Reformer  

SciTech Connect (OSTI)

University of Utah's project entitled 'Investigation of Fuel Chemistry and Bed Performance in a Fluidized Bed Black Liquor Steam Reformer' (DOE Cooperative Agreement DE-FC26-02NT41490) was developed in response to a solicitation released by the U.S. Department of Energy in December 2001, requesting proposals for projects targeted towards black liquor/biomass gasification technology support research and development. Specifically, the solicitation was seeking projects that would provide technical support for Department of Energy supported black liquor and biomass gasification demonstration projects under development at the time.

Kevin Whitty

2007-06-30T23:59:59.000Z

76

Use of sulfide-containing liquors for removing mercury from flue gases  

DOE Patents [OSTI]

A method and apparatus for reducing and removing mercury in industrial gases, such as a flue gas, produced by the combustion of fossil fuels, such as coal, adds sulfide ions to the flue gas as it passes through a scrubber. Ideally, the source of these sulfide ions may include at least one of: sulfidic waste water, kraft caustic liquor, kraft carbonate liquor, potassium sulfide, sodium sulfide, and thioacetamide. The sulfide ion source is introduced into the scrubbing liquor as an aqueous sulfide species. The scrubber may be either a wet or dry scrubber for flue gas desulfurization systems.

Nolan, Paul S. (North Canton, OH); Downs, William (Alliance, OH); Bailey, Ralph T. (Uniontown, OH); Vecci, Stanley J. (Alliance, OH)

2003-01-01T23:59:59.000Z

77

Method for improving separation of carbohydrates from wood pulping and wood or biomass hydrolysis liquors  

DOE Patents [OSTI]

A method for separating carbohydrates from pulping liquors includes the steps of providing a wood pulping or wood or biomass hydrolysis pulping liquor having lignin therein, and mixing the liquor with an acid or a gas which forms an acid upon contact with water to initiate precipitation of carbohydrate to begin formation of a precipitate. During precipitation, at least one long chain carboxylated carbohydrate and at least one cationic polymer, such as a polyamine or polyimine are added, wherein the precipitate aggregates into larger precipitate structures. Carbohydrate gel precipitates are then selectively removed from the larger precipitate structures. The method process yields both a carbohydrate precipitate and a high purity lignin.

Griffith, William Louis; Compere, Alicia Lucille; Leitten Jr., Carl Frederick

2010-04-20T23:59:59.000Z

78

Low temperature pyrolysis of black liquor and polymerization of products in alkali aqueous medium  

SciTech Connect (OSTI)

Atmospheric pressure pyrolysis for the production of liquids and gases from black liquor and its calcium salts and acidic precipitate have been carried out in a little stainless steel tube. Yields, sum of liquid and gas products, from black liquor and its calcium salts and acidic precipitate were 44.7%, 52.0% and 59.1% of dry basis respectively. The precipitates obtained from black liquor by acidifying with hydrochloric acid and passing carbon dioxide have been polymerized in aqueous acetone containing formaldehyde and ammonia, and converted a polymeric resin.

Demirbas, A. (Dept. of Chemical Education, Karadeniz Teknik Univ., Trabzon (TR)); Ucan, H. (Dept. of Chemistry, Selcuk Univ., Konya (TR))

1991-01-01T23:59:59.000Z

79

Energy considerations for steam plasma gasification of black liquor and chemical recovery  

SciTech Connect (OSTI)

This paper investigates the energy economics of using a hybrid steam plasma process to gasify black liquor. In the pulp and paper industry, gasification is gaining credibility as an incremental method to supplement the standard Kraft process, which bums the black liquor in large furnaces to recover energy and inorganic chemicals (sodium and sulfur) that are recycled back into the wood pulping process. This paper shows that despite the energy intensive nature of steam plasma processing, several fortuitous conditions arise that make it a viable technology for the gasification of black liquor.

Grandy, J.D.; Kong, P.C.

1995-10-01T23:59:59.000Z

80

Energy considerations for steam plasma gasification of black liquor and chemical recovery  

SciTech Connect (OSTI)

This paper investigates the energy economics of using a hybrid steam plasma process to gasify black liquor. In the pulp and paper industry, gasification is gaining credibility as an incremental method to supplement the standard Kraft process, which burns the black liquor in large furnaces to recover energy and inorganic chemicals (sodium and sulfur) that are recycled back into the wood pulping process. This paper shows that despite the energy intensive nature of steam plasma processing, several fortuitous conditions arise that make it a viable technology for the gasification of black liquor.

Grandy, J.D.; Kong, P.C. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

1995-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Biomass gasification project gets funding to solve black liquor safety and landfill problems  

SciTech Connect (OSTI)

This paper reports on biomass gasifications. The main by-product in pulp making is black liquor from virgin fiber; the main by-product in paper recycling is fiber residue. Although the black liquor is recycled for chemical and energy recovery, safety problems plague the boilers currently used to do this. The fiber residue is usually transported to a landfill. The system being developed by MTCI will convert black liquor and fiber residue into a combustible gas, which can then be used for a wide variety of thermal or power generation applications.

Black, N.P.

1991-02-01T23:59:59.000Z

82

Use of sulfide-containing liquors for removing mercury from flue gases  

DOE Patents [OSTI]

A method and apparatus for reducing and removing mercury in industrial gases, such as a flue gas, produced by the combustion of fossil fuels, such as coal, adds sulfide ions to the flue gas as it passes through a scrubber. Ideally, the source of these sulfide ions may include at least one of: sulfidic waste water, kraft caustic liquor, kraft carbonate liquor, potassium sulfide, sodium sulfide, and thioacetamide. The sulfide ion source is introduced into the scrubbing liquor as an aqueous sulfide species. The scrubber may be either a wet or dry scrubber for flue gas desulfurization systems.

Nolan, Paul S.; Downs, William; Bailey, Ralph T.; Vecci, Stanley J.

2006-05-02T23:59:59.000Z

83

Kinetics of gasification of black liquor char by steam  

SciTech Connect (OSTI)

This paper reports on the steam gasification kinetics of kraft black liquor char that were studied in a thermogravimetric analysis reactor. The effect of steam and hydrogen concentration on gasification rate can be described by Langmuir-Hinshelwood type kinetics. An activation energy of 210 kJ/mol was obtained. Methane formation was negligible, and H{sub 2}S was the major gaseous sulfur-containing product obtained over the temperature range studied, 873-973 K. The CO{sub 2} concentration was higher than calculated for the water-shift reaction at equilibrium. A gasification mechanism is proposed whereby CO{sub 2} is one of the primary gasification products.

Li, J.; van Heiningen, A.R.P. (Dept. of Chemical Engineering, McGill Univ., Pulp and Paper Research Inst. of Canada, Montreal, Quebec (CA))

1991-07-01T23:59:59.000Z

84

Simultaneous and rapid determination of multiple component concentrations in a Kraft liquor process stream  

DOE Patents [OSTI]

The present invention is a rapid method of determining the concentration of the major components in a chemical stream. The present invention is also a simple, low cost, device of determining the in-situ concentration of the major components in a chemical stream. In particular, the present invention provides a useful method for simultaneously determining the concentrations of sodium hydroxide, sodium sulfide and sodium carbonate in aqueous kraft pulping liquors through use of an attenuated total reflectance (ATR) tunnel flow cell or optical probe capable of producing a ultraviolet absorbency spectrum over a wavelength of 190 to 300 nm. In addition, the present invention eliminates the need for manual sampling and dilution previously required to generate analyzable samples. The inventive method can be used in Kraft pulping operations to control white liquor causticizing efficiency, sulfate reduction efficiency in green liquor, oxidation efficiency for oxidized white liquor and the active and effective alkali charge to kraft pulping operations.

Li, Jian (Marietta, GA); Chai, Xin Sheng (Atlanta, GA); Zhu, Junyoung (Marietta, GA)

2008-06-24T23:59:59.000Z

85

E-Print Network 3.0 - alkaline black liquor Sample Search Results  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

by Explorit Topic List Advanced Search Sample search results for: alkaline black liquor Page: << < 1 2 3 4 5 > >> 1 Journal of Membrane Science, 33 (1987) 83-95 Elsevier Science...

86

A comprehensive program to develop correlations for the physical properties of Kraft black liquor. Interim report No. 3  

SciTech Connect (OSTI)

The black liquor properties program has been conducted over this last period so as to systematically collect data on properties, liquor composition, and lignin characteristics very carefully by methods that have developed during this program. Complete data has been collected for Slash Pine black liquors made by experimental pulping at different pulping conditions. In addition, data has been collected for mill liquors and partial properties or composition data has been collected on Slash Pine black liquors. Data reduction methods have been developed or extended for correlation of viscosity, heat capacity, heat of dilution, and density. Correlation of properties to pulping conditions and of composition to. pulping conditions has begun. In most cases, data reduction methods have been developed that are fundamentally based and that have been shown to be generally applicable to all black liquors. In the near future, we fully expect to accomplish our goal of developing generalized correlations relating physical properties of Slash Pine kraft black liquors to liquor composition. This interim report reviews the methods used, describes examples of data reduction methods that have been developed, and presents some preliminary results for correlation of liquor composition and properties to pulping conditions for Slash Pine black liquors.

Fricke, A.L.; Dong, D.J.; Schmidl, G.W.; Stoy, M.A.; Zaman, A.A.

1993-09-01T23:59:59.000Z

87

Swelling of kraft black liquor: an understanding of the associated phenomena during pyrolysis  

SciTech Connect (OSTI)

The objectives of this thesis were to quantify the swelling of black liquor during pyrolysis in a nitrogen atmosphere and to determine what factors were responsible for swelling. The first part of the investigation studied the process variables: pyrolysis temperature, solid content, heating rate and particle size. A temperature of 500/sup 0/C resulted in maximum swelling for the investigated temperature range of 300-900/sup 0/C. The swelling of black liquor occurred during the evolution of pyrolysis gases; however, there was no correlation found between the amount of pyrolysis gases evolved and the change in char volume. The initial solid content of black liquor had a small influence on the swelling of black liquor. The heating rate was found to effect the rate of swelling but not the final volume. Particle size had no effect on the swollen volume per unit particle weight. The effect of black liquor composition was studied. An interaction between sugar acids and kraft lignin was responsible for swelling. The extractives interfered with the swelling mechanism of black liquor, while inorganic salts acted as a diluent. The swelling behavior of black liquor appeared to be dictated by the surface active and viscous forces present in black liquor during pyrolysis. Surface active forces were evidenced by the formation of small bubbles (50-150 microns in diameter) which appeared necessary for highly swollen chars. Low swelling chars did not exhibit this phenomenon. Bubble formation began at 250/sup 0/C, which closely corresponded to the thermal decomposition temperature of sugar acids. The sugar acids formed bubbles when pyrolyzed but did not swell significantly during pyrolysis. Kraft lignin appeared to enhance the swelling of the sugar acids by increasing the viscosity and stabilizing the bubbles during pyrolysis.

Miller, P.T.

1986-01-01T23:59:59.000Z

88

Spent Nuclear Fuel Fact Sheets  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

management needs. By coordinating common needs for research, technology development, and testing programs, the National Spent Nuclear Fuel Program is achieving cost efficiencies...

89

Fuel nitrogen release during black liquor pyrolysis; Part 1: Laboratory measurements at different conditions  

SciTech Connect (OSTI)

Fuel nitrogen release during black liquor pyrolysis is high. There is only minor release during the drying stage. Ammonia is the main fixed nitrogen species formed. The rate of fixed nitrogen release increases with increasing temperature. The level of fixed nitrogen released by birch liquor is almost twice the level for pine liquor. Assuming complete conversion to NO, fixed nitrogen yields gave NO concentrations near typically measured values for flue gases in full scale recovery boilers. The purpose of this work was to gain more detailed information about the behavior of the fuel nitrogen in black liquor combustion. The work focused on the pyrolysis or devolatilization of the combustion process. Devolatilization is the stage at which the majority (typically 50--80%) of the liquor organics release from a fuel particle or droplet as gaseous species due to the rapid destruction of the organic macromolecules in the liquor. In this paper, the authors use the terms devolatilization and pyrolysis interchangeably with no difference in their meaning.

Aho, K.; Vakkilainen, E. (A. Ahistrom Corp., Varkaus (Finland)); Hupa, M. (Abo Akademi Univ., Turku (Finland). Chemical Engineering Dept.)

1994-05-01T23:59:59.000Z

90

Effect of pulsation on black liquor gasification. Final report  

SciTech Connect (OSTI)

Pyrolysis is an endothermic process. The heat of reaction is provided either by partial combustion of the waste or by heat transfer from an external combustion process. In one proposed system black liquor is pyrolized in a fluidized bed to which heat is added through a series of pulse combustor tail pipes submerged in the bed material. This system appears promising because of the relatively high heat transfer in pulse combustors and in fluidized beds. Other advantages of pulse combustors are discussed elsewhere. The process is, however, only economically viable if a part of the pyrolysis products can be used to fire the pulse combustors. The overall goals of this study were to determine: (1) which is the limiting heat transfer rate in the process of transferring heat from the hot combustion products to the pipe, through the pipe, from the tail pipe to the bed and through the bed; i.e., whether increased heat transfer within the pulse combustor will significantly increase the overall heat transfer rate; (2) whether the heat transfer benefits of the pulse combustor can be utilized while maintaining the temperature in the bed within the narrow temperature range required by the process without generating hot spots in the bed; and (3) whether the fuel gas produced during the gasification process can be used to efficiently fire the pulse combustor.

Zinn, B.T.; Jagoda, J.; Jeong, H.; Kushari, A.; Rosen, L.J.

1998-12-01T23:59:59.000Z

91

Research on droplet formation for application to kraft black liquors: Final report: Tasks I and III, report No. 4  

SciTech Connect (OSTI)

The overall objective of this project is to generate technical data with which to design nozzles for kraft black liquor recovery boilers which can reduce under and over size droplets and adjust for changing black liquor properties and production requirements. The research is organized into five tasks: Droplet formation from a single jet, theoretical and experimental--ambient gas medium; Surface tensions of black liquor; Aerodynamic/hydrodynamic stability/instability of droplets once formed; Black liquor droplet formation from a single jet--furnace gas medium; Prototype of a new nozzle design. 88 figs.

Stockel, I.H.

1988-10-01T23:59:59.000Z

92

Physical properties of kraft black liquor: Summary report, Phases 1 and 2  

SciTech Connect (OSTI)

Since 1981, a research program has been in progress to determine the physical properties of kraft black liquors and to develop methods for reduction of data and correlation of properties with pumping conditions. The basic premise that has been used to direct the research program is that kraft black liquor behaves as a polymer solution, particularly at high solids, and that the behavior is dominated by the characteristics of the lignin present. This premise is proving to be correct, and the principles that follow from this premise are proving to be successful for data reduction and correlation. The research has been a complex program involving experimental pulping, chemical analysis, lignin separation and characterization, thermal analysis, rheological measurements, and considerable equipment and methods development. Due to the complexity of the program, the unforeseen need to expend a great deal of effort in development of experimental techniques for analysis, and the fact that our liquors proved to be unstable at high temperatures and solids, all of the original objectives could not be accomplished. However, our program has added substantially to the body of knowledge of physical properties of black liquor. Our results indicate that the goal of developing correlations for physical properties of kraft black liquor is practical and can be realized through extension of the present work.

Fricke, A.L.

1987-09-01T23:59:59.000Z

93

Improved Materials for High-Temperature Black Liquor Gasification  

SciTech Connect (OSTI)

The laboratory immersion test system built and operated at ORNL was found to successfully screen samples from numerous refractory suppliers, including both commercially available and experimental materials. This system was found to provide an accurate prediction of how these materials would perform in the actual gasifier environment. Test materials included mullites, alumino-silicate bricks, fusion-cast aluminas, alumina-based and chrome-containing mortars, phosphate-bonded mortars, coated samples provided under an MPLUS-funded project, bonded spinels, different fusion-cast magnesia-alumina spinels with magnesia content ranging from 2.5% to about 60%, high-MgO castable and brick materials, spinel castables, and alkali-aluminate materials. This testing identified several candidate material systems that perform well in the New Bern gasifier. Fusion-cast aluminas were found to survive for nearly one year, and magnesia-alumina spinels have operated successfully for 18 months and are expected to survive for two years. Alkali-aluminates and high-MgO-content materials have also been identified for backup lining applications. No other material with a similar structure and chemical composition to that of the fusion-cast magnesium-aluminum spinel brick currently being used for the hot-face lining is commercially available. Other materials used for this application have been found to have inferior service lives, as previously discussed. Further, over 100 laboratory immersion tests have been performed on other materials (both commercial and experimental), but none to date has performed as well as the material currently being used for the hot-face lining. Operating experience accumulated with the high-temperature gasifier at New Bern, North Carolina, has confirmed that the molten alkali salts degrade many types of refractories. Fusion-cast alumina materials were shown to provide a great improvement in lifetime over materials used previously. Further improvement was realized with fusion-cast magnesia-alumina spinel refractory, which appears to be the most resistant to degradation found to date, exhibiting over a year of service life and expected to be capable of over two years of service life. Regarding the use of refractory mortar, it was found that expansion of the current chrome-alumina mortar when subjected to black liquor smelt is likely contributing to the strains seen on the vessel shell. Additionally, the candidate high-alumina mortar that was originally proposed as a replacement for the current chrome-alumina mortar also showed a large amount of expansion when subjected to molten smelt. A UMR experimental mortar, composed of a phosphate bonded system specifically designed for use with fusion-cast magnesium-aluminum spinel, was found to perform well in the molten smelt environment. Strain gauges installed on the gasifier vessel shell provided valuable information about the expansion of the refractory, and a new set of strain gauges and thermocouples has been installed in order to monitor the loading caused by the currently installed spinel refractory. These results provide information for a direct comparison of the expansion of the two refractories. Measurements to date suggest that the fusion-cast magnesia-alumina spinel is expanding less than the fusion-cast {alpha}/{beta}-alumina used previously. A modified liquor nozzle was designed and constructed to test a number of materials that should be more resistant to erosion and corrosion than the material currently used. Inserts made of three erosion-resistant metallic materials were fabricated, along with inserts made of three ceramic materials. The assembled system was sent to the New Bern mill for installation in the gasifer in 2005. Following operation of the gasifier using the modified nozzle, inserts should be removed and analyzed for wear by erosion/corrosion. Although no materials have been directly identified for sensor/thermocouple protection tubes, several of the refractory material systems identified for lining material applications may be applicable for use in this

Keiser, J.R.; Hemrick, J.G.; Gorog, J.P.; Leary, R.

2006-06-29T23:59:59.000Z

94

Red Sky with Red Mesa  

ScienceCinema (OSTI)

The Red Sky/Red Mesa supercomputing platform dramatically reduces the time required to simulate complex fuel models, from 4-6 months to just 4 weeks, allowing researchers to accelerate the pace at which they can address these complex problems. Its speed also reduces the need for laboratory and field testing, allowing for energy reduction far beyond data center walls.

None

2014-06-23T23:59:59.000Z

95

Intermodal transportation of spent fuel  

SciTech Connect (OSTI)

Concepts for transportation of spent fuel in rail casks from nuclear power plant sites with no rail service are under consideration by the US Department of Energy in the Commercial Spent Fuel Management program at the Pacific Northwest Laboratory. This report identifies and evaluates three alternative systems for intermodal transfer of spent fuel: heavy-haul truck to rail, barge to rail, and barge to heavy-haul truck. This report concludes that, with some modifications and provisions for new equipment, existing rail and marine systems can provide a transportation base for the intermodal transfer of spent fuel to federal interim storage facilities. Some needed land transportation support and loading and unloading equipment does not currently exist. There are insufficient shipping casks available at this time, but the industrial capability to meet projected needs appears adequate.

Elder, H.K.

1983-09-01T23:59:59.000Z

96

Investigation of Pressurized Entrained-Flow Kraft Black Liquor Gasification in an Industrially Relevant Environment  

SciTech Connect (OSTI)

The University of Utah's project 'Investigation of Pressurized Entrained-Flow Kraft Black Liquor Gasification in an Industrially Relevant Environment' (U.S. DOE Cooperative Agreement DE-FC26-04NT42261) was a response to U.S. DOE/NETL solicitation DE-PS36-04GO94002, 'Biomass Research and Development Initiative' Topical Area 4-Kraft Black Liquor Gasification. The project began September 30, 2004. The objective of the project was to improve the understanding of black liquor conversion in high pressure, high temperature reactors that gasify liquor through partial oxidation with either air or oxygen. The physical and chemical characteristics of both the gas and condensed phase were to be studied over the entire range of liquor conversion, and the rates and mechanisms of processes responsible for converting the liquor to its final smelt and syngas products were to be investigated. This would be accomplished by combining fundamental, lab-scale experiments with measurements taken using a new semi-pilot scale pressurized entrained-flow gasifier. As a result of insufficient availability of funds and changes in priority within the Office of Biomass Programs of the U.S. Department of Energy, the research program was terminated in its second year. In total, only half of the budgeted funding was made available for the program, and most of this was used during the first year for construction of the experimental systems to be used in the program. This had a severe impact on the program. As a consequence, most of the planned research was unable to be performed. Only studies that relied on computational modeling or existing experimental facilities started early enough to deliver useful results by the time to program was terminated Over the course of the program, small scale (approx. 1 ton/day) entrained-flow gasifier was designed and installed at the University of Utah's off-campus Industrial Combustion and Gasification Research Facility. The system is designed to operate at pressures as high as 32 atmospheres, and at temperatures as high as 1500 C (2730 F). Total black liquor processing capacity under pressurized, oxygen-blown conditions should be in excess of 1 ton black liquor solids per day. Many sampling ports along the conversion section of the system will allow detailed analysis of the environment in the gasifier under industrially representative conditions. Construction was mostly completed before the program was terminated, but resources were insufficient to operate the system. A system for characterizing black liquor sprays in hot environments was designed and constructed. Silhouettes of black liquor sprays formed by injection of black liquor through a twin fluid (liquor and atomizing air) nozzle were videoed with a high-speed camera, and the resulting images were analyzed to identify overall characteristics of the spray and droplet formation mechanisms. The efficiency of liquor atomization was better when the liquor was injected through the center channel of the nozzle, with atomizing air being introduced in the annulus around the center channel, than when the liquor and air feed channels were reversed. Atomizing efficiency and spray angle increased with atomizing air pressure up to a point, beyond which additional atomizing air pressure had little effect. Analysis of the spray patterns indicates that two classifications of droplets are present, a finely dispersed 'mist' of very small droplets and much larger ligaments of liquor that form at the injector tip and form one or more relatively large droplets. This ligament and subsequent large droplet formation suggests that it will be challenging to obtain a narrow distribution of droplet sizes when using an injector of this design. A model for simulating liquor spray and droplet formation was developed by Simulent, Inc. of Toronto. The model was able to predict performance when spraying water that closely matched the vendor specifications. Simulation of liquor spray indicates that droplets on the order 200-300 microns can be expected, and that higher liquor flow will result in be

Kevin Whitty

2008-06-30T23:59:59.000Z

97

Formation of fuel NO[sub x] during black-liquor combustion  

SciTech Connect (OSTI)

Fuel NOx and thermal NOx were measured in combustion gases from black liquors in two laboratory furnaces. Combustion at 950 C in air (8% O[sub 2]) produced NOx concentrations of 40-80ppm. Combustion at 950 C in synthetic air containing no nitrogen (21% 0[sub 2] in Ar) produced the same result, demonstrating that all of the NOx produced during combustion at 950 C was fuel NOx. Formation of fuel NOx increased moderately with increasing temperature in the range of 800-1,000 C, but temperature sensitivity of fuel NOx was much less than that of thermal NOx. The results imply that the major source of NOx in recovery furnace emissions is the fuel NOx in recovery furnace formed by conversion of liquor-bound nitrogen during combustion. This is consistent with thermal NOx theory, which postulates that black-liquor combustion temperatures are too low to generate significant amounts of thermal NOx.

Nichols, K.M. (Weyerhaeuser Paper Co., Tacoma, WA (United States)); Lien, S.J. (Inst. of Paper Science and Technology, Atlanta, GA (United States))

1993-03-01T23:59:59.000Z

98

Research on droplet formation for application to kraft black liquors---Final project report  

SciTech Connect (OSTI)

The objective of this project was to generate technical data to guide the design of new nozzles for kraft black liquor recovery boilers. The goal of new nozzle designs would be to narrow the droplet size distribution compared to current nozzles and to adjust for changing black liquor properties and production requirements. Uniform droplets in a recovery boiler should reduce fouling of superheater tubes and caused a more efficient burning of the black liquor, both of which result in improved energy efficiency. The research was organized into five tasks which are described in the next chapter. This fifth and final project report contains the details of Task 4 and 5 and further analysis of Task 1 results. The details of the other tasks are reported in previous technical reports. The major results from the entire project are highlighted in this section in order of significance.

Bousfield, D.W.

1990-01-01T23:59:59.000Z

99

Red Giant Red Giant White Giant  

E-Print Network [OSTI]

Red Giant Red Giant White Giant Red Giant White Giant White Giant Blue Giant Blue Giant Blue Giant. Proxima Centauri, the closest star to the Sun, is a red giant. Mass: 1- 4 Solar Mass StarPower Points: 7

Bechtold, Jill

100

HFIR spent fuel management alternatives  

SciTech Connect (OSTI)

The High Flux Isotope Reactor (HFIR) at Martin Marietta Energy Systems' Oak Ridge National Laboratory (ORNL) has been unable to ship its spent fuel to Savannah River Site (SRS) for reprocessing since 1985. The HFIR storage pools are expected to fill up in the February 1994 to February 1995 time frame. If a management altemative to existing HFIR pool storage is not identified and implemented before the HFIR pools are full, the HFIR will be forced to shut down. This study investigated several alternatives for managing the HFIR spent fuel, attempting to identify options that could be implemented before the HFIR pools are full. The options investigated were: installing a dedicated dry cask storage facility at ORNL, increasing HFIR pool storage capacity by clearing the HFIR pools of debris and either close-packing or stacking the spent fuel elements, storing the spent fuel at another ORNL pool, storing the spent fuel in one or more hot cells at ORNL, and shipping the spent fuel offsite for reprocessing or storage elsewhere.

Begovich, J.M.; Green, V.M.; Shappert, L.B.; Lotts, A.L.

1992-10-15T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

HFIR spent fuel management alternatives  

SciTech Connect (OSTI)

The High Flux Isotope Reactor (HFIR) at Martin Marietta Energy Systems` Oak Ridge National Laboratory (ORNL) has been unable to ship its spent fuel to Savannah River Site (SRS) for reprocessing since 1985. The HFIR storage pools are expected to fill up in the February 1994 to February 1995 time frame. If a management altemative to existing HFIR pool storage is not identified and implemented before the HFIR pools are full, the HFIR will be forced to shut down. This study investigated several alternatives for managing the HFIR spent fuel, attempting to identify options that could be implemented before the HFIR pools are full. The options investigated were: installing a dedicated dry cask storage facility at ORNL, increasing HFIR pool storage capacity by clearing the HFIR pools of debris and either close-packing or stacking the spent fuel elements, storing the spent fuel at another ORNL pool, storing the spent fuel in one or more hot cells at ORNL, and shipping the spent fuel offsite for reprocessing or storage elsewhere.

Begovich, J.M.; Green, V.M.; Shappert, L.B.; Lotts, A.L.

1992-10-15T23:59:59.000Z

102

A comprehensive program to develop correlations for the physical properties of Kraft black liquor. Interim report No. 2  

SciTech Connect (OSTI)

Experimental effort for the program to evaluate physical properties of kraft black liquors is now proceeding well. Experimental work includes pulping, liquor analysis, lignin purification and characterization, vapor-liquid equilibria, heat capacity, heats of solution and combustion, and viscosity measurements. Measurement of thermal conductivity has not yet begun. Collection of the data necessary for development of generalized correlations is proceeding, but will require about two more years. The digester is operating very well. It is now possible to operate the digester as a closed, rotating reactor or as a batch reactor with liquor circulation. When operated with liquor circulation, temperatures within the chip bed can be monitored during cooking. Cooking is reproducible, and cooks are being performed to produce liquors for experimental studies. The digester could be further modified to permit us to conduct rapid exchange batch pulping or to permit us to simulate continuous pulping. Liquors to be used in experimental studies are concentrated in our large scale evaporator or in our small scale evaporator. The large scale evaporator is used to concentrate liquors to about 50% solids for storage and for use in studies requiring high solids liquors. The small scale evaporator is used for preparing final samples to as high as 85% solids and for measuring vapor-liquid equilibria. Liquors are now routinely analyzed to determine all components, except higher molecular weight organic acids and extractives. Lignin determination by uv-visible means has been improved. Lignin purification from black liquor has been improved and lignin molecular weights are determined routinely. Work on lignin molecular weight distribution is still not satisfactory, but recent developments holds promise.

Fricke, A.L.

1990-12-01T23:59:59.000Z

103

High-solids black liquor firing in pulp and paper industry kraft recovery boilers. Quarterly report, Phase 1a: Black liquor gasifier evaluation  

SciTech Connect (OSTI)

This project phase addresses the following workscope: Conduct bench-scale tests of a low temperature, partial combustion gasifier; Prepare a gasifier pilot-plant preliminary design and cost estimate and prepare a budgetary cost estimate of the balance of the program; Outline a test program to evaluate gasification; Prepare an economic/market analysis of gasification and solicit pulp and paper industry support for subsequent phases; and Prepare a final report and conduct a project review prior to commencement of work leading to construction of any pilot scale components or facilities. The primary accomplishments included completion of installation of the bench-scale black liquor gasifier and supporting systems, preparing test plans and related safety procedures and detailed operating procedures, defining the functional design requirements and outlining the test plans for the pilot-scale gasifier, and preparing a preliminary economic assessment of the black liquor gasifier. This work accomplished under Phase 1a during this period is further described by task.

NONE

1996-07-01T23:59:59.000Z

104

Energy conservation in black-liquor evaporator of pulp and paper industry  

SciTech Connect (OSTI)

This paper is an attempt on energy conservation in a quintuple effect evaporator used to concentrate dilute black liquor solution by raising their steam economy through the changes in the operating variables. It also describes the steam economy of the evaporator for the various feed arrangements so as to determine the ranges of the variables for which evaporation occurs profitable.

Agarwal, V.K.; Gupta, S.C. [Univ. of Roorkee (India). Dept. of Chemical Engineering

1995-12-31T23:59:59.000Z

105

Assessment of the release of atomic Na from a burning black liquor droplet using quantitative PLIF  

SciTech Connect (OSTI)

The quantitative measurement of atomic sodium (Na) release, at high concentration, from a burning black liquor droplet has been demonstrated using a planar laser-induced fluorescence (PLIF) technique, corrected for fluorescence trapping. The local temperature of the particle was measured to be approximately 1700 C, at a height of 10 mm above a flat flame burner. The PLIF technique was used to assess the temporal release of atomic Na from the combustion of black liquor and compare it with the Na concentration in the remaining smelt. A first-order model was made to provide insight using a simple Plug Flow Reactor model based on the independently measured concentration of residual Na in the smelt as a function of time. This model also required the dilution ratio of the combustion products in the flat flame entrained into the plume gas from the black liquor particle to be estimated. The key findings of these studies are: (i) the peak concentration of atomic Na from the combustion of the black liquor droplets is around 1.4 ppm; (ii) very little atomic Na is present during the drying, devolatilisation or char combustion stages; and (iii) the presence of atomic Na during smelt phase dominates over that from the other combustion stages. (author)

Saw, Woei L.; Nathan, Graham J. [Centre for Energy Technology, The Environment Institute, School of Mechanical Engineering, The University of Adelaide, SA 5005 (Australia); Ashman, Peter J.; Alwahabi, Zeyad T. [Centre for Energy Technology, The Environment Institute, School of Chemical Engineering, The University of Adelaide, SA 5005 (Australia)

2009-07-15T23:59:59.000Z

106

Final technical report. In-situ FT-IR monitoring of a black liquor recovery boiler  

SciTech Connect (OSTI)

This project developed and tested advanced Fourier transform infrared (FT-IR) instruments for process monitoring of black liquor recovery boilers. The state-of-the-art FT-IR instruments successfully operated in the harsh environment of a black liquor recovery boiler and provided a wealth of real-time process information. Concentrations of multiple gas species were simultaneously monitored in-situ across the combustion flow of the boiler and extractively at the stack. Sensitivity to changes of particulate fume and carryover levels in the process flow were also demonstrated. Boiler set-up and operation is a complex balance of conditions that influence the chemical and physical processes in the combustion flow. Operating parameters include black liquor flow rate, liquor temperature, nozzle pressure, primary air, secondary air, tertiary air, boiler excess oxygen and others. The in-process information provided by the FT-IR monitors can be used as a boiler control tool since species indicative of combustion efficiency (carbon monoxide, methane) and pollutant emissions (sulfur dioxide, hydrochloric acid and fume) were monitored in real-time and observed to fluctuate as operating conditions were varied. A high priority need of the U.S. industrial boiler market is improved measurement and control technology. The sensor technology demonstrated in this project is applicable to the need of industry.

James Markham; Joseph Cosgrove; David Marran; Jorge Neira; Chad Nelson; Peter Solomon

1999-05-31T23:59:59.000Z

107

Black liquor viscosity reduction through salt additives: A novel environmentally benign processing alternative  

SciTech Connect (OSTI)

Processing black liquor at high solids would reduce SO{sub x} emissions, facilitate the use of non-chlorine bleaching techniques and enhance the energy efficiency of the pulping process. However, black liquor exhibits and exponential increase in viscosity as its solids content rises, thus hindering its processability in the composition range of interest (>70% solids). In this study, we present a new approach for controlling viscosity at high solids content by {open_quotes}salting in{close_quotes} black liquor through addition of thiocyanate salts. These salts increases the solubility of the polymer constituents in black liquor leading to a decrease in its viscosity. Several salts capable of viscosity reduction by as much as two orders of magnitude have been identified. The effects of cation size, solution pH and temperature on viscosity reduction is presented and interpreted in terms of the underlying principles of {open_quotes}salting in{close_quotes} and how it affects aqueous solution structure.

Roberts, J.E.; Khan, S.A.; Spontak, R.J. [North Carolina State Univ., Raleigh, NC (United States)

1996-10-01T23:59:59.000Z

108

Generator-Absorber heat exchange transfer apparatus and method using an intermediate liquor  

DOE Patents [OSTI]

Numerous embodiments and related methods for generator-absorber heat exchange (GAX) are disclosed, particularly for absorption heat pump systems. Such embodiments and related methods use the working solution of the absorption system for the heat transfer medium where the working solution has an intermediate liquor concentration.

Phillips, Benjamin A. (Benton Harbor, MI); Zawacki, Thomas S. (St. Joseph, MI)

1996-11-05T23:59:59.000Z

109

Separation of kraft lignin from kraft black liquor: Final report, July 1984-April 1987  

SciTech Connect (OSTI)

All the objectives were accomplished: a high-quality kraft lignin containing less than 50 ppM sodium was separated into a solvent phase (freon) from as much as 1000 lb kraft black liquor. Supporting data (infrared spectra, chemical analyses, etc.) are included. (DLC)

Kurple, K.R.

1988-04-15T23:59:59.000Z

110

Coliquefaction of coal and black liquor to environmentally acceptable liquid fuels  

SciTech Connect (OSTI)

Previous work in the laboratories has demonstrated that addition to lignin to coal during liquefaction significantly increases the depolymerization of coal and enhances the quality of the liquid products. It is believed that thermolysis of the lignin results in the formation of phenoxyl and other reactive radicals at temperatures too low for significant thermolysis of the coal matrix; such radicals are effective and active intermediates that depolymerize coal by cleaving methylene bridges. It has been reported that alkali is also effective for extraction of liquids from coal. The work presented here combines these two reactive agents by utilizing the black liquor waste stream from the Kraft pulping process for coal depolymerization. That waste stream contains large amounts of lignin and sodium hydroxide, as well as other components. To permit comparative evaluations of the extent of coal depolymerization by coprocessing coal and black liquor, reference runs were performed with tetralin alone, sodium hydroxide in tetralin, and lignin in tetralin. Results indicated that the sodium hydroxide-tetralin system resulted in almost 67% conversion at 375 C, 1 hour. The black liquor system exhibited a lower conversion of 60%, indicating some inhibition of the depolymerization reactions by components in the black liquor.

Kim, J. [Korea Inst. of Energy Research, Taejon (Korea, Republic of); Lalvani, S.B.; Muchmore, C.B.; Akash, B.A. [Southern Illinois Univ., Carbondale, IL (United States)

1999-11-01T23:59:59.000Z

111

BIOMASS AND BLACK LIQUOR GASIFIER/GAS TURBINE COGENERATION AT PULP AND PAPER MILLS  

E-Print Network [OSTI]

BIOMASS AND BLACK LIQUOR GASIFIER/GAS TURBINE COGENERATION AT PULP AND PAPER MILLS ERIC D. LARSON modeling of gasifier/gas turbine pulp-mill cogeneration systemsusing gasifier designs under commercial gasification. The use of biomass fuels with gas turbines could transform a typical pulp mill from a net

112

Spent-fuel-storage alternatives  

SciTech Connect (OSTI)

The Spent Fuel Storage Alternatives meeting was a technical forum in which 37 experts from 12 states discussed storage alternatives that are available or are under development. The subject matter was divided into the following five areas: techniques for increasing fuel storage density; dry storage of spent fuel; fuel characterization and conditioning; fuel storage operating experience; and storage and transport economics. Nineteen of the 21 papers which were presented at this meeting are included in this Proceedings. These have been abstracted and indexed. (ATT)

Not Available

1980-01-01T23:59:59.000Z

113

Novel Pulping Technology: Directed Green Liquor Utilization (D-GLU) Pulping  

SciTech Connect (OSTI)

The general objectives of this new project are the same as those described in the original proposal. Conventional kraft pulping technologies will be modified for significant improvements in pulp production, such as strength, bleachability, and yield by using green liquor, a naturally high, kraft mill-derived sulfidity source. Although split white liquor sulfidity and other high sulfidity procedures have the promise of addressing several of the latter important economic needs of pulp mills, they require considerable engineering/capital retrofits, redesigned production methods, and thus add to overall mill expenditures. Green liquor use, however, possesses the required high sulfidity to obtain in general the benefits attributable to higher sulfidity cooking, without the required capital constraints for implementation. Before introduction of green liquor in our industrial operations, a stronger understanding of its fundamental chemical interaction with the lignin and carbohydrates in US hardwood and softwoods must be obtained. In addition, its effect on bleachability, enhancement of pulp properties, and influence on the overall energy and recovery of the mill requires further exploration before the process witnesses widespread mill use in North America. Thus, proof of principle will be accomplished in this work and the consequent effect of green liquor and other high sulfide sources on the pulping and bleaching operations will be explored for US kraft mills. The first year of this project will generate the pertinent information to validate its ability for implementation in US pulping operations, whereas year two will continue this work while proceeding to analyze pulp bleachability and final pulp/paper properties and develop a general economic and feasibility analysis for its eventual implementation in North America.

Lucian A. Lucia

2005-11-15T23:59:59.000Z

114

Black liquor combustion validated recovery boiler modeling, five-year report  

SciTech Connect (OSTI)

The objective of this project was to develop a new computer model of a recovery boiler furnace using a computational fluid dynamics (CFD) code specifically tailored to the requirements for solving recovery boiler flows, and using improved submodels for black liquor combustion based on continued laboratory fundamental studies. The project originated in October 1990 and was scheduled to run for four years. At that time, there was considerable emphasis on developing accurate predictions of the physical carryover of macroscopic particles of partially burnt black liquor and smelt droplets out of the furnace, since this was seen as the main cause of boiler plugging. This placed a major emphasis on gas flow patterns within the furnace and on the mass loss rates and swelling and shrinking rates of burning black liquor drops. As work proceeded on developing the recovery boiler furnace model, it became apparent that some recovery boilers encounter serious plugging problems even when physical carryover was minimal. After the original four-year period was completed, the project was extended to address this issue. The objective of the extended project was to improve the utility of the models by including the black liquor chemistry relevant to air emissions predictions and aerosol formation, and by developing the knowledge base and computational tools to relate furnace model outputs to fouling and plugging of the convective sections of the boilers. The work done to date includes CFD model development and validation, acquisition of information on black liquor combustion fundamentals and development of improved burning models, char bed model development, and model application and simplification.

Grace, T.M.; Frederick, W.J.; Salcudean, M.; Wessel, R.A.

1996-08-01T23:59:59.000Z

115

Combustion processes in black liquor recovery: Analysis and interpretation of combustion rate data and an engineering design model  

SciTech Connect (OSTI)

The overall objective of this project is to develop computational models for predicting the combustion times for black liquor droplets in a recovery furnace environment. These models are needed as an important component of large-scale, global recovery boiler models. The work is divided into two tasks: interpretation of experimental black liquor single droplet combustion data from two laboratories; and formulation and evaluation of computational models for the stages of combustion of black liquor droplets. This report contains the results of the project. 109 refs., 64 figs., 12 tabs.

Fredrick, W.J.

1990-03-01T23:59:59.000Z

116

Spent Fuel Disposal Trust Fund (Maine)  

Broader source: Energy.gov [DOE]

Any licensee operating a nuclear power plant in this State shall establish a segregated Spent Nuclear Fuel Disposal Trust Fund in accordance with this subchapter for the eventual disposal of spent...

117

Fundamental Study of Black Liquor Gasification Kinetics. Quarterly progress report for the period October 1999 to December 1999  

SciTech Connect (OSTI)

The overall objective of this research is to evaluate the kinetics of gasification of kraft black liquor under laboratory conditions simulating pressurized, oxygen-blown gasification. The significant independent variables are gasifier temperature, black liquor composition particle size, and particle residence time. The authors will quantify their impact on the concentration of major and trace gas phase species, as well as the composition of condensed phase inorganic products, including specification of the Na- and S-containing compounds and overall carbon conversion.

NONE

2000-01-31T23:59:59.000Z

118

Actinide removal from spent salts  

DOE Patents [OSTI]

A method for removing actinide contaminants (uranium and thorium) from the spent salt of a molten salt oxidation (MSO) reactor is described. Spent salt is removed from the reactor and analyzed to determine the contaminants present and the carbonate concentration. The salt is dissolved in water, and one or more reagents are added to precipitate the thorium as thorium oxide and/or the uranium as either uranium oxide or as a diuranate salt. The precipitated materials are filtered, dried and packaged for disposal as radioactive waste. About 90% of the thorium and/or uranium present is removed by filtration. After filtration, salt solutions having a carbonate concentration >20% can be dried and returned to the reactor for re-use. Salt solutions containing a carbonate concentration <20% require further clean-up using an ion exchange column, which yields salt solutions that contain less than 0.1 ppm of thorium or uranium.

Hsu, Peter C. (Pleasanton, CA); von Holtz, Erica H. (Livermore, CA); Hipple, David L. (Livermore, CA); Summers, Leslie J. (Livermore, CA); Adamson, Martyn G. (Danville, CA)

2002-01-01T23:59:59.000Z

119

Spent fuel integrity during transportation  

SciTech Connect (OSTI)

The conditions of recent shipments of light water reactor spent fuel were surveyed. The radioactivity level of cask coolant was examined in an attempt to find the effects of transportation on LWR fuel assemblies. Discussion included potential cladding integrity loss mechanisms, canning requirements, changes of radioactivity levels, and comparison of transportation in wet or dry media. Although integrity loss or degradation has not been identified, radioactivity levels usually increase during transportation, especially for leaking assemblies.

Funk, C.W.; Jacobson, L.D.

1980-01-01T23:59:59.000Z

120

Development of viscometers for kraft black liquor. Summary report, Phase 2 and 2A  

SciTech Connect (OSTI)

This report documents the results of the evaluation of the on-line prototype viscometers for kraft black liquors carried out at the Pilot Plant facilities of the University of Florida. The original plan called for the evaluation of five prototype on-line viscometers along with laboratory bench versions. At a later stage in the project an additional experimental prototype under development at Southwest Research Institute was added. The viscometers are evaluated for accuracy and repeatability under varying process conditions, such as black liquor species, solids content, temperature, flow rate, and contaminants, as well as for maintenance and reliability. This document reports extensive results of the evaluations and recommendations for design modifications and for the installation of the instruments in industrial pulping mills for further field evaluations in Phase 3 of the project. The report also documents relevant details of the final design of the pilot flow loop used to support the experiments.

Fricke, A.L.; Crisalle, O.D.

1996-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Comparison of Refractory Performance in Black Liquor Gasifiers and a Smelt Test System  

SciTech Connect (OSTI)

Prior laboratory corrosion studies along with experience at the black liquor gasifier in New Bern, North Carolina, clearly demonstrate that serious material problems exist with the gasifier's refractory lining. Mullite-based and alumina-based refractories used at the New Bern facility suffered significant degradation even though they reportedly performed adequately in smaller scale systems. Oak Ridge National Laboratory's involvement in the failure analysis, and the initial exploration of suitable replacement materials, led to the realization that a simple and reliable, complementary method for refractory screening was needed. The development of a laboratory test system and its suitability for simulating the environment of black liquor gasifiers was undertaken. Identification and characterization of corrosion products were used to evaluate the test system as a rapid screening tool for refractory performance and as a predictor of refractory lifetime. Results from the test systems and pl ants were qualitatively similar.

Peascoe, RA

2001-09-25T23:59:59.000Z

122

Probability of spent fuel transportation accidents  

SciTech Connect (OSTI)

The transported volume of spent fuel, incident/accident experience and accident environment probabilities were reviewed in order to provide an estimate of spent fuel accident probabilities. In particular, the accident review assessed the accident experience for large casks of the type that could transport spent (irradiated) nuclear fuel. This review determined that since 1971, the beginning of official US Department of Transportation record keeping for accidents/incidents, there has been one spent fuel transportation accident. This information, coupled with estimated annual shipping volumes for spent fuel, indicated an estimated annual probability of a spent fuel transport accident of 5 x 10/sup -7/ spent fuel accidents per mile. This is consistent with ordinary truck accident rates. A comparison of accident environments and regulatory test environments suggests that the probability of truck accidents exceeding regulatory test for impact is approximately 10/sup -9//mile.

McClure, J. D.

1981-07-01T23:59:59.000Z

123

Feasibility of black liquor gasification in combined cycle cogeneration. Final report, Phase I  

SciTech Connect (OSTI)

A small-scale test program of 65% solids black liquor gasification was conducted in the bench-scale molten salt gasifier. Nine tests were performed using both air and oxygen as the oxidant. The black liquor gasified readily and the product gas had a dry-basis heating value of 70 Btu/scf with air and about 250 Btu/scf with oxygen. These values were almost identical to values predicted on the basis of thermodynamic equilibrium in the gas phase, indicating that the system had achieved near-equilibrium. However, the reduction of the melt to sodium sulfide was generally low. An independent research program aimed at improving the performance of air-blown black liquor gasification was conducted. That work resulted in a modified gasifier system design which increased the off-gas heating value to 120 Btu/scf and the reduction of the melt to over 95%. This was an improvement that would potentially allow use of the scrubbed product gas as a feed to a combustion gas turbine without prior enrichment.

Kelleher, E.G.

1983-06-30T23:59:59.000Z

124

Combined biomass and black liquor gasifier/gas turbine cogeneration at pulp and paper mills  

SciTech Connect (OSTI)

Kraft pulp and paper mills generate large quantities of black liquor and byproduct biomass suitable for gasification. These fuels are used today for onsite cogeneration of heat and power in boiler/steam turbine systems. Gasification technologies under development would enable these fuels to be used in gas turbines. This paper reports results of detailed full-load performance modeling of pulp-mill cogeneration systems based on gasifier/gas turbine technologies. Pressurized, oxygen-blown black liquor gasification, the most advanced of proposed commercial black liquor gasifier designs, is considered, together with three alternative biomass gasifier designs under commercial development (high-pressure air-blown, low-pressure air-blown, and low-pressure indirectly-heated). Heavy-duty industrial gas turbines of the 70-MW{sub e} and 25-MW {sub e} class are included in the analysis. Results indicate that gasification-based cogeneration with biomass-derived fuels would transform a typical pulp mill into significant power exporter and would also offer possibilities for net reductions in emissions of carbon dioxide relative to present practice.

Larson, E.D.; Kreutz, T.G. [Princeton Univ., NJ (United States). Center for Energy and Environmental Studies; Consonni, S. [Politecnico di Milano, Milan (Italy). Dipt. di Energetica

1999-07-01T23:59:59.000Z

125

Pulsed combustion process for black liquor gasification. Second annual report, [November 1990--February 1992  

SciTech Connect (OSTI)

This second annual report summarizes the work accomplished during the period November 1990 through February 1992 for DOE Cooperative Agreement No. DE-FC05-90CE40893. The overall project objective is to field test an energy-efficient, innovative black liquor recovery system at a significant industrial scale. This is intended to demonstrate the maturity of the technology in an industrial environment and serve as an example to the industry of the safer and more energy-efficient processing technique. The project structure is comprised of three primary activities: process characterization testing, scale-up hardware development, and field testing. The objective of the process characterization testing was to resolve key technical issues regarding the black liquor recovery process that were identified during earlier laboratory verification tests. This was intended to provide a sound engineering data base for the design, construction and testing of a nominal 1.0 TPH integrated black liquor recovery gasifier. The objective of the scale-up hardware development effort was to ensure that key hardware components, in particular the pulse heater module, would perform reliably and safely in the field. Finally, the objective of the field test is to develop an industrial data base sufficient to demonstrate the capabilities and performance of the operating system with respect to thermal efficiency, product quality, fuel handling, system control, reliability and cost. These tests are to provide long-term and continuous operating data at a capacity unattainable in the bench-scale apparatus.

Not Available

1993-02-01T23:59:59.000Z

126

Spent nuclear fuel sampling strategy  

SciTech Connect (OSTI)

This report proposes a strategy for sampling the spent nuclear fuel (SNF) stored in the 105-K Basins (105-K East and 105-K West). This strategy will support decisions concerning the path forward SNF disposition efforts in the following areas: (1) SNF isolation activities such as repackaging/overpacking to a newly constructed staging facility; (2) conditioning processes for fuel stabilization; and (3) interim storage options. This strategy was developed without following the Data Quality Objective (DQO) methodology. It is, however, intended to augment the SNF project DQOS. The SNF sampling is derived by evaluating the current storage condition of the SNF and the factors that effected SNF corrosion/degradation.

Bergmann, D.W.

1995-02-08T23:59:59.000Z

127

Spent Fuel Transportation Risk Assessment  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of EnergyEnergyENERGYWomen Owned Small Business Webinar June 20,Department ofSpecialEnergy SpelmanSpent

128

Red Cabbage Smoothie Ingredients  

E-Print Network [OSTI]

Red Cabbage Smoothie Ingredients · 1 1/2 cups cold water · 1/2 small head red cabbage, quartered: http://www.accordingtoelle.com/2014/05/red-cabbage-smoothie/ Recipe provided by former chef

Myers, Lawrence C.

129

Red River Compact (Texas)  

Broader source: Energy.gov [DOE]

The Red River Compact Commission administers the Red River Compact to ensure that Texas receives its equitable share of quality water from the Red River and its tributaries as apportioned by the...

130

Improved Materials for Use as Components in Kraft Black Liquor Recovery Boilers  

SciTech Connect (OSTI)

This Cooperative Research and Development Agreement (CRADA) was undertaken to evaluate current and improved materials and materials processing conditions for use as components in kraft black liquor recovery boilers and other unit processes. The main areas addressed were: (1) Improved Black Liquor Nozzles, (2) Weld Overlay of Composite Floor Tubes, and (3) Materials for Lime Kilns. Iron aluminide was evaluated as an alternate material for the nozzles used to inject an aqueous solution known as black liquor into recovery boilers as well for the uncooled lining in the ports used for the nozzles. Although iron aluminide is known to have much better sulfidation resistance in gases than low alloy and stainless steels, it did not perform adequately in the environment where it came into contact with molten carbonate, sulfide and sulfate salts. Weld overlaying carbon steel tubes with a layer of stainless weld metal was a proposed method of extending the life of recovery boiler floor tubes that have experienced considerable fireside corrosion. After exposure under service conditions, sections of weld overlaid floor tubes were removed from a boiler floor and examined metallographically. Examination results indicated satisfactory performance of the tubes. Refractory-lined lime kilns are a critical component of the recovery process in kraft pulp mills, and the integrity of the lining is essential to the successful operation of the kiln. A modeling study was performed to determine the cause of, and possible solutions for, the repeated loss of the refractory lining from the cooled end of a particular kiln. The evaluation showed that the temperature, the brick shape and the coefficient of friction between the bricks were the most important parameters influencing the behavior of the refractory lining.

Keiser, J.R.

2001-10-22T23:59:59.000Z

131

Effect of pulsations on black liquor gasification. Progress report, July--September 1995  

SciTech Connect (OSTI)

The objective of this study is to investigate the use of pulse combustion to provide the energy required for the endothermic gasification of black liquor in a fluidized bed. In this process it is critical that the temperature remain in the small window above the gasification temperature but below the smelting temperature of the inorganic salts in the black liquor. Pulse combustors have been shown to have high heat transfer rates between the hot combustion products and the combustor tailpipe. Similarly, fluidized beds have high heat transfer rates within the bed itself, promoting temperature uniformity throughout. Typical analysis of the gasified black liquor shows there is a large percentage of combustible gases in the products of the gasification process (approximately 70%). The potential exists, therefore, for using this fuel mixture to fire the pulse combustor. This makes the entire process more efficient and may be necessary to make it economically feasible. The overall goals of this study are to determine (1) which is the limiting heat transfer rate in the process of transferring the heat from the hot combustion products to the pipe, through the pipe, from the tailpipe to the bed and then throughout the bed; i.e., whether increased heat transfer within the pulse combustor will significantly increase the overall heat transfer rate; (2) whether the temperature distribution in the bed can be maintained within the narrow temperature range required by the process without generating hot spots in the bed even if the heat transfer from the pulse combustor is significantly increased; and (3) whether the fuel gas produced during the gasification process can be used to efficiently fire the pulse combustor.

Kushari, A.; Jeong, H.; Jagoda, J.I.; Zinn, B.T.

1995-12-31T23:59:59.000Z

132

Improved Materials for Use as Components in Kraft Black Liquor Recovery Boilers  

SciTech Connect (OSTI)

This Cooperative Research and Development Agreement (CRADA) was undertaken to evaluate current and improved materials and materials processing conditions for use as components in kraft black liquor recovery boilers and other unit processes. The main areas addressed were: (1) Improved Black Liquor Nozzles, (2) Weld Overlay of Composite Floor Tubes, and (3) Materials for Lime Kilns. Iron aluminide was evaluated as an alternate material for the nozzles used to inject an aqueous solution known as black liquor into recovery boilers as well for the uncooled lining in the ports used for the nozzles. Although iron aluminide is known to have much better sulfidation resistance in gases than low alloy and stainless steels, it did not perform adequately in the environment where it came into contact with molten carbonate, sulfide and sulfate salts. Weld overlaying carbon steel tubes with a layer of stainless weld metal was a proposed method of extending the life of recovery boiler floor tubes that have experienced considerable fireside corrosion. After exposure under service conditions, sections of weld overlaid floor tubes were removed from a boiler floor and examined metallographically. Examination results indicated satisfactory performance of the tubes. Refractory-lined lime kilns are a critical component of the recovery process in kraft pulp mills, and the integrity of the lining is essential to the successful operation of the kiln. A modeling study was performed to determine the cause of, and possible solutions for, the repeated loss of the refractory lining from the cooled end of a particular kiln. The evaluation showed that the temperature, the brick shape and the coefficient of friction between the bricks were the most important parameters influencing the behavior of the refractory lining.

Keiser, J.R.

2000-04-18T23:59:59.000Z

133

Conversion of a black liquor recovery boiler to wood firing: A case history  

SciTech Connect (OSTI)

In 1983 a large integrated pulp and paper mill in southeastern United States retired an older chemical recovery boiler when it was replaced by a newer and larger unit as part of a mill expansion. At that time the mill was generating steam and power using wood waste, natural gas and black liquor, a common fuel mix for pulp mills. The retirement of the recovery boiler presented an opportunity for the mill and corporate engineering to evaluate various mixes of fuels for the mill.

Eleniewski, M.A. [Detroit Stoker Company, Monroe, MI (United States)

1994-12-31T23:59:59.000Z

134

Eucalyptus kraft black liquor enhances growth and productivity of Spirulina in outdoor cultures  

SciTech Connect (OSTI)

Mass cultivation of microalgae for commercial applications suffers from poor productivities when measured against laboratory results or theoretical projections. In an effort to reduce this gap it was discovered that addition of eucalyptus kraft black liquor (BL) enhanced biomass productivity in outdoor cultures of Spirulina by increasing growth rate by 38% and biomass yield by 43%. BL treatment resulted in elevation of nitrogen assimilating enzyme activities and efficiency of phosphate utilization. Analyses of forenoon and afternoon oxygen production rates (OPRs) indicated higher photosynthetic and respiratory activity in BL-treated cultures compared to untreated cultures. 20 refs., 1 fig., 2 tabs.

Chauhan, V.S.; Singh, G.; Ramamurthy, V. [Thapar Institute of Engineering and Technology, Patiala (India)

1995-07-01T23:59:59.000Z

135

Spent Nuclear Fuel (SNF) Project Execution Plan  

SciTech Connect (OSTI)

The Spent Nuclear Fuel (SNF) Project supports the Hanford Site Mission to cleanup the Site by providing safe, economic, environmentally sound management of Site spent nuclear fuel in a manner that reduces hazards by staging it to interim onsite storage and deactivates the 100 K Area facilities.

LEROY, P.G.

2000-11-03T23:59:59.000Z

136

Electronic nose with a new feature reduction method and a multi-linear classifier for Chinese liquor classification  

SciTech Connect (OSTI)

An electronic nose (e-nose) was designed to classify Chinese liquors of the same aroma style. A new method of feature reduction which combined feature selection with feature extraction was proposed. Feature selection method used 8 feature-selection algorithms based on information theory and reduced the dimension of the feature space to 41. Kernel entropy component analysis was introduced into the e-nose system as a feature extraction method and the dimension of feature space was reduced to 12. Classification of Chinese liquors was performed by using back propagation artificial neural network (BP-ANN), linear discrimination analysis (LDA), and a multi-linear classifier. The classification rate of the multi-linear classifier was 97.22%, which was higher than LDA and BP-ANN. Finally the classification of Chinese liquors according to their raw materials and geographical origins was performed using the proposed multi-linear classifier and classification rate was 98.75% and 100%, respectively.

Jing, Yaqi; Meng, Qinghao, E-mail: qh-meng@tju.edu.cn; Qi, Peifeng; Zeng, Ming; Li, Wei; Ma, Shugen [Tianjin Key Laboratory of Process Measurement and Control, Institute of Robotics and Autonomous Systems, School of Electrical Engineering and Automation, Tianjin University, Tianjin 300072 (China)] [Tianjin Key Laboratory of Process Measurement and Control, Institute of Robotics and Autonomous Systems, School of Electrical Engineering and Automation, Tianjin University, Tianjin 300072 (China)

2014-05-15T23:59:59.000Z

137

Recovery of manganese oxides from spent alkaline and zinccarbon batteries. An application as catalysts for VOCs elimination  

SciTech Connect (OSTI)

Highlights: Manganese oxides were synthesized using spent batteries as raw materials. Spent alkaline and zinccarbon size AA batteries were used. A biohydrometallurgical process was employed to bio-lixiviate batteries. Manganese oxides were active in the oxidation of VOCs (ethanol and heptane). - Abstract: Manganese, in the form of oxide, was recovered from spent alkaline and zinccarbon batteries employing a biohydrometallurgy process, using a pilot plant consisting in: an air-lift bioreactor (containing an acid-reducing medium produced by an Acidithiobacillus thiooxidans bacteria immobilized on elemental sulfur); a leaching reactor (were battery powder is mixed with the acid-reducing medium) and a recovery reactor. Two different manganese oxides were recovered from the leachate liquor: one of them by electrolysis (EMO) and the other by a chemical precipitation with KMnO{sub 4} solution (CMO). The non-leached solid residue was also studied (RMO). The solids were compared with a MnO{sub x} synthesized in our laboratory. The characterization by XRD, FTIR and XPS reveal the presence of Mn{sub 2}O{sub 3} in the EMO and the CMO samples, together with some Mn{sup 4+} cations. In the solid not extracted by acidic leaching (RMO) the main phase detected was Mn{sub 3}O{sub 4}. The catalytic performance of the oxides was studied in the complete oxidation of ethanol and heptane. Complete conversion of ethanol occurs at 200 C, while heptane requires more than 400 C. The CMO has the highest oxide selectivity to CO{sub 2}. The results show that manganese oxides obtained using spent alkaline and zinccarbon batteries as raw materials, have an interesting performance as catalysts for elimination of VOCs.

Gallegos, Mara V., E-mail: plapimu@yahoo.com.ar [Pla.Pi.Mu-Planta Piloto Multipropsito, (CICPBA-UNLP) Cno. Centenario y 505, M.B. Gonnet, Buenos Aires (Argentina); Falco, Lorena R., E-mail: mlfalco@quimica.unlp.edu.ar [Pla.Pi.Mu-Planta Piloto Multipropsito, (CICPBA-UNLP) Cno. Centenario y 505, M.B. Gonnet, Buenos Aires (Argentina); Peluso, Miguel A., E-mail: apelu@quimica.unlp.edu.ar [Centro de Investigacin y Desarrollo en Ciencias Aplicadas, Dr. J. Ronco CINDECA (CONICET CCT La Plata), 47 N257, La Plata, Buenos Aires (Argentina); Sambeth, Jorge E., E-mail: sambeth@quimica.unlp.edu.ar [Centro de Investigacin y Desarrollo en Ciencias Aplicadas, Dr. J. Ronco CINDECA (CONICET CCT La Plata), 47 N257, La Plata, Buenos Aires (Argentina); Thomas, Horacio J. [Pla.Pi.Mu-Planta Piloto Multipropsito, (CICPBA-UNLP) Cno. Centenario y 505, M.B. Gonnet, Buenos Aires (Argentina)

2013-06-15T23:59:59.000Z

138

Black liquor combustion validated recovery boiler modeling: Final year report. Volume 4 (Appendix IV)  

SciTech Connect (OSTI)

This project was initiated in October 1990, with the objective of developing and validating a new computer model of a recovery boiler furnace using a computational fluid dynamics (CFD) code specifically tailored to the requirements for solving recovery boiler flows, and using improved submodels for black liquor combustion based on continued laboratory fundamental studies. The key tasks to be accomplished were as follows: (1) Complete the development of enhanced furnace models that have the capability to accurately predict carryover, emissions behavior, dust concentrations, gas temperatures, and wall heat fluxes. (2) Validate the enhanced furnace models, so that users can have confidence in the predicted results. (3) Obtain fundamental information on aerosol formation, deposition, and hardening so as to develop the knowledge base needed to relate furnace model outputs to plugging and fouling in the convective sections of the boiler. (4) Facilitate the transfer of codes, black liquid submodels, and fundamental knowledge to the US kraft pulp industry. Volume 4 contains the following appendix sections: Radiative heat transfer properties for black liquor combustion -- Facilities and techniques and Spectral absorbance and emittance data; and Radiate heat transfer determination of the optical constants of ash samples from kraft recovery boilers -- Calculation procedure; Computation program; Density determination; Particle diameter determination; Optical constant data; and Uncertainty analysis.

Grace, T.M.; Frederick, W.J.; Salcudean, M.; Wessel, R.A.

1998-08-01T23:59:59.000Z

139

Material Characterization and Analysis for Selection of Refractories Used In Black Liquor Gasification  

SciTech Connect (OSTI)

Black liquor gasification provides the pulp and paper industry with a technology which could potentially replace recovery boilers with equipment that could reduce emissions and, if used in a combined cycle system, increase the power production of the mill allowing it to be a net exporter of electrical power. In addition, rather than burning the syngas produced in a gasifier, this syngas could be used to produce higher value chemicals or fuels. However, problems with structural materials, and particularly the refractory lining of the reactor vessel, have caused unplanned shutdowns and resulted in component replacement much sooner than originally planned. Through examination of exposed materials, laboratory corrosion tests and cooperative efforts with refractory manufacturers, many refractory materials issues in high-temperature black liquor gasification have been addressed and optimized materials have been selected for this application. In this paper, the characterization and analysis techniques used for refractory screening and selection will be discussed along with characteristic results from these methods which have led to the selection of optimized materials for this application.

Hemrick, James Gordon [ORNL; Keiser, James R [ORNL; Meisner, Roberta Ann [ORNL; Gorog, John Peter [ORNL

2008-01-01T23:59:59.000Z

140

Material Characterization and Analysis for Selection of Refractories Used in Black Liquor Gasification  

SciTech Connect (OSTI)

Black liquor gasification provides the pulp and paper industry with a technology which could potentially replace recovery boilers with equipment that could reduce emissions and, if used in a combined cycle system, increase the power production of the mill allowing it to be a net exporter of electrical power. In addition, rather than burning the syngas produced in a gasifier, this syngas could be used to produce higher value chemicals or fuels. However, problems with structural materials such as the refractory lining of the reactor vessel have caused unplanned shutdowns and resulted in component replacement much sooner than originally planned. Through examination of exposed materials, laboratory corrosion tests and cooperative efforts with refractory manufacturers, many refractory materials issues in high-temperature black liquor gasification have been addressed and optimized materials have been selected for this application. In this paper, an updated summary of the characterization and analysis techniques used for refractory screening and selection will be discussed along with characteristic results from these methods which have led to the selection of optimized materials for both the hot-face and back-up linings used in this application.

Hemrick, James Gordon [ORNL; Keiser, James R [ORNL; Meisner, Roberta A [University of Tennessee, Knoxville (UTK) & Oak Ridge National Laboratory (ORNL)

2010-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Separation and characterization of lignins from the black liquor of oil palm trunk fiber pulping  

SciTech Connect (OSTI)

Six lignin preparations, isolated by a novel two-step precipitation method instead of the traditional one-step precipitation method from the oil palm trunk fiber pulping (OPTFP) black liquor, were found to be relatively free of nonlignin materials such as polysaccharide degradation products, ash, and salts. A lignin fraction with a purity of 99.5% was obtained at an optimum precipitation pH 1.5 after isolation of the nonlignin materials in ethanol. About 94% of the total lignin was recovered by this novel method at this condition, and the value of COD in the treated black liquor reduced significantly to lower 250. The isolated lignin fractions contained syringyl, guaiacyl, and p-hydroxyphenyl units in an approximate molar ratio of 16--20:5:1 on the basis of chemical and spectroscopic analysis. Small amounts of p-hydroxybenzoic acids were found to be esterified to lignin, while ferulic acids were associated to lignin by ether linkage. {sup 13}C-NMR indicated the presence of {beta}-O-4 ether bonds, and {beta}-5 and 5-5{prime} carbon-carbon linkages between the lignin molecules.

Sun, R.; Tomkinson, J.; Bolton, J.

1999-11-01T23:59:59.000Z

142

National Report Joint Convention on the Safety of Spent Fuel...  

Office of Environmental Management (EM)

National Report Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management National Report Joint Convention on the Safety of Spent...

143

Idaho Spent Fuel Facility (ISFF) Project, Appropriate Acquisition...  

Office of Environmental Management (EM)

Idaho Spent Fuel Facility (ISFF) Project, Appropriate Acquisition Strategy Lessons Learned Report, NNSA, Feb 2010 Idaho Spent Fuel Facility (ISFF) Project, Appropriate Acquisition...

144

MOLTEN SALT CORROSION OF SUPERHEATERS IN BLACK LIQUOR RECOVERY BOILERS John Bohling, University of Tennessee Georgia Tech SURF 2010 Fellow  

E-Print Network [OSTI]

MOLTEN SALT CORROSION OF SUPERHEATERS IN BLACK LIQUOR RECOVERY BOILERS John Bohling, University If the temperature is above the first melting point of the scale, severe corrosion of the tubes can result temperatures, reducing efficiency. The corrosive nature of the superheater environment arises primarily from

Li, Mo

145

Stability and Regeneration of Catalysts for the Destruction of Tars from Bio-mass Black Liquor Gasification  

SciTech Connect (OSTI)

The goal of this project was to develop catalytic materials and processes that would be effective in the destruction of tars formed during the gasification of black liquor and biomass. We report here the significant results obtained at the conclusion of this two year project.

Pradeep Agrawal

2004-09-07T23:59:59.000Z

146

PERFORMANCE OF BLACK LIQUOR GASIFIER/GAS TURBINE COMBINED CYCLE COGENERATION IN mE KRAFT PULP  

E-Print Network [OSTI]

PERFORMANCE OF BLACK LIQUOR GASIFIER/GAS TURBINE COMBINED CYCLE COGENERATION IN mE KRAFT PULP high-temperature gasifiers for gas turbine applications. ABB and MTCr/Stonechem are developing low-load performance of gasifier/gas turbine systemsincorporating the four above-noted gasifier designs are reported

147

Fluoride removal from water with spent catalyst  

SciTech Connect (OSTI)

The adsorption of fluoride from water with spent catalyst was studied. Adsorption density of fluoride decreased with increasing pH. Linear adsorption isotherm was utilized to describe the adsorption reaction. The adsorption was a first-order reaction, and the rate constant increased with decreasing surface loading. Adsorption reaction of fluoride onto spent catalyst was endothermic, and the reaction rate increased slightly with increasing temperature. Fluoro-alumino complex and free fluoride ion were involved in the adsorption reaction. It is proposed that both the silica and alumina fractions of spent catalyst contribute to the removal of fluoride from aqueous solution. Coulombic interaction is proposed as the major driving force of the adsorption reaction of fluoride onto spent catalyst.

Lai, Y.D.; Liu, J.C. [National Taiwan Institute of Technology, Taipei (Taiwan, Province of China)

1996-12-01T23:59:59.000Z

148

Spent fuel storage requirements 1993--2040  

SciTech Connect (OSTI)

Historical inventories of spent fuel are combined with U.S. Department of Energy (DOE) projections of future discharges from commercial nuclear reactors in the United States to provide estimates of spent fuel storage requirements through the year 2040. The needs are estimated for storage capacity beyond that presently available in the reactor storage pools. These estimates incorporate the maximum capacities within current and planned in-pool storage facilities and any planned transshipments of spent fuel to other reactors or facilities. Existing and future dry storage facilities are also discussed. The nuclear utilities provide historical data through December 1992 on the end of reactor life are based on the DOE/Energy Information Administration (EIA) estimates of future nuclear capacity, generation, and spent fuel discharges.

Not Available

1994-09-01T23:59:59.000Z

149

HYDRAULIC CEMENT PREPARATION FROM LURGI SPENT SHALE  

E-Print Network [OSTI]

cement from spent oil shale," Vol. 10, No. 4, p. 54S,Colorado's primary oil shale resource for vertical modifiedSimulated effects of oil-shale development on the hydrology

Mehta, P.K.

2013-01-01T23:59:59.000Z

150

HYDRAULIC CEMENT PREPARATION FROM LURGI SPENT SHALE  

E-Print Network [OSTI]

hydraulic cement from spent oil shale," Vol. 10, No. 4, p.J. W. , "Colorado's primary oil shale resource for verticalSimulated effects of oil-shale development on the hydrology

Mehta, P.K.

2013-01-01T23:59:59.000Z

151

HYDRAULIC CEMENT PREPARATION FROM LURGI SPENT SHALE  

SciTech Connect (OSTI)

Low cost material is needed for grouting abandoned retorts. Experimental work has shown that a hydraulic cement can be produced from Lurgi spent shale by mixing it in a 1:1 weight ratio with limestone and heating one hour at 1000C. With 5% added gypsum, strengths up to 25.8 MPa are obtained. This cement could make an economical addition up to about 10% to spent shale grout mixes, or be used in ordinary cement applications.

Mehta, P.K.; Persoff, P.; Fox, J.P.

1980-06-01T23:59:59.000Z

152

Spent nuclear fuel reprocessing modeling  

SciTech Connect (OSTI)

The long-term wide development of nuclear power requires new approaches towards the realization of nuclear fuel cycle, namely, closed nuclear fuel cycle (CNFC) with respect to fission materials. Plant nuclear fuel cycle (PNFC), which is in fact the reprocessing of spent nuclear fuel unloaded from the reactor and the production of new nuclear fuel (NF) at the same place together with reactor plant, can be one variant of CNFC. Developing and projecting of PNFC is a complicated high-technology innovative process that requires modern information support. One of the components of this information support is developed by the authors. This component is the programme conducting calculations for various variants of process flow sheets for reprocessing SNF and production of NF. Central in this programme is the blocks library, where the blocks contain mathematical description of separate processes and operations. The calculating programme itself has such a structure that one can configure the complex of blocks and correlations between blocks, appropriate for any given flow sheet. For the ready sequence of operations balance calculations are made of all flows, i.e. expenses, element and substance makeup, heat emission and radiation rate are determined. The programme is open and the block library can be updated. This means that more complicated and detailed models of technological processes will be added to the library basing on the results of testing processes using real equipment, in test operating mode. The development of the model for the realization of technical-economic analysis of various variants of technologic PNFC schemes and the organization of 'operator's advisor' is expected. (authors)

Tretyakova, S.; Shmidt, O.; Podymova, T.; Shadrin, A.; Tkachenko, V. [Bochvar Institute, 5 Rogova str., Moscow 123098 (Russian Federation); Makeyeva, I.; Tkachenko, V.; Verbitskaya, O.; Schultz, O.; Peshkichev, I. [Russian Federal Nuclear Center - VNIITF E.I. Zababakhin, p.o.box 245, Snezhinsk, 456770 (Russian Federation)

2013-07-01T23:59:59.000Z

153

Refractory Testing and Evaluation at Oak Ridge National Laboratory for Black Liquor Gasifier Applications.  

SciTech Connect (OSTI)

Work is on-going at Oak Ridge National Laboratory to evaluate refractory containment and smelt contact materials for black liquor gasification applications. Materials have been evaluated and selected for low temperature gasification processes, with a number of materials being installed in commercial units currently under construction. For high temperature low pressure gasification processes, efforts have focused on screening candidate lining materials through immersion testing, improving existing refractory performance through the application of surface treatments, and the installation and evaluation of samples in an operating gasifier in New Bern, NC. Efforts concerning high temperature high pressure gasification have involved the identification and testing of suitable refractory materials for the coating of a helical carbon steel cooling coil arrangment.

Hemrick, James Gordon [ORNL; Keiser, James R [ORNL; Meisner, Roberta Ann [ORNL; Hubbard, Camden R [ORNL; Lara-Curzio, Edgar [ORNL

2006-01-01T23:59:59.000Z

154

Separation of kraft lignin from kraft black liquor: Final report, July 1984-April 1987  

SciTech Connect (OSTI)

The importance of this work is related to the fact that with over 16 million tons of kraft lignin available annually, practically all of it is burned just for its heat value. In essence, kraft lignin has no real value except its heat value. The major accomplishments of this research has shown that it is possible to produce high purity kraft lignin from kraft black liquor. This patented technology represents a way of producing a material that can be utilized in a wide variety of markets. Kraft lignin that was produced using this technology was sent to major corporations who used this kraft lignin as a starting material in their chemical processes. 3 figs.

Kurple, K.R.

1988-04-15T23:59:59.000Z

155

Cracking and Corrosion of Composite Tubes in Black Liquor Recovery Boiler Primary Air Ports  

SciTech Connect (OSTI)

Black liquor recovery boilers are an essential part of kraft mills. Their design and operating procedures have changed over time with the goal of providing improved boiler performance. These performance improvements are frequently associated with an increase in heat flux and/or operating temperature with a subsequent increase in the demand on structural materials associated with operation at higher temperatures and/or in more corrosive environments. Improvements in structural materials have therefore been required. In most cases the alternate materials have provided acceptable solutions. However, in some cases the alternate materials have solved the original problem but introduced new issues. This report addresses the performance of materials in the tubes forming primary air port openings and, particularly, the problems associated with use of stainless steel clad carbon steel tubes and the solutions that have been identified.

Keiser, James R.; Singbeil, Douglas L.; Sarma, Gorti B.; Kish, Joseph R.; Yuan, Jerry; Frederick, Laurie A.; Choudhury, Kimberly A.; Gorog, J. Peter; Jett, Francois R.; Hubbard, Camden R.; Swindeman, Robert W.; Singh, Prett M.; Maziasz, Phillip J.

2006-10-01T23:59:59.000Z

156

HIGHLY ENERGY EFFICIENT D-GLU (DIRECTED-GREEN LIQ-UOR UTILIZATION) PULPING  

SciTech Connect (OSTI)

Purpose: The purpose of the project was to retrofit the front end (pulp house) of a commercial kraft pulping mill to accommodate a mill green liquor (GL) impregna-tion/soak/exposure and accrue downstream physical and chemical benefits while prin-cipally reducing the energy footprint of the mill. A major player in the mill contrib-uting to excessive energy costs is the lime kiln. The project was intended to offload the energy (oil or natural gas) demands of the kiln by by-passing the causticization/slaking site in the recovery area and directly using green liquor as a pulping medium for wood. Scope: The project was run in two distinct, yet mutually compatible, phases: Phase 1 was the pre-commercial or laboratory phase in which NC State University and the Insti-tute of Paper Science and Technology (at the Georgia Institute of Technology) ran the pulping and associated experiments, while Phase 2 was the mill scale trial. The first tri-al was run at the now defunct Evergreen Pulp Mill in Samoa, CA and lead to a partial retrofit of the mill that was not completed because it went bankrupt and the work was no longer the low-hanging fruit on the tree for the new management. The second trial was run at the MeadWestvaco Pulp Mill in Evedale, TX which for all intents and pur-poses was a success. They were able to fully retrofit the mill, ran the trial, studied the pulp properties, and gave us conclusions.

Lucia, Lucian A

2013-04-19T23:59:59.000Z

157

Black Liquor Combustion Validated Recovery Boiler Modeling, Final Year Report, Volume 5: Appendix V  

SciTech Connect (OSTI)

This project was initiated in October 1990 with the objective of developing and validating a new computer model of a recovery boiler furnace using a computational fluid dynamics (CFD) code specifically tailored to the requirements for solving recovery boiler flows, and using improved submodels for black liquor combustion based on continued laboratory fundamental studies. Many of these objectives were accomplished at the end of the first five years and documented in a comprehensive report on that work (DOE/CE/40936-T3, 1996). A critical review of recovery boiler modeling, carried out in 1995, concluded that further enhancements of the model were needed to make reliable predictions of key output variables. In addition, there was a need for sufficient understanding of fouling and plugging processes to allow model outputs to be interpreted in terms of the effect on plugging and fouling. As a result, the project was restructured and reinitiated at the end of October 1995, and was completed in June 1997. The entire project is now complete and this report summarizes all of the work done on the project since it was restructured. The key tasks to be accomplished under the restructured project were to (1) Complete the development of enhanced furnace models that have the capability to accurately predict carryover, emissions behavior, dust concentrations, gas temperatures, and wall heat fluxes; (2) Validate the enhanced furnace models, so that users can have confidence in the results; (3) Obtain fundamental information on aerosol formation, deposition, and hardening so as to develop the knowledge base needed to relate furnace model outputs to plugging and fouling in the convective sections of the boiler; and (4) Facilitate the transfer of codes, black liquor submodels, and fundamental knowledge to the U.S. kraft pulp industry.

Grace, T.M.; Frederick, W.J.; Salcudean, M.; Wessel, R.A.

1998-08-01T23:59:59.000Z

158

Black Liquor Combustion Validated Recovery Boiler Modeling, Final Year Report, Volume 4: Appendix IV  

SciTech Connect (OSTI)

This project was initiated in October 1990 with the objective of developing and validating a new computer model of a recovery boiler furnace using a computational fluid dynamics (CFD) code specifically tailored to the requirements for solving recovery boiler flows, and using improved submodels for black liquor combustion based on continued laboratory fundamental studies. Many of these objectives were accomplished at the end of the first five years and documented in a comprehensive report on that work (DOE/CE/40936-T3, 1996). A critical review of recovery boiler modeling, carried out in 1995, concluded that further enhancements of the model were needed to make reliable predictions of key output variables. In addition, there was a need for sufficient understanding of fouling and plugging processes to allow model outputs to be interpreted in terms of the effect on plugging and fouling. As a result, the project was restructured and reinitiated at the end of October 1995, and was completed in June 1997. The entire project is now complete and this report summarizes all of the work done on the project since it was restructured. The key tasks to be accomplished under the restructured project were to (1) Complete the development of enhanced furnace models that have the capability to accurately predict carryover, emissions behavior, dust concentrations, gas temperatures, and wall heat fluxes; (2) Validate the enhanced furnace models, so that users can have confidence in the results; (3) Obtain fundamental information on aerosol formation, deposition, and hardening so as to develop the knowledge base needed to relate furnace model outputs to plugging and fouling in the convective sections of the boiler; and (4) Facilitate the transfer of codes, black liquor submodels, and fundamental knowledge to the U.S. kraft pulp industry.

Grace, T.M.; Frederick, W.J.; Salcudean, M.; Wessel, R.A.

1998-08-01T23:59:59.000Z

159

Code Red 2 kills off Code Red 1  

E-Print Network [OSTI]

#12;#12;Code Red 2 kills off Code Red 1 Code Red 2 settles into weekly pattern Nimda enters the ecosystem Code Red 2 dies off as programmed CR 1 returns thanks to bad clocks #12;Code Red 2 dies off as programmed Nimda hums along, slowly cleaned up With its predator gone, Code Red 1 comes back, still

Paxson, Vern

160

Spent fuel integrity during dry storage  

SciTech Connect (OSTI)

Information on spent fuel integrity is of interest in evaluating the impact of long-term dry storage on the behavior of spent fuel rods. Spent fuel used during cask performance tests at the Idaho National Engineering Laboratory (INEL) offers significant opportunities for confirmation of the benign nature of long-term dry storage. The cask performance tests conducted at INEL included visual observation and ultrasonic examination of the condition of cladding, fuel rods, and fuel assembly hardware before dry storage and consolidation of the fuel; and a qualitative determination of the effect of dry storage and fuel consolidation on fission gas release from the spent fuel rods. A variety of cover gases and cask orientations were used during the cask performance tests. Cover gases included vacuum, nitrogen, and helium. The nitrogen and helium backfills were sampled and analyzed to detect leaking spent fuel rods. At the conclusion of each performance test, periodic gas sampling was conducted on each cask as part of a surveillance and monitoring activity. Continued surveillance and monitoring activities are being conducted for intact fuel in a CASTOR V/21 cask and for consolidated fuel in a VSC-17 cask. The results of the gas sampling activities are reported in this paper.

McKinnon, M.A.

1995-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Spent Nuclear Fuel Alternative Technology Decision Analysis  

SciTech Connect (OSTI)

The Westinghouse Savannah River Company (WSRC) made a FY98 commitment to the Department of Energy (DOE) to recommend a technology for the disposal of aluminum-based spent nuclear fuel (SNF) at the Savannah River Site (SRS). The two technologies being considered, direct co-disposal and melt and dilute, had been previously selected from a group of eleven potential SNF management technologies by the Research Reactor Spent Nuclear Fuel Task Team chartered by the DOE''s Office of Spent Fuel Management. To meet this commitment, WSRC organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and ultimately provide a WSRC recommendation to DOE on a preferred SNF alternative management technology.

Shedrow, C.B.

1999-11-29T23:59:59.000Z

162

69. Red Butte-Red Fir Ridge (Shasta Red Fir) (Imper 1988b, Cheng 1996d)  

E-Print Network [OSTI]

69. Red Butte-Red Fir Ridge (Shasta Red Fir) (Imper 1988b, Cheng 1996d) Location This established (fig. 139). Ecological subsection ­ High Cascades (M261Df). Target Element Red Fir (Abies magnifica) Distinctive Features Shasta Red Fir Forest: Taxonomically, the description of Shasta red fir (Abies magnifica

Standiford, Richard B.

163

Spent Fuel Background Report Volume I  

SciTech Connect (OSTI)

This report is an overview of current spent nuclear fuel management in the DOE complex. Sources of information include published literature, internal DOE documents, interviews with site personnel, and information provided by individual sites. Much of the specific information on facilities and fuels was provided by the DOE sites in response to the questionnaire for data for spent fuels and facilities data bases. This information is as accurate as is currently available, but is subject to revision pending results of further data calls. Spent fuel is broadly classified into three categories: (a) production fuels, (b) special fuels, and (c) naval fuels. Production fuels, comprising about 80% of the total inventory, are those used at Hanford and Savannah River to produce nuclear materials for defense. Special fuels are those used in a wide variety of research, development, and testing activities. Special fuels include fuel from DOE and commercial reactors used in research activities at DOE sites. Naval fuels are those developed and used for nuclear-powered naval vessels and for related research and development. Given the recent DOE decision to curtail reprocessing, the topic of main concern in the management of spent fuel is its storage. Of the DOE sites that have spent nuclear fuel, the vast majority is located at three sites-Hanford, INEL, and Savannah River. Other sites with spent fuel include Oak Ridge, West Valley, Brookhaven, Argonne, Los Alamos, and Sandia. B&W NESI Lynchburg Technology Center and General Atomics are commercial facilities with DOE fuel. DOE may also receive fuel from foreign research reactors, university reactors, and other commercial and government research reactors. Most DOE spent fuel is stored in water-filled pools at the reactor facilities. Currently an engineering study is being performed to determine the feasibility of using dry storage for DOE-owned spent fuel currently stored at various facilities. Delays in opening the deep geologic repository and the decision to phase out reprocessing of production fuels are extending the need for interim storage. The report describes the basic storage conditions and the general SNF inventory at individual DOE facilities.

Abbott, D.

1994-03-01T23:59:59.000Z

164

Gasification of kraft black liquor and use of the products in combined cycle cogeneration. Final report, Phase II  

SciTech Connect (OSTI)

This Phase II study of kraft black liquor gasification and use of the product gases in combined cycle cogeneration based on combustion gas turbines was motivated by the very promising results of the Phase I feasibility study. The Phase I study indicated that the alternative technology to the Tomlinson recovery furnace had the potential of improving the energy efficiency and safety of combusting black liquor, reducing the capital and operating costs, increasing the electric power output, and providing an economical system for incremental kraft capacity additions. During Phase II, additional bench-scale experiments were run, pilot-scale experiments were conducted, equipment systems were investigated, and performance and economics were reanalyzed. All of the objectives of the Phase II project were met. Recommendations are summarized.

Kelleher, E.G.

1985-07-01T23:59:59.000Z

165

Simultaneous measurement of the surface temperature and the release of atomic sodium from a burning black liquor droplet  

SciTech Connect (OSTI)

Simultaneous measurement of the concentration of released atomic sodium, swelling, surface and internal temperature of a burning black liquor droplet under a fuel lean and rich condition has been demonstrated. Two-dimensional two-colour optical pyrometry was employed to determine the distribution of surface temperature and swelling of a burning black liquor droplet while planar laser-induced fluorescence (PLIF) was used to assess the temporal release of atomic sodium. The key findings of these studies are: (i) the concentration of atomic sodium released during the drying and devolatilisation stages was found to be correlated with the external surface area; and (ii) the insignificant presence of atomic sodium during the char consumption stage shows that sodium release is suppressed by the lower temperature and by the high CO{sub 2} content in and around the particle. (author)

Saw, Woei L.; Nathan, Graham J. [Centre for Energy Technology, The University of Adelaide, SA 5006 (Australia); School of Mechanical Engineering, The University of Adelaide (Australia); Ashman, Peter J.; Alwahabi, Zeyad T. [Centre for Energy Technology, The University of Adelaide, SA 5006 (Australia); School of Chemical Engineering, The University of Adelaide (Australia); Hupa, Mikko [Process Chemistry Centre, Aabo Akademi, Biskopsgatan 8 FI-20500 Aabo (Finland)

2010-04-15T23:59:59.000Z

166

Direct Causticizing for Black Liquor Gasification in a Circulating Fluidized Bed  

SciTech Connect (OSTI)

Gasification of black liquor (BLG) has distinct advantages over direct combustion in Tomlinson recovery boilers. In this project we seek to resolve causticizing issues in order to make pressurized BLG even more efficient and cost-effective. One advantage of BLG is that the inherent partial separation of sulfur and sodium during gasification lends itself to the use of proven high yield variants to conventional kraft pulping which require just such a separation. Processes such as polysulfide, split sulfidity, ASAQ, and MSSAQ can increase pulp yield from 1% to 10% over conventional kraft but require varying degrees of sulfur/sodium separation, which requires additional [and costly] processing in a conventional Tomlinson recovery process. However during gasification, the sulfur is partitioned between the gas and smelt phases, while the sodium all leaves in the smelt; thus creating the opportunity to produce sulfur-rich and sulfur-lean white liquors for specialty pulping processes. A second major incentive of BLG is the production of a combustible product gas, rich in H2 and CO. This product gas (a.k.a. syngas) can be used in gas turbines for combined cycle power generation (which is twice as efficient as the steam cycle alone), or it can be used as a precursor to form liquid fuels, such as dimethyl ether or Fischer Tropsh diesel. There is drawback to BLG, which has the potential to become a third major incentive if this work is successful. The causticizing load is greater for gasification of black liquor than for combustion in a Tomlinson boiler. So implementing BLG in an existing mill would require costly increases to the causticizing capacity. In situ causticizing [within the gasifier] would handle the entire causticizing load and therefore eliminate the lime cycle entirely. Previous work by the author and others has shown that titanate direct causticizing (i.e. in situ) works quite well for high-temperature BLG (950C), but was limited to pressures below about 5 bar. It is desirable however to operate BLG at 20-30 bar for efficiency reasons related to either firing the syngas in a turbine, or catalytically forming liquid fuels. This work focused on achieving high direct causticizing yields at 20 bars pressure. The titanate direct causticizing reactions are inhibited by CO2. Previous work has shown that the partial pressure of CO2 should be kept below about 0.5 bar in order for the process to work. This translates to a total reactor pressure limit of about 5 bar for airblown BLG, and only 2 bar for O2-blown BLG. In this work a process was developed in which the CO2 partial pressure could be manipulated to a level under 0.5 bar with the total system pressure at 10 bar during O2-blown BLG. This fell short of our 20 bar goal but still represents a substantial increase in the pressure limit. A material and energy balance was performed, as well as first-pass economics based on capital and utilities costs. Compared to a reference case of using BLG with a conventional lime cycle [Larson, 2003], the IRR and NVP were estimated for further replacing the lime kiln with direct causticizing. The economics are strongly dependent on the price of lime kiln fuel. At $6/mmBTU the lime cycle is the clear choice. At $8/mmBTU the NPV is $10M with IRR of 17%. At $12/mmBTU the NPV is $45M with IRR of 36%. To further increase the total allowable pressure, the CO2 could be further decreased by further decreasing the temperature. Testing should be done at 750C. Also a small pilot should be built.

Scott Sinquefield; Xiaoyan Zeng, Alan Ball

2010-03-02T23:59:59.000Z

167

Are red 2MASS QSOs young?  

E-Print Network [OSTI]

We use photometric data from Spitzer to explore the mid- and far-IR properties of 10 red QSOs (J-K>2, R-K>5) selected by combining the 2MASS in the NIR with the SDSS at optical wavelengths. Optical and/or near-infrared spectra are available for 8/10 sources. Modeling the SED from UV to far-IR shows that moderate dust reddening (A_V=1.3-3.2) can explain the red optical and near-IR colours of the sources in the sample. There is also evidence that red QSOs have 60/12micron luminosity ratio higher than PG QSOs (97% significance). This can be interpreted as a higher level of star-formation in these systems (measured by the 60micron luminosity) for a given AGN power (approximated by the 12micron luminosity). This is consistent with a picture where red QSOs represent an early phase of AGN evolution, when the supermassive black hole is enshrouded in dust and gas clouds, which will eventually be blown out (possibly by AGN driven outflows) and the system will appear as typical optically luminous QSO. There is also tentative evidence significant at the 96% level that red 2MASS QSOs are more often associated with radio emission than optically selected SDSS QSOs. This may indicate outflows, also consistent with the young AGN interpretation. We also estimate the space density of red QSOs relative to optically selected SDSS QSOs, taking into account the effect of dust extinction and the intrinsic luminosity of the sources. We estimate that the fraction of red QSOs in the overall population increases from 3% at M_K=-27.5mag to 12% at M_K=-29.5mag. This suggests that reddened QSOs become more important at the bright end of the Luminosity Function. If red QSOs are transition objects on the way to becoming typical optically luminous QSOs, the low fractions above suggest that these systems spent <12% of their lifetime at the "reddened" stage.

A. Georgakakis; D. L. Clements; G. Bendo; M. Rowan-Robinson; K. Nandra; M. S. Brotherton

2008-12-10T23:59:59.000Z

168

CONTAMINATION OF GROUNDWATER BY ORGANIC POLLUTANTS LEACHED FROM IN-SITU SPENT SHALE  

E-Print Network [OSTI]

from Characterization of Spent Shale s . , , . . . ,4. Preparation of Spent Shale Samples and Procedure forof Particular Types of Spent Shale References Appendix A.

Amy, Gary L.

2013-01-01T23:59:59.000Z

169

Spent Nuclear Fuel (SNF) Project Product Specification  

SciTech Connect (OSTI)

This document establishes the limits and controls for the significant parameters that could potentially affect the safety and/or quality of the Spent Nuclear Fuel (SNF) packaged for processing, transport, and storage. The product specifications in this document cover the SNF packaged in Multi-Canister Overpacks to be transported throughout the SNF Project.

PAJUNEN, A.L.

2000-01-20T23:59:59.000Z

170

INVESTIGATIONS ON HYDRAULIC CEMENTS FROM SPENT OIL SHALE  

E-Print Network [OSTI]

CEMENTS FROM SPENT OIL SHALE P.K. Mehta and P. Persoff AprilCement Manufacture from Oil Shale, U.S. Patent 2,904,445,CEMENTS FROM SPENT OIL SHALE P, K, Mehta Civil Engineering

Mehta, P.K.

2012-01-01T23:59:59.000Z

171

Mechanical Design of Steel Tubing for Use in Black Liquor Recovery Boilers  

SciTech Connect (OSTI)

Finite element models were developed for thermal-mechanical analysis of black liquor recovery boiler floor tubes. Residual stresses in boiler floors due to various manufacturing processes were analyzed. The modeling results were verified by X-ray and neutron diffraction measurements at room temperature on as-manufactured tubes as well as tubes after service. The established finite element models were then used to evaluate stress conditions during boiler operation. Using these finite element models, a parametric response surface study was performed to investigate the influence of material properties of the clad layer on stresses in the floor tubes during various boiler operating conditions, which yielded a generalized solution of stresses in the composite tube floors. The results of the study are useful for identifying the mechanisms of cracking experienced by recovery boilers. Based on the results of the response surface study, a recommendation was made for more suitable materials in terms of the analyzed mechanical properties. Alternative materials and manufacturing processes are being considered to improve the resistance to cracking and the in-service life of composite tubes. To avoid numerous FE stress-strain analyses of composite tubes made of different material combinations, a response surface study was performed that considered two essential mechanical properties of the clad material - coefficient of thermal expansion and yield stress - as independent variables. The response surface study provided a generalized solution of stresses in the floor in terms of the two selected parameters.

Taljat, B.; Zacharaia, T.; Wang, X.; Kesier, J.; Swindeman, R.; Hubbard, C.

1999-05-26T23:59:59.000Z

172

Dynamic air deposited coatings for power and black liquor recovery boilers  

SciTech Connect (OSTI)

Dynamic Air Deposition (DyAir) is a novel coating method designed to protect the tubing of power and black liquor recovery boilers against corrosion attack at elevated temperatures. The method utilizes the energy of combustion of gaseous fuel and air to heat the powder material to a temperature just below its melting point and accelerate it over 600 m/s to form a coating. The Ni-Cr and Ni-Cr-Mo DyAir coatings revealed no gas permeability and extremely low oxygen content. Compared to the electric arc and HVOF-sprayed coatings, the DyAir coatings exhibited higher hardness and better crack resistance. During aging at 400 and 700 C the bond strength and crack resistance of the DyAir coatings increased dramatically due to intensive diffusion processes in absence of internal corrosion attack. The DyAir coatings revealed outstanding resistance to corrosion, such as sulfidation attack in presence of hydrochloric acid gas at 400 C, oxidation attack at 700 C and oxidation attack in presence of chlorine at 400 C.

Verstak, A.A.; Baranovski, V.E. [Advanced Surface Technologies Inc., Richmond, VA (United States)

1999-11-01T23:59:59.000Z

173

Black liquor combustion validated recovery boiler modeling: Final year report. Volume 5 (Appendix V)  

SciTech Connect (OSTI)

This project was initiated in October 1990, with the objective of developing and validating a new computer model of a recovery boiler furnace using a computational fluid dynamics (CFD) code specifically tailored to the requirements for solving recovery boiler flows, and using improved submodels for black liquor combustion based on continued laboratory fundamental studies. The key tasks to be accomplished were as follows: (1) Complete the development of enhanced furnace models that have the capability to accurately predict carryover, emissions behavior, dust concentrations, gas temperatures, and wall heat fluxes. (2) Validate the enhanced furnace models, so that users can have confidence in the predicted results. (3) Obtain fundamental information on aerosol formation, deposition, and hardening so as to develop the knowledge base needed to relate furnace model outputs to plugging and fouling in the convective sections of the boiler. (4) Facilitate the transfer of codes, black liquid submodels, and fundamental knowledge to the US kraft pulp industry. Volume 5 contains model validation simulations and comparison with data.

Grace, T.M.; Frederick, W.J.; Salcudean, M.; Wessel, R.A.

1998-08-01T23:59:59.000Z

174

Gasification behavior of carbon residue in bed solids of black liquor gasifier  

SciTech Connect (OSTI)

Steam gasification of carbon residue in bed solids of a low-temperature black liquor gasifier was studied using a thermogravimetric system at 3 bar. Complete gasification of the carbon residue, which remained unreactive at 600 C, was achieved in about 10 min as the temperature increased to 800 C. The rate of gasification and its temperature dependence were evaluated from the non-isothermal experiment results. Effects of particle size and adding H{sub 2} and CO to the gasification agent were also studied. The rate of steam gasification could be taken as zero order in carbon until 80% of carbon was gasified, and for the rest of the gasification process the rate appeared to be first order in carbon. The maximum rate of carbon conversion was around 0.003/s and the activation energy was estimated to be in the range of 230-300 kJ/mol. The particle size did not show significant effect on the rate of gasification. Hydrogen and carbon monoxide appeared to retard the onset of the gasification process. (author)

Preto, Fernando; Zhang, Xiaojie (Frank); Wang, Jinsheng [CANMET Energy Technology Centre, Natural Resources (Canada)

2008-07-15T23:59:59.000Z

175

The Suitable Geological Formations for Spent Fuel Disposal in Romania  

SciTech Connect (OSTI)

Using the experience in the field of advanced countries and formerly Romanian program data, ANDRAD, the agency responsible for the disposal of radioactive wastes, started the program for spent fuel disposal in deep geological formations with a documentary analysis at the national scale. The potential geological formations properly characterized elsewhere in the world: salt, clay, volcanic tuff, granite and crystalline rocks,. are all present in Romania. Using general or specific selection criteria, we presently consider the following two areas for candidate geological formations: 1. Clay formations in two areas in the western part of Romania: (1) The Pannonian basin Socodor - Zarand, where the clay formation is 3000 m thick, with many bentonitic strata and undisturbed structure, and (2) The Eocene Red Clay on the Somes River, extending 1200 m below the surface. They both need a large investigation program in order to establish and select the required homogeneous, dry and undisturbed zones at a suitable depth. 2. Old platform green schist formations, low metamorphosed, quartz and feldspar rich rocks, in the Central Dobrogea structural unit, not far from Cernavoda NPP (30 km average distance), 3000 m thick and including many homogeneous, fine granular, undisturbed, up to 300 m thick layers. (authors)

Marunteanu, C. [Bucharest Univ. (Romania); Ionita, G. [ANDRAD, Bucharest (Romania); Durdun, I. [S.C. GEOTEC S.A., Bucharest (Romania)

2007-07-01T23:59:59.000Z

176

EIS-0015: U.S. Spent Fuel Policy  

Broader source: Energy.gov [DOE]

Subsumed DOE/EIS-0040 and DOE/EIS-0041. The Savannah River Laboratory prepared this EIS to analyze the impacts of implementing or not implementing the policy for interim storage of spent power reactor fuel. This Final EIS is a compilation of three Draft EISs and one Supplemental Draft EIS: DOE/EIS-0015-D, Storage of U.S. Spent Power Reactor Fuel; DOE/EIS-0015-DS, Storage of U.S. Spent Power Reactor Fuel - Supplement; DOE/EIS-0040-D, Storage of Foreign Spent Power Reactor Fuel; and DOE/EIS-0041-D, Charge for Spent Fuel Storage.

177

Spent Sealed Sources Management in Switzerland - 12011  

SciTech Connect (OSTI)

Information is provided about the international recommendations for the safe management of disused and spent sealed radioactive sources wherein the return to the supplier or manufacturer is encouraged for large radioactive sources. The legal situation in Switzerland is described mentioning the demand of minimization of radioactive waste as well as the situation with respect to the interim storage facility at the Paul Scherrer Institute (PSI). Based on this information and on the market situation with a shortage of some medical radionuclides the management of spent sealed sources is provided. The sources are sorted according to their activity in relation to the nuclide-specific A2-value and either recycled as in the case of high active sources or conditioned as in the case for sources with lower activity. The results are presented as comparison between recycled and conditioned activity for three selected nuclides, i.e. Cs-137, Co-60 and Am-241. (author)

Beer, H.F. [Paul Scherrer Institute, CH-5232 Villigen (Switzerland)

2012-07-01T23:59:59.000Z

178

Spent Fuel Working Group Report. Volume 1  

SciTech Connect (OSTI)

The Department of Energy is storing large amounts of spent nuclear fuel and other reactor irradiated nuclear materials (herein referred to as RINM). In the past, the Department reprocessed RINM to recover plutonium, tritium, and other isotopes. However, the Department has ceased or is phasing out reprocessing operations. As a consequence, Department facilities designed, constructed, and operated to store RINM for relatively short periods of time now store RINM, pending decisions on the disposition of these materials. The extended use of the facilities, combined with their known degradation and that of their stored materials, has led to uncertainties about safety. To ensure that extended storage is safe (i.e., that protection exists for workers, the public, and the environment), the conditions of these storage facilities had to be assessed. The compelling need for such an assessment led to the Secretary`s initiative on spent fuel, which is the subject of this report. This report comprises three volumes: Volume I; Summary Results of the Spent Fuel Working Group Evaluation; Volume II, Working Group Assessment Team Reports and Protocol; Volume III; Operating Contractor Site Team Reports. This volume presents the overall results of the Working Group`s Evaluation. The group assessed 66 facilities spread across 11 sites. It identified: (1) facilities that should be considered for priority attention. (2) programmatic issues to be considered in decision making about interim storage plans and (3) specific vulnerabilities for some of these facilities.

O`Toole, T.

1993-11-01T23:59:59.000Z

179

Alkali salt ash formation during black liquor combustion at kraft recovery boilers  

SciTech Connect (OSTI)

Recovery boiler is an essential part of paper pulping process, where waste sludge called black liquor is burned for chemical recovery and energy production. This study was carried out at an operating industrial recovery boiler in Finland. Measurement of aerosol particles was carried out at bullnose level of furnace, at boiler exit, and at outlet of electrostatic precipitator (ESP). Aerosol mass size distributions in size range 0.02--50 {micro}m were measured with Berner type low pressure impactor (BLPI) operated with precyclone. BLPI samples were further analyzed with ion chromatography for water soluble Na, K, SO{sub 4}, and Cl. Particle morphology was studied with scanning electron microscopy (SEM). Phase composition of crystalline salts was measured with X-ray diffraction (XRD). Particles larger than 1 {micro}m were analyzed with computer controlled scanning electron microscopy (CCSEM) to derive particle composition classes. At ESP inlet mass size distribution was bimodal with a major mode at about 1.2 {micro}m and a minor mode at about 5 {micro}m (aerodynamic diameter). At ESP outlet the mass size distribution showed only one peak at about 1.2 {micro}m. Both submicron and supermicron particles were agglomerates formed from 0.3 to 0.5 {micro}m spherical primary particles. XRD analyses indicated that particles were crystalline with two phases of Na{sub 2}SO{sub 4} (thenardite and sodium sulphate) and K{sub 3}Na(SO{sub 4}){sub 2}. CCSEM results of individual particles larger than 1 {micro}m showed that 79 to 88 volume percent of particles contained mainly Na and S, 7 to 10 volume percent Na, K, and S with minor amount of particles containing Na, S, and Ca.

Mikkanen, P. Kauppinen, E.I.; Pyykoenen, J.; Jokiniemi, J.K. [VTT (Finland); Maekinen, M. [Finnish Meterological Inst., Helsinki (Finland)

1996-12-31T23:59:59.000Z

180

Red Pepper Sauce  

E-Print Network [OSTI]

... chopped 2 cloves garlic, minced 1/4 cup water 1/2 Tbs. white wine vinegar 1/8 tsp. crushed red pepper 1/8 tsp. white pepper dash or two Tabasco sauce 1/2 to...

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Pyrometric temperature measurement method and apparatus for measuring particle temperatures in hot furnaces: Application to reacting black liquor  

SciTech Connect (OSTI)

A specialized two-color pyrometric method has been developed for the measurement of particle surface temperatures in hot, radiating environments. In this work, the method has been applied to the measurement of surface temperatures of single reacting black liquor char particles in an electrically heated muffle furnace. Black liquor was introduced into the hot furnace as wet droplets. After drying, the resulted particles were processed in different atmospheres corresponding to combustion, pyrolysis, and gasification at furnace temperatures of 700{endash}900{degree}C. The pyrometric measurement is performed using two silicon photodiode detectors and 10 nm bandpass filters centered at 650 and 1050 nm. Thermal radiation is transferred using an uncooled fiberoptic probe brought into the vicinity of the char particle. The key features of the pyrometric apparatus and analysis method are: (1) Single particle temperature is resolved temporally at high speed. (2) The thermal radiation originating from the furnace and reflected by the particle is accounted for in the measurement of the surface temperature. (3) Particle temperatures above or below the furnace temperature can be measured without the need of a cooled background assisting the measurement in the hot furnace. To accomplish this, a minimum particle size is needed that is a function of the temperature difference between the particle and furnace. Particles cooler than the furnace can be measured if their diameter is more than 0.7 mm. Surface temperatures of 300{endash}400{degree}C above the furnace temperature were measured during combustion of black liquor char particles in air. In atmospheres corresponding to gasification, endothermic reactions occurred, and char temperature remained typically 40{degree} below the furnace temperature. {copyright} {ital 1996 American Institute of Physics.}

Stenberg, J. [Tampere University of Technology, P.O. Box 692, Tampere SF-33101 (Finland)] [Tampere University of Technology, P.O. Box 692, Tampere SF-33101 (Finland); Frederick, W.J. [Oregon State University, Gleeson 103, Corvallis, Oregon 97331 (United States)] [Oregon State University, Gleeson 103, Corvallis, Oregon 97331 (United States); Bostroem, S. [Abo Akademi University, Lemminkaeisenkatu 14-18 B, Turku SF-20520 (Finland)] [Abo Akademi University, Lemminkaeisenkatu 14-18 B, Turku SF-20520 (Finland); Hernberg, R. [Tampere University of Technology, P.O. Box 692, Tampere SF-33101 (Finland)] [Tampere University of Technology, P.O. Box 692, Tampere SF-33101 (Finland); Hupa, M. [Abo Akademi University, Lemminkaeisenkatu 14-18 B, Turku SF-20520 (Finland)] [Abo Akademi University, Lemminkaeisenkatu 14-18 B, Turku SF-20520 (Finland)

1996-05-01T23:59:59.000Z

182

Causes and solutions for cracking of coextruded and weld overlay floor tubes in black liquor recovery boilers  

SciTech Connect (OSTI)

Cracking of coextruded, black liquor recovery boiler floor tubes is both a safety and an economic issue to mill operators. In an effort to determine the cause of the cracking and to identify a solution, extensive studies, described in this and three accompanying papers, are being conducted. In this paper, results of studies to characterize both the cracking and the chemical and thermal environment are reported. Based on the results described in this series of papers, a possible mechanism is presented and means to lessen the likelihood of cracking or to totally avoid cracking of floor tubes are offered.

Keiser, J.R.; Taljat, B.; Wang, X.L. [and others

1998-09-01T23:59:59.000Z

183

Electrolysis of weak black liquor: Part II. Effect of process parameters on the energy efficiency of the electrolytic cell  

SciTech Connect (OSTI)

A laboratory study of the effect of eight process parameters on the performance of the electrolytic cell when electrolyzing weak black liquor (WBL) showed that current density and temperature are critical to the operation. These two variables showed an interaction effect upon the operation of the cell. The addition of sodium sulfate to the WBL was beneficial to the energy efficiency. No chlorine gas was produced when electrolyzing WBL containing sodium chloride within the pH range of 5.4 to 13.

Cloutier, J.N.; Azarniouch, M.K.; Callender, D.

1994-12-31T23:59:59.000Z

184

Study of soluble scale fouling control in high solids black liquor concentrators. Progress report, quarter 5 (October 1, 1999 - December 31, 1999)  

SciTech Connect (OSTI)

During this quarter, work has finally resumed on the black liquor solubility experiments, but no new data have been generated. The crystallization experiments with inorganic model solutions have been completed, and crystallization experiments with kraft black liquor have been started. The Annular Test Cell apparatus is now fully operational, while construction of the falling film evaporator pilot plant is nearly complete. Startup of this unit is planned for late in Quarter 6. In the CFD model development work, the relaxation of simplifying assumptions in the falling film model have been completed, and expressions were developed to estimate film velocity/film Reynolds number relations. Also, thin film data taken for a range of conventional fluids were compared to predictions using selected methods, and attempts were initiated to extrapolate to approximate black liquor evaporator conditions.

W.J. Frederick; F. Chen; G. Hsieh; S. Lien; R.W. Murphy; R.W. Rousseau; W. Schmidl

2000-01-01T23:59:59.000Z

185

Surrogate Spent Nuclear Fuel Vibration Integrity Investigation  

SciTech Connect (OSTI)

Transportation packages for spent nuclear fuel (SNF) must meet safety requirements under normal and accident conditions as specified by federal regulations. During transportation, SNF experiences unique conditions and challenges to cladding integrity due to the vibrational and impact loading encountered during road or rail shipment. ORNL has been developing testing capabilities that can be used to improve our understanding of the impacts of vibration loading on SNF integrity, especially for high burn-up SNF in normal transportation operation conditions. This information can be used to meet nuclear industry and U.S. Nuclear Regulatory Commission needs in the area of safety of SNF storage and transportation operations.

Wang, Jy-An John [ORNL; Wang, Hong [ORNL; Bevard, Bruce Balkcom [ORNL; Howard, Rob L [ORNL

2014-01-01T23:59:59.000Z

186

Spent fuel management fee methodology and computer code user's manual.  

SciTech Connect (OSTI)

The methodology and computer model described here were developed to analyze the cash flows for the federal government taking title to and managing spent nuclear fuel. The methodology has been used by the US Department of Energy (DOE) to estimate the spent fuel disposal fee that will provide full cost recovery. Although the methodology was designed to analyze interim storage followed by spent fuel disposal, it could be used to calculate a fee for reprocessing spent fuel and disposing of the waste. The methodology consists of two phases. The first phase estimates government expenditures for spent fuel management. The second phase determines the fees that will result in revenues such that the government attains full cost recovery assuming various revenue collection philosophies. These two phases are discussed in detail in subsequent sections of this report. Each of the two phases constitute a computer module, called SPADE (SPent fuel Analysis and Disposal Economics) and FEAN (FEe ANalysis), respectively.

Engel, R.L.; White, M.K.

1982-01-01T23:59:59.000Z

187

Investigation of the condition of spent-fuel pool components  

SciTech Connect (OSTI)

It is currently projected that spent nuclear fuel, which is discharged from the reactor and then stored in water pools, may remain in those pools for several decades. Other studies have addressed the expected integrity of the spent fuel during extended water storage; this study assesses the integrity of metallic spent fuel pool components. Results from metallurgical examinations of specimens taken from stainless steel and aluminum components exposed in spent fuel pools are presented. Licensee Event Reports (LERs) relating to problems with spent fuel components were assessed and are summarized to define the types of operational problems that have occurred. The major conclusions of this study are: aluminum and stainless steel spent fuel pool components have a good history of performance in both deionized and borated water pools. Although some operational problems involving pool components have occurred, these problems have had minimal impacts.

Kustas, F.M.; Bates, S.O.; Opitz, B.E.; Johnson, A.B. Jr.; Perez, J.M. Jr.; Farnsworth, R.K.

1981-09-01T23:59:59.000Z

188

Controlling emissions from a black liquor fluidized bed evaporator (Copeland reactor) using a regenerative thermal oxidizer and a prefilter  

SciTech Connect (OSTI)

This paper reports on an intriguing pilot project developed to control air emissions from a pulp mill. Testing is complete, and the results show favorable emissions reductions. Stone Container Corporation, REECO, NCASI, the Ohio DEP, and the US EPA, have all worked together and approved the installation of control equipment, for VOC and HAP emissions under Presumptive MACT, setting the standard for the Copeland Reactor process in a semi chem pulp mill. The equipment, once operational, will reduce VOC and CO emissions by greater than 90%. This installation will be done at one seventh the cost of the significant process modifications required to accomplish the same emission reduction. In addition, increased process operating efficiency will be achieved with the use of an energy recovery system. The process is a black liquor fluidized bed boiler, which is used to generate sodium carbonate from the black liquor. The vapor emissions were high in VOCs, CO and particulate. After much study and testing, a wet electrostatic precipitator was chosen as the filter system for particulate control, followed by a regenerative thermal oxidizer for VOC and HAP control, finally an air-to-air heat exchanger is being used to preheat the combustion air entering the process.

Grzanka, R.

1997-12-31T23:59:59.000Z

189

Black liquor combustion validated recovery boiler modeling: Final year report. Volume 2 (Appendices I, section 5 and II, section 1)  

SciTech Connect (OSTI)

This project was initiated in October 1990, with the objective of developing and validating a new computer model of a recovery boiler furnace using a computational fluid dynamics (CFD) code specifically tailored to the requirements for solving recovery boiler flows, and using improved submodels for black liquor combustion based on continued laboratory fundamental studies. The key tasks to be accomplished were as follows: (1) Complete the development of enhanced furnace models that have the capability to accurately predict carryover, emissions behavior, dust concentrations, gas temperatures, and wall heat fluxes. (2) Validate the enhanced furnace models, so that users can have confidence in the predicted results. (3) Obtain fundamental information on aerosol formation, deposition, and hardening so as to develop the knowledge base needed to relate furnace model outputs to plugging and fouling in the convective sections of the boiler. (4) Facilitate the transfer of codes, black liquid submodels, and fundamental knowledge to the US kraft pulp industry. Volume 2 contains the last section of Appendix I, Radiative heat transfer in kraft recovery boilers, and the first section of Appendix II, The effect of temperature and residence time on the distribution of carbon, sulfur, and nitrogen between gaseous and condensed phase products from low temperature pyrolysis of kraft black liquor.

Grace, T.M.; Frederick, W.J.; Salcudean, M.; Wessel, R.A.

1998-08-01T23:59:59.000Z

190

Spent nuclear fuel project - criteria document spent nuclear fuel final safety analysis report  

SciTech Connect (OSTI)

The criteria document provides the criteria and planning guidance for developing the Spent Nuclear Fuel (SNF) Final Safety Analysis Report (FSAR). This FSAR will support the US Department of Energy, Richland Operations Office decision to authorize the procurement, installation, installation acceptance testing, startup, and operation of the SNF Project facilities (K Basins, Cold Vacuum Drying Facility, and Canister Storage Building).

MORGAN, R.G.

1999-02-23T23:59:59.000Z

191

Evaluation of Options for Permanent Geologic Disposal of Spent...  

Broader source: Energy.gov (indexed) [DOE]

policy decisions regarding strategies for the management and permanent disposal of spent nuclear fuel (SNF) and high-level radioactive waste (HLW) in the United States requiring...

192

Transportation capabilities study of DOE-owned spent nuclear fuel  

SciTech Connect (OSTI)

This study evaluates current capabilities for transporting spent nuclear fuel owned by the US Department of Energy. Currently licensed irradiated fuel shipping packages that have the potential for shipping the spent nuclear fuel are identified and then matched against the various spent nuclear fuel types. Also included are the results of a limited investigation into other certified packages and new packages currently under development. This study is intended to support top-level planning for the disposition of the Department of Energy`s spent nuclear fuel inventory.

Clark, G.L.; Johnson, R.A.; Smith, R.W. [Packaging Technology, Inc., Tacoma, WA (United States); Abbott, D.G.; Tyacke, M.J. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

1994-10-01T23:59:59.000Z

193

Spent Nuclear Fuel project integrated safety management plan  

SciTech Connect (OSTI)

This document is being revised in its entirety and the document title is being revised to ``Spent Nuclear Fuel Project Integrated Safety Management Plan.

Daschke, K.D.

1996-09-17T23:59:59.000Z

194

President Reagan Calls for a National Spent Fuel Storage Facility...  

National Nuclear Security Administration (NNSA)

Spent Fuel Storage Facility Washington, DC The Reagan Administration announces a nuclear energy policy that anticipates the establishment of a facility for the storage of...

195

US Spent (Used) Fuel Status, Management and Likely Directions- 12522  

SciTech Connect (OSTI)

As of 2010, the US has accumulated 65,200 MTU (42,300 MTU of PWR's; 23,000 MTU of BWR's) of spent (irradiated or used) fuel from 104 operating commercial nuclear power plants situated at 65 sites in 31 States and from previously shutdown commercial nuclear power plants. Further, the Department of Energy (DOE) has responsibility for an additional 2458 MTU of DOE-owned defense and non defense spent fuel from naval nuclear power reactors, various non-commercial test reactors and reactor demonstrations. The US has no centralized large spent fuel storage facility for either commercial spent fuel or DOE-owned spent fuel. The 65,200 MTU of US spent fuel is being safely stored by US utilities at numerous reactor sites in (wet) pools or (dry) metal or concrete casks. As of November 2010, the US had 63 'independent spent fuel storage installations' (or ISFSI's) licensed by the US Nuclear Regulatory Commission located at 57 sites in 33 states. Over 1400 casks loaded with spent fuel for dry storage are at these licensed ISFSI's; 47 sites are located at commercial reactor sites and 10 are located 'away' from a reactor (AFR's) site. DOE's small fraction of a 2458 MTU spent fuel inventory, which is not commercial spent fuel, is with the exception of 2 MTU, being stored at 4 sites in 4 States. The decades old US policy of a 'once through' fuel cycle with no recycle of spent fuel was set into a state of 'mass confusion or disruption' when the new US President Obama's administration started in early 2010 stopping the only US geologic disposal repository at the Yucca Mountain site in the State of Nevada from being developed and licensed. The practical result is that US nuclear power plant operators will have to continue to be responsible for managing and storing their own spent fuel for an indefinite period of time at many different sites in order to continue to generate electricity because there is no current US government plan, schedule or policy for taking possession of accumulated spent fuel from the utilities. There are technical solutions for continuing the safe storage of spent fuel for 100 years or more and these solutions will be implemented by the US utilities that need to keep their nuclear power plants operating while the unknown political events are played out to establish future US policy decisions that can remain in place long enough regarding accumulated spent fuel inventories to implement any new US spent fuel centralized storage or disposition policy by the US government. (author)

Jardine, Leslie J. [L. J. Jardine Services, Consultant, Dublin CA, 94568 (United States)

2012-07-01T23:59:59.000Z

196

Pyroprocess for processing spent nuclear fuel  

DOE Patents [OSTI]

This is a pyroprocess for processing spent nuclear fuel. The spent nuclear fuel is chopped into pieces and placed in a basket which is lowered in to a liquid salt solution. The salt is rich in ZrF.sub.4 and containing alkali or alkaline earth fluorides, and in particular, the salt chosen was LiF-50 mol % ZrF.sub.4 with a eutectic melting point of 500.degree. C. Prior to lowering the basket, the salt is heated to a temperature of between 550.degree. C. and 700.degree. C. in order to obtain a molten solution. After dissolution the oxides of U, Th, rare earth and other like oxides, the salt bath solution is subject to hydro-fluorination to remove the oxygen and then to a fluorination step to remove U as gaseous UF.sub.6. In addition, after dissolution, the basket contains PuO.sub.2 and undissolved parts of the fuel rods, and the basket and its contents are processed to remove the Pu.

Miller, William E. (Naperville, IL); Tomczuk, Zygmunt (Lockport, IL)

2002-01-01T23:59:59.000Z

197

Fundamental study of black liquor gasification kinetics using a pressurized entrained-flow reactor (PEFR). Quarterly progress report for the period July 1999 to September 1999  

SciTech Connect (OSTI)

The goal of the program is to identify the optimal operating window for black liquor gasification. The goals during this year are to prepare the PEFR for operation, conduct a series of preliminary screening tests to bracket BLG operating conditions, and develop a process model that can guide identification of the optimal operating window.

NONE

1999-10-29T23:59:59.000Z

198

High-solids black liquor firing in pulp and paper industry Kraft recovery boilers. Final report, Phase 1, Volume 1: Executive summary  

SciTech Connect (OSTI)

This project is a multiple-phase effort to develop technologies to improve high-solids black liquor firing in pulp mill recovery boilers. The objectives are to develop a preliminary design of a recovery furnace simulator; evaluate the economics of high-solids; and delineate a project concept for evaluating candidate technologies to improve chemical recovery.

Southards, W.T.; Clement, J.L.; McIlroy, R.A.; Tharp, M.R.; Verrill, C.L.; Wessell, R.A.

1995-11-01T23:59:59.000Z

199

Testing of the CANDU Spent Fuel Storage Basket Package  

SciTech Connect (OSTI)

The paper described the results of testing for a CANDU Spent Fuel Storage Basket Package Prototype intended to be used for transport and storage of the CANDU spent fuel bundles within NPP CANDU Cernavoda, Romania. The results obtained proved that the objectives of those tests were achieved

Vieru, G.

2002-02-28T23:59:59.000Z

200

Breeder Spent Fuel Handling Program multipurpose cask design basis document  

SciTech Connect (OSTI)

The Breeder Spent Fuel Handling (BSFH) Program multipurpose cask Design Basis Document defines the performance requirements essential to the development of a legal weight truck cask to transport FFTF spent fuel from reactor to a reprocessing facility and the resultant High Level Waste (HLW) to a repository. 1 ref.

Duckett, A.J.; Sorenson, K.B.

1985-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Ayrshire Red Squirrel Group Squirrelpox  

E-Print Network [OSTI]

Ayrshire Red Squirrel Group SSG Report 1st March 2012 Squirrelpox Sero-positive grey squirrels. Concerns are also rising that there may be outbreaks of pox in red squirrel populations which have gone

202

Characterization plan for Hanford spent nuclear fuel  

SciTech Connect (OSTI)

Reprocessing of spent nuclear fuel (SNF) at the Hanford Site Plutonium-Uranium Extraction Plant (PUREX) was terminated in 1972. Since that time a significant quantity of N Reactor and Single-Pass Reactor SNF has been stored in the 100 Area K-East (KE) and K-West (KW) reactor basins. Approximately 80% of all US Department of Energy (DOE)-owned SNF resides at Hanford, the largest portion of which is in the water-filled KE and KW reactor basins. The basins were not designed for long-term storage of the SNF and it has become a priority to move the SNF to a more suitable location. As part of the project plan, SNF inventories will be chemically and physically characterized to provide information that will be used to resolve safety and technical issues for development of an environmentally benign and efficient extended interim storage and final disposition strategy for this defense production-reactor SNF.

Abrefah, J.; Thornton, T.A.; Thomas, L.E.; Berting, F.M.; Marschman, S.C.

1994-12-01T23:59:59.000Z

203

Arrival condition of spent fuel after storage, handling, and transportation  

SciTech Connect (OSTI)

This report presents the results of a study conducted to determine the probable arrival condition of spent light-water reactor (LWR) fuel after handling and interim storage in spent fuel storage pools and subsequent handling and accident-free transport operations under normal or slightly abnormal conditions. The objective of this study was to provide information on the expected condition of spent LWR fuel upon arrival at interim storage or fuel reprocessing facilities or at disposal facilities if the fuel is declared a waste. Results of a literature survey and data evaluation effort are discussed. Preliminary threshold limits for storing, handling, and transporting unconsolidated spent LWR fuel are presented. The difficulty in trying to anticipate the amount of corrosion products (crud) that may be on spent fuel in future shipments is also discussed, and potential areas for future work are listed. 95 references, 3 figures, 17 tables.

Bailey, W.J.; Pankaskie, P.J.; Langstaff, D.C.; Gilbert, E.R.; Rising, K.H.; Schreiber, R.E.

1982-11-01T23:59:59.000Z

204

Case histories of West Valley spent fuel shipments: Final report  

SciTech Connect (OSTI)

In 1983, NRC/FC initiated a study on institutional issues related to spent fuel shipments originating at the former spent fuel processing facility in West Valley, New York. FC staff viewed the shipment campaigns as a one-time opportunity to document the institutional issues that may arise with a substantial increase in spent fuel shipping activity. NRC subsequently contracted with the Aerospace Corporation for the West Valley Study. This report contains a detailed description of the events which took place prior to and during the spent fuel shipments. The report also contains a discussion of the shipment issues that arose, and presents general findings. Most of the institutional issues discussed in the report do not fall under NRC's transportation authority. The case histories provide a reference to agencies and other institutions that may be involved in future spent fuel shipping campaigns. 130 refs., 7 figs., 19 tabs.

Not Available

1987-01-01T23:59:59.000Z

205

Black Liquor Combustion Validated Recovery Boiler Modeling, Final Year Report, Volume 3: Appendix II, Sections 2 & 3 and Appendix III  

SciTech Connect (OSTI)

This project was initiated in October 1990 with the objective of developing and validating a new computer model of a recovery boiler furnace using a computational fluid dynamics (CFD) code specifically tailored to the requirements for solving recovery boiler flows, and using improved submodels for black liquor combustion based on continued laboratory fundamental studies. Many of these objectives were accomplished at the end of the first five years and documented in a comprehensive report on that work (DOE/CE/40936-T3, 1996). A critical review of recovery boiler modeling, carried out in 1995, concluded that further enhancements of the model were needed to make reliable predictions of key output variables. In addition, there was a need for sufficient understanding of fouling and plugging processes to allow model outputs to be interpreted in terms of the effect on plugging and fouling. As a result, the project was restructured and reinitiated at the end of October 1995, and was completed in June 1997. The entire project is now complete and this report summarizes all of the work done on the project since it was restructured. The key tasks to be accomplished under the restructured project were to (1) Complete the development of enhanced furnace models that have the capability to accurately predict carryover, emissions behavior, dust concentrations, gas temperatures, and wall heat fluxes; (2) Validate the enhanced furnace models, so that users can have confidence in the results; (3) Obtain fundamental information on aerosol formation, deposition, and hardening so as to develop the knowledge base needed to relate furnace model outputs to plugging and fouling in the convective sections of the boiler; and (4) Facilitate the transfer of codes, black liquor submodels, and fundamental knowledge to the U.S. kraft pulp industry.

T.M. Grace, W.J. Frederick, M. Salcudean, R.A. Wessel

1998-08-01T23:59:59.000Z

206

The Impacts of Dry-Storage Canister Designs on Spent Nuclear...  

Office of Environmental Management (EM)

Canister Designs on Spent Nuclear Fuel Handling, Storage, Transportation, and Disposal in the U.S. The Impacts of Dry-Storage Canister Designs on Spent Nuclear Fuel...

207

Red-black Tree Jingjing Xia  

E-Print Network [OSTI]

Advanced Algorithm Design Red-black Tree Jingjing Xia #12;Red-Black Tree A red-black tree is a binary search tree, and each node contains one extra field: its color, it can be either black or red of the binary search tree. If a binary search tree satisfies all the following red-black properties, it is a red

Chen, Yangjun

208

INVESTIGATIONS ON HYDRAULIC CEMENTS FROM SPENT OIL SHALE  

SciTech Connect (OSTI)

A process for making hydraulic cements from spent oil shale is described in this paper. Inexpensive cement is needed to grout abandoned in-situ retorts of spent shale for subsidence control, mitigation of leaching, and strengthening the retorted mass in order to recover oil from adjacent pillars of raw shale. A hydraulic cement was produced by heating a 1:1 mixture of Lurgi spent shale and CaCO{sub 3} at 1000 C for one hour. This cement would be less expensive than ordinary portland cement and is expected to fulfill the above requirements.

Mehta, P.K.; Persoff, P.

1980-04-01T23:59:59.000Z

209

INVESTIGATIONS ON HYDRAULIC CEMENTS FROM SPENT OIL SHALE  

E-Print Network [OSTI]

20 to 40% of the oil shale, and explosively rubblizing andCEMENTS FROM SPENT OIL SHALE P.K. Mehta and P. Persoff AprilCement Manufacture from Oil Shale, U.S. Patent 2,904,445,

Mehta, P.K.

2012-01-01T23:59:59.000Z

210

Application of ALARA principles to shipment of spent nuclear fuel  

SciTech Connect (OSTI)

The public exposure from spent fuel shipment is very low. In view of this low exposure and the perfect safety record for spent fuel shipment, existing systems can be considered satisfactory. On the other hand, occupational exposure reduction merits consideration and technology improvement to decrease dose should concentrate on this exposure. Practices that affect the age of spent fuel in shipment and the number of times the fuel must be shipped prior to disposal have the largest impact. A policy to encourage a 5-year spent fuel cooling period prior to shipment coupled with appropriate cask redesign to accommodate larger loads would be consistent with ALARA and economic principles. And finally, bypassing high population density areas will not in general reduce shipment dose.

Greenborg, J.; Brackenbush, L.W.; Murphy, D.W. Burnett, R.A.; Lewis, J.R.

1980-05-01T23:59:59.000Z

211

Inventory of LWR spent nuclear fuel in the 324 Building  

SciTech Connect (OSTI)

This document contains the results of calculations to estimate the decay heat, neutron source term, photon source term, and radioactive inventory of light-water-reactor spent nuclear fuel in the 324 Building at Pacific Northwest National Laboratory.

Jenquin, U.P.

1996-09-01T23:59:59.000Z

212

Risk and Responsibility Sharing in Nuclear Spent Fuel Management  

E-Print Network [OSTI]

With the Nuclear Waste Policy Act of 1982, the responsibility of American utilities in the long-term management of spent nuclear fuel was limited to the payment of a fee. This narrow involvement did not result in faster ...

De Roo, Guillaume

213

www.vopen.net 1994 Young Mark Ewing Red Hat Red H  

E-Print Network [OSTI]

www.vopen.net Linux --- 1994 Young Mark Ewing Red Hat Red H at Linux Linux Red Hat Linux Red Hat Linux Red Hat Linux MandrakeSOT BestConnectivaAbit KondaraRed Hat Linux 2001 4 16 Red Hat Red Hat Linux 7.1 Red Hat Linux 1 1.1 1 Linux 2.4.2 2 Xfree86 4.0.3 3 4 Big5 5 CPU CPU 4

Li, Tiejun

214

Extraction of uranium from spent fuels using liquefied gases  

SciTech Connect (OSTI)

For reprocessing of spent nuclear fuels, a novel method to extract actinides from spent fuel using highly compressed gases, nitrogen dioxide and carbon dioxide was proposed. As a fundamental study, the nitrate conversion with liquefied nitrogen dioxide and the nitrate extraction with supercritical carbon dioxide were demonstrated by using uranium dioxide powder, uranyl nitrate and tri-n-butylphosphate complex in the present study. (authors)

Sawada, Kayo; Hirabayashi, Daisuke; Enokida, Youichi [EcoTopia Science Institute, Nagoya University, Furo-cho, Chikusa-ku, Nagoya, 464-8603 (Japan)

2007-07-01T23:59:59.000Z

215

Spent nuclear fuel discharges from U.S. reactors 1994  

SciTech Connect (OSTI)

Spent Nuclear Fuel Discharges from US Reactors 1994 provides current statistical data on fuel assemblies irradiated at commercial nuclear reactors operating in the US. This year`s report provides data on the current inventories and storage capacities at these reactors. Detailed statistics on the data are presented in four chapters that highlight 1994 spent fuel discharges, storage capacities and inventories, canister and nonfuel component data, and assembly characteristics. Five appendices, a glossary, and bibliography are also included. 10 figs., 34 tabs.

NONE

1996-02-01T23:59:59.000Z

216

Detection of estrogen- and dioxin-like activity in pulp and paper mill black liquor and effluent using in vitro bioassays  

SciTech Connect (OSTI)

Pulp and paper mill effluent contains a complex mixture of compounds which adversely affect fish physiologically and at the population level. These effects include compromised reproductive fitness and the induction of mixed-function oxidase activities; two classic responses mediated by the estrogen and/or Ah receptor. In vitro recombinant receptor/reporter gene assays were used to examine pulp and paper mill black liquor and effluent for estrogenic, dioxin-like and antiestrogenic activities. Using MCF7 cells transiently transfected with a Gal4-estrogen receptor chimeric construct (Gal4-HEGO) and a Gal4-regulated luciferase reporter gene (17m5-G-Luc), it was estimated that black liquor contains 4 {+-} 2 ppb ``estrogen equivalents``, while negligible estrogenic activity was observed in a methanol-extracted pulp and paper mill effluent fraction (MF). A dioxin response element (DRE)-regulated luciferase reporter gene (pGudLucl.1) transiently transfected into Hepalclc7 wild type cells exhibited a dose-dependent increase in luciferase activity following treatment with 2,3,7,8-tetrachlorodibenzo-p-dioxin (TCDO), black liquor and MF. Based on the dose response curves, black liquor and MF contain 10 {+-} 4 ppb and 20 {+-} 6 ppt ``TCDD equivalents``, respectively. Moreover, MF exhibited significant AhR-mediated antiestrogenic activity. These results demonstrate the utility of these bioassays and suggest that the effects observed in fish exposed to pulp and paper mill effluent may be due to unidentified ER and AhR ligands not detected by conventional chemical analysis due to the lack of appropriate chemical standards.

Zacharewski, T.; Berhane, K.; Gillesby, B.; Burnison, K. [Univ. of Western Ontario, London, Ontario (Canada). Dept. of Pharmacology and Toxicology; [National Water Research Inst., Burlington, Ontario (Canada). Aquatic Ecosystem Conservation Branch

1995-12-31T23:59:59.000Z

217

Reactor-specific spent fuel discharge projections: 1985 to 2020  

SciTech Connect (OSTI)

The creation of four spent-fuel data bases that contain information on the projected amounts of spent fuel to be discharged from US commercial nuclear reactors through the year 2020 is described. The data bases contain detailed spent-fuel information from existing, planned, and projected pressurized water reactors (PWR) and boiling water reactors (BWR). The projections are based on individual reactor information supplied by the US reactor owners. The basic information is adjusted to conform to Energy Information Agency (EIA) forecasts for nuclear installed capacity, generation, and spent fuel discharged. The EIA cases considered are: (1) No New Orders with Extended Burnup, (2) No New Orders with Constant Burnup, (3) Middle Case with Extended Burnup, and (4) Middle Case with Constant Burnup. Detailed, by-reactor tables are provided for annual discharged amounts of spent fuel, for storage requirements assuming maximum-at-reactor storage, and for storage requirements assuming maximum-at-reactor plus intra-utility transshipment of spent fuel.

Heeb, C.M.; Libby, R.A.; Walling, R.C.; Purcell, W.L.

1986-09-01T23:59:59.000Z

218

West Valley facility spent fuel handling, storage, and shipping experience  

SciTech Connect (OSTI)

The result of a study on handling and shipping experience with spent fuel are described in this report. The study was performed by Pacific Northwest Laboratory (PNL) and was jointly sponsored by the US Department of Energy (DOE) and the Electric Power Research Institute (EPRI). The purpose of the study was to document the experience with handling and shipping of relatively old light-water reactor (LWR) fuel that has been in pool storage at the West Valley facility, which is at the Western New York Nuclear Service Center at West Valley, New York and operated by DOE. A subject of particular interest in the study was the behavior of corrosion product deposits (i.e., crud) deposits on spent LWR fuel after long-term pool storage; some evidence of crud loosening has been observed with fuel that was stored for extended periods at the West Valley facility and at other sites. Conclusions associated with the experience to date with old spent fuel that has been stored at the West Valley facility are presented. The conclusions are drawn from these subject areas: a general overview of the West Valley experience, handling of spent fuel, storing of spent fuel, rod consolidation, shipping of spent fuel, crud loosening, and visual inspection. A list of recommendations is provided. 61 refs., 4 figs., 5 tabs.

Bailey, W.J.

1990-11-01T23:59:59.000Z

219

The united kingdom's changing requirements for spent fuel storage  

SciTech Connect (OSTI)

The UK is adopting an open fuel cycle, and is necessarily moving to a regime of long term storage of spent fuel, followed by geological disposal once a geological disposal facility (GDF) is available. The earliest GDF receipt date for legacy spent fuel is assumed to be 2075. The UK is set to embark on a programme of new nuclear build to maintain a nuclear energy contribution of 16 GW. Additionally, the UK are considering a significant expansion of nuclear energy in order to meet carbon reduction targets and it is plausible to foresee a scenario where up to 75 GW from nuclear power production could be deployed in the UK by the mid 21. century. Such an expansion, could lead to spent fuel storage and its disposal being a dominant issue for the UK Government, the utilities and the public. If the UK were to transition a closed fuel cycle, then spent fuel storage should become less onerous depending on the timescales. The UK has demonstrated a preference for wet storage of spent fuel on an interim basis. The UK has adopted an approach of centralised storage, but a 16 GW new build programme and any significant expansion of this may push the UK towards distributed spent fuel storage at a number of reactors station sites across the UK.

Hodgson, Z.; Hambley, D.I.; Gregg, R.; Ross, D.N. [National Nuclear Laboratory, Chadwick House, Birchwood Park, Warrington, Cheshire WA3 6AE (United Kingdom)

2013-07-01T23:59:59.000Z

220

Reactor-specific spent fuel discharge projections, 1987-2020  

SciTech Connect (OSTI)

The creation of five reactor-specific spent fuel data bases that contain information on the projected amounts of spent fuel to be discharged from U.S. commercial nuclear reactors through the year 2020 is described. The data bases contain detailed spent fuel information from existing, planned, and projected pressurized water reactors (PWR) and boiling water eactors (BWR), and one existing high temperature gas reactor (HTGR). The projections are based on individual reactor information supplied by the U.S. reactor owners. The basic information is adjusted to conform to Energy Information Administration (EIA) forecasts for nuclear installed capacity, generation, and spent fuel discharged. The EIA cases considered are: No New Orders (assumes increasing burnup), No New Orders with No Increased Burnup, Upper Reference (assumes increasing burnup), Upper Reference with No Increased Burnup, and Lower Reference (assumes increasing burnup). Detailed, by-reactor tables are provided for annual discharged amounts of spent fuel, for storage requirements assuming maximum at-reactor storage, and for storage requirements assuming maximum at-reactor storage plus intra-utility transshipment of spent fuel. 8 refs., 8 figs., 10 tabs.

Walling, R.C.; Heeb, C.M.; Purcell, W.L.

1988-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Shippingport Spent Fuel Canister System Description  

SciTech Connect (OSTI)

In 1978 and 1979, a total of 72 blanket fuel assemblies (BFAs), irradiated during the operating cycles of the Shippingport Atomic Power Station's Pressurized Water Reactor (PWR) Core 2 from April 1965 to February 1974, were transferred to the Hanford Site and stored in underwater storage racks in Cell 2R at the 221-T Canyon (T-Plant). The initial objective was to recover the produced plutonium in the BFAs, but this never occurred and the fuel assemblies have remained within the water storage pool to the present time. The Shippingport Spent Fuel Canister (SSFC) is a confinement system that provides safe transport functions (in conjunction with the TN-WHC cask) and storage for the BFAs at the Canister Storage Building (CSB). The current plan is for these BFAs to be retrieved from wet storage and loaded into SSFCs for dry storage. The sealed SSFCs containing BFAs will be vacuum dried, internally backfilled with helium, and leak tested to provide suitable confinement for the BFAs during transport and storage. Following completion of the drying and inerting process, the SSFCs are to be delivered to the CSB for closure welding and long-term interim storage. The CSB will provide safe handling and dry storage for the SSFCs containing the BFAs. The purpose of this document is to describe the SSFC system and interface equipment, including the technical basis for the system, design descriptions, and operations requirements. It is intended that this document will be periodically updated as more equipment design and performance specification information becomes available.

JOHNSON, D.M.

2000-03-27T23:59:59.000Z

222

Development of an alternative kraft black liquor recovery process based on low-temperature processing in fluidized beds. Final technical report on Annex 9, Task 1  

SciTech Connect (OSTI)

The overall objective of this research program was to provide the fundamental knowledge and experimental data from pilot scale operation for an alternative black liquor recovery technology which would have a higher overall energy efficiency, would not suffer from the smelt-water explosion hazard and would be lower in capital cost. In addition, the alternative process would be more flexible and well suited for incremental recovery capacity or for new pulping processes, such as the new sulfide-sulfide-AQ process. The research program consists of number of specific research objectives with the aim to achieve the ultimate objective of developing an alternative recovery process which is shown in Figure 1. The specific objectives are linked to individual unit operations and they represent the following research topics: (1) superheated steam drying of kraft black liquors; (2) fast pyrolysis of black liquor; (3) hydrogen sulfide absorption from flue gas; (4) reduction of sodium sulfate in solid phase with gaseous hydrogen; and (5) verification of the fundamental results in fluidized bed pilot plant. The accomplishments in each of these objectives are described.

Kubes, G.J.

1994-03-24T23:59:59.000Z

223

Black liquor combustion validated recovery boiler modeling: Final year report. Volume 1 (Main text and Appendix I, sections 1--4)  

SciTech Connect (OSTI)

This project was initiated in October 1990, with the objective of developing and validating a new computer model of a recovery boiler furnace using a computational fluid dynamics (CFD) code specifically tailored to the requirements for solving recovery boiler flows, and using improved submodels for black liquor combustion based on continued laboratory fundamental studies. The key tasks to be accomplished were as follows: (1) Complete the development of enhanced furnace models that have the capability to accurately predict carryover, emissions behavior, dust concentrations, gas temperatures, and wall heat fluxes. (2) Validate the enhanced furnace models, so that users can have confidence in the predicted results. (3) Obtain fundamental information on aerosol formation, deposition, and hardening so as to develop the knowledge base needed to relate furnace model outputs to plugging and fouling in the convective sections of the boiler. (4) Facilitate the transfer of codes, black liquid submodels, and fundamental knowledge to the US kraft pulp industry. Volume 1 contains the main body of the report and the first 4 sections of Appendix 1: Modeling of black liquor recovery boilers -- summary report; Flow and heat transfer modeling in the upper furnace of a kraft recovery boiler; Numerical simulation of black liquor combustion; and Investigation of turbulence models and prediction of swirling flows for kraft recovery furnaces.

Grace, T.M.; Frederick, W.J.; Salcudean, M.; Wessel, R.A.

1998-08-01T23:59:59.000Z

224

Ambiguous Red Shifts  

E-Print Network [OSTI]

A one-parameter conformal invariance of Maxwell's equations allows the wavelengths of electromagnetic waves to change as they propagate, and do so even in otherwise field-free space. This produces an ambiguity in interpretations of stellar red shifts. Experiments that will determine the value of the group parameter, and thereby remove the ambiguity, are proposed. They are based on an analysis of the anomalous frequency shifts uncovered in the Pioneer 10 and 11 spacecraft studies, and physical interpretation of an isomorphism discovered by E. L. Hill. If the group parameter is found to be non-zero, Hubble's relations will have to be reinterpreted and space-time metrics will have to be altered. The cosmological consequences of the transformations are even more extensive because, though they change frequencies, they do not alter the energy and momentum conservations laws of classical and quantum-electrodynamical fields established by Cunningham and by Bialynicki-Birula.

Carl E. Wulfman

2010-10-11T23:59:59.000Z

225

Black liquor combustion validated recovery boiler modeling: Final year report. Volume 3 (Appendices II, sections 2--3 and III)  

SciTech Connect (OSTI)

This project was initiated in October 1990, with the objective of developing and validating a new computer model of a recovery boiler furnace using a computational fluid dynamics (CFD) code specifically tailored to the requirements for solving recovery boiler flows, and using improved submodels for black liquor combustion based on continued laboratory fundamental studies. The key tasks to be accomplished were as follows: (1) Complete the development of enhanced furnace models that have the capability to accurately predict carryover, emissions behavior, dust concentrations, gas temperatures, and wall heat fluxes. (2) Validate the enhanced furnace models, so that users can have confidence in the predicted results. (3) Obtain fundamental information on aerosol formation, deposition, and hardening so as to develop the knowledge base needed to relate furnace model outputs to plugging and fouling in the convective sections of the boiler. (4) Facilitate the transfer of codes, black liquid submodels, and fundamental knowledge to the US kraft pulp industry. Volume 3 contains the following appendix sections: Formation and destruction of nitrogen oxides in recovery boilers; Sintering and densification of recovery boiler deposits laboratory data and a rate model; and Experimental data on rates of particulate formation during char bed burning.

Grace, T.M.; Frederick, W.J.; Salcudean, M.; Wessel, R.A.

1998-08-01T23:59:59.000Z

226

Spent Nuclear Fuel (SNF) Project Product Specification  

SciTech Connect (OSTI)

The process for removal of Spent Nuclear Fuel (SNF) from the K Basins has been divided into major sub-systems. The Fuel Retrieval System (FRS) removes fuel from the existing storage canisters, cleans it, and places it into baskets. The multi-canister overpack (MCO) loading system places the baskets into an MCO that has been pre-loaded in a cask. The cask, containing a loaded MCO, is then transferred to the Cold Vacuum Drying (CVD) Facility. After drying at the CVD Facility, the cask, and MCO, are transferred to the Canister Storage Building (CSB), where the MCO is removed from the cask, staged, inspected, sealed (by welding), and stored until a suitable permanent disposal option is implemented. The purpose of this document is to specify the process related characteristics of an MCO at the interface between major process systems. The characteristics are derived from the primary technical documents that form the basis for safety analysis and design calculations. This document translates the calculation assumptions into implementation requirements and describes the method of verifying that the requirement is achieved. These requirements are used to define validation test requirements and describe requirements that influence multiple sub-project safety analysis reports. This product specification establishes limits and controls for each significant process parameter at interfaces between major sub-systems that potentially affect the overall safety and/or quality of the SNF packaged for processing, transport, and interim dry storage. The product specifications in this document cover the SNF packaged in MCOs to be transported throughout the SNF Project. The description of the product specifications are organized in the document as follows: Section 2.0--Summary listing of product specifications at each major sub-system interface. Section 3.0--Summary description providing guidance as to how specifications are complied with by equipment design or processing within a major sub-system. Section 4.0--Specific technical basis description for each product specification. The scope of this product specification does not include data collection requirements to support accountability or environmental compliance activities.

PAJUNEN, A.L.

2000-12-07T23:59:59.000Z

227

Red Means Go Structural Engineering  

E-Print Network [OSTI]

Red Means Go Structural Engineering: An Overview of Global Directions Marc Hoit, Ph.D. Vice Chancellor for IT Professor of Civil Engineering #12;Red Means Go Overview · Global trends affecting on advanced degrees · Educate for the "Smile" Creativity as fundamental education Entrepreneurs ­ Need

228

Red Raider Orientation COLLEGE DISMISSAL  

E-Print Network [OSTI]

and Management Wildlife Science #12;RED RAIDER ORIENTATION University Studies University Studies Wind Energy Center, City of Lubbock · Information Sessions and Campus Resource Fair · Dinner on your own and Parent Communications, etc.) #12;#12;RED RAIDER ORIENTATION Business Administration Accounting Energy Commerce

Rock, Chris

229

White Baneberry and Red Baneberry  

E-Print Network [OSTI]

1 White Baneberry and Red Baneberry Actaea pachypoda and Actaea rubra buttercup family (ranunculaceae) both white baneberry and red baneberry are poisonous plants native to the northeast inhabit swamps. Range: white baneberry--parts of the canadian mari- times and the southern border

Landweber, Laura

230

Red Rice Research and Control.  

E-Print Network [OSTI]

s cu l t iva ted white r i c e , Oryza sativa L. Red r i c e crosses read i ly .- with white r i c e and i s very s i m i l a r t o it i n appearance. The main morpho- logical d i f ferences t h a t d i s t ingu i sh it from white r i c... l e s i n white r i c e . Since these characters can be t r ans fe r red by crossing, new red r i c e types can and do appear. Red r i c e i s undesirable because: 1. Red r i c e p l a n t s compete with cu l t iva ted r i c e...

Baker, John B.; Baldwin, Ford L.; Bourgeois, W.J.; Cox, Clodis H.; Craigmiles, Julian P.; Dishman, William D.; Eastin, E. Ford; Helpert, Charles W.; Hill, Lewis C.; Huey, Bobby A.; Klosterboer, Arlen D.; Sonnier, Earl A.

1980-01-01T23:59:59.000Z

231

Safety Aspects of Dry Spent Fuel Storage and Spent Fuel Management - 13559  

SciTech Connect (OSTI)

Dry storage systems are characterized by passive and inherent safety systems ensuring safety even in case of severe incidents or accidents. After the events of Fukushima, the advantages of such passively and inherently safe dry storage systems have become more and more obvious. As with the storage of all radioactive materials, the storage of spent nuclear fuel (SF) and high-level radioactive waste (HLW) must conform to safety requirements. Following safety aspects must be achieved throughout the storage period: - safe enclosure of radioactive materials, - safe removal of decay heat, - securing nuclear criticality safety, - avoidance of unnecessary radiation exposure. The implementation of these safety requirements can be achieved by dry storage of SF and HLW in casks as well as in other systems such as dry vault storage systems or spent fuel pools, where the latter is neither a dry nor a passive system. Furthermore, transport capability must be guaranteed during and after storage as well as limitation and control of radiation exposure. The safe enclosure of radioactive materials in dry storage casks can be achieved by a double-lid sealing system with surveillance of the sealing system. The safe removal of decay heat must be ensured by the design of the storage containers and the storage facility. The safe confinement of radioactive inventory has to be ensured by mechanical integrity of fuel assembly structures. This is guaranteed, e.g. by maintaining the mechanical integrity of the fuel rods or by additional safety measures for defective fuel rods. In order to ensure nuclear critically safety, possible effects of accidents have also to be taken into consideration. In case of dry storage it might be necessary to exclude the re-positioning of fissile material inside the container and/or neutron moderator exclusion might be taken into account. Unnecessary radiation exposure can be avoided by the cask or canister vault system itself. In Germany dry storage of SF in casks fulfills both transport and storage requirements. Mostly, storage facilities are designed as concrete buildings above the ground, but due to regional constraints, one storage facility has also been built as a rock tunnel. The decay heat is always removed by natural air flow; further technical equipment is not needed. The removal of decay heat and shielding had been modeled and calculated by state-of-the-art computer codes before such a facility has been built. TueV and BAM present their long experience in the licensing process for sites and casks and inform about spent nuclear fuel management and issues concerning dry storage of spent nuclear fuel. Different storage systems and facilities in Germany, Europe and world-wide are compared with respect to the safety aspects mentioned above. Initial points are the safety issues of wet storage of SF, and it is shown how dry storage systems can ensure the compliance with the mentioned safety criteria over a long storage period. The German storage concept for dry storage of SF and HLW is presented and discussed. Exemplarily, the process of licensing, erection and operation of selected German dry storage facilities is presented. (authors)

Botsch, W.; Smalian, S.; Hinterding, P. [TUV NORD Nuclear c/o TUV NORD EnSys Hannover GmbH and Co.KG, Dept. Radiation Protection and Waste Disposal, Am TueV 1, 30519 Hannover (Germany)] [TUV NORD Nuclear c/o TUV NORD EnSys Hannover GmbH and Co.KG, Dept. Radiation Protection and Waste Disposal, Am TueV 1, 30519 Hannover (Germany); Voelzke, H.; Wolff, D.; Kasparek, E. [BAM Federal Institute for Materials Research and Testing Division 3.4 Safety of Storage Containers Unter den Eichen 44-46, 12203 Berlin (Germany)] [BAM Federal Institute for Materials Research and Testing Division 3.4 Safety of Storage Containers Unter den Eichen 44-46, 12203 Berlin (Germany)

2013-07-01T23:59:59.000Z

232

Spent nuclear fuel discharges from US reactors 1993  

SciTech Connect (OSTI)

The Energy Information Administration (EIA) of the U.S. Department of Energy (DOE) administers the Nuclear Fuel Data Survey, Form RW-859. This form is used to collect data on fuel assemblies irradiated at commercial nuclear reactors operating in the United States, and the current inventories and storage capacities of those reactors. These data are important to the design and operation of the equipment and facilities that DOE will use for the future acceptance, transportation, and disposal of spent fuels. The data collected and presented identifies trends in burnup, enrichment, and spent nuclear fuel discharged form commercial light-water reactor as of December 31, 1993. The document covers not only spent nuclear fuel discharges; but also site capacities and inventories; canisters and nonfuel components; and assembly type characteristics.

Not Available

1995-02-01T23:59:59.000Z

233

Status of Proposed Repository for Latin-American Spent Fuel  

SciTech Connect (OSTI)

This report compiles preliminary information that supports the premise that a repository is needed in Latin America and analyzes the nuclear situation (mainly in Argentina and Brazil) in terms of nuclear capabilities, inventories, and regional spent-fuel repositories. The report is based on several sources and summarizes (1) the nuclear capabilities in Latin America and establishes the framework for the need of a permanent repository, (2) the International Atomic Energy Agency (IAEA) approach for a regional spent-fuel repository and describes the support that international institutions are lending to this issue, (3) the current situation in Argentina in order to analyze the Argentinean willingness to find a location for a deep geological repository, and (4) the issues involved in selecting a location for the repository and identifies a potential location. This report then draws conclusions based on an analysis of this information. The focus of this report is mainly on spent fuel and does not elaborate on other radiological waste sources.

Ferrada, J.J.

2004-10-04T23:59:59.000Z

234

Mission Need Statement: Idaho Spent Fuel Facility Project  

SciTech Connect (OSTI)

Approval is requested based on the information in this Mission Need Statement for The Department of Energy, Idaho Operations Office (DOE-ID) to develop a project in support of the mission established by the Office of Environmental Management to "complete the safe cleanup of the environmental legacy brought about from five decades of nuclear weapons development and government-sponsored nuclear energy research". DOE-ID requests approval to develop the Idaho Spent Fuel Facility Project that is required to implement the Department of Energy's decision for final disposition of spent nuclear fuel in the Geologic Repository at Yucca Mountain. The capability that is required to prepare Spent Nuclear Fuel for transportation and disposal outside the State of Idaho includes characterization, conditioning, packaging, onsite interim storage, and shipping cask loading to complete shipments by January 1,2035. These capabilities do not currently exist in Idaho.

Barbara Beller

2007-09-01T23:59:59.000Z

235

Spent fuel storage system for LMFBR fuel experiments  

SciTech Connect (OSTI)

Fuel that had been irradiated in the Argonne National Laboratory Experimental Breeder Reactor II (EBR-II) at Idaho Falls, Idaho, and examined at the Hanford Engineering Development Laboratory at Richland, Washington, was placed in long term retrievable storage utilizing a system designed at Hanford. The Spent Fuel Storage Cask system was designed for transport and storage of a large quantity of spent fuel at the Hanford 200 Area transuranic (TRU) asphalt storage pad. The entire system is designed for long term retrievable storage to allow future reprocessing of the fuel. The system was designed to meet the criticality, shielding, and thermal requirements for a maximum fuel load of four kilograms fissile. The Spent Fuel Storage Cask was built to transport and store the fuel from EBR-II on the TRU asphalt storage pad.

Seay, J.M.; Gruber, W.J.

1983-01-01T23:59:59.000Z

236

Information handbook on independent spent fuel storage installations  

SciTech Connect (OSTI)

In this information handbook, the staff of the U.S. Nuclear Regulatory Commission describes (1) background information regarding the licensing and history of independent spent fuel storage installations (ISFSIs), (2) a discussion of the licensing process, (3) a description of all currently approved or certified models of dry cask storage systems (DCSSs), and (4) a description of sites currently storing spent fuel in an ISFSI. Storage of spent fuel at ISFSIs must be in accordance with the provisions of 10 CFR Part 72. The staff has provided this handbook for information purposes only. The accuracy of any information herein is not guaranteed. For verification or for more details, the reader should refer to the respective docket files for each DCSS and ISFSI site. The information in this handbook is current as of September 1, 1996.

Raddatz, M.G.; Waters, M.D.

1996-12-01T23:59:59.000Z

237

SCOTTISH RED SQUIRREL ACTION PLAN  

E-Print Network [OSTI]

SCOTTISH RED SQUIRREL ACTION PLAN 2006­2011 #12;#12;S C O T T I S H R E D S Q U I R R E L A C T I O.1 Background 1 1.2 Action Plan Working Group 1 1.3 Issues affecting the conservation of the red squirrel 1 1.2 Timescale and partnership working 3 2.3 Rationale 3 2.4 Key actions 4 2.4.1 Establish and monitor the red

238

NUHOMS modular spent-fuel storage system: Performance testing  

SciTech Connect (OSTI)

This report documents the results of a heat transfer and shielding performance evaluation of the NUTECH HOrizontal MOdular Storage (NUHOMS{reg sign}) System utilized by the Carolina Power and Light Co. (CP L) in an Independent Spent Fuel Storage Installation (ISFSI) licensed by the US Nuclear Regulatory Commission (NRC). The ISFSI is located at CP L's H. B. Robinson Nuclear Plant (HBR) near Hartsville, South Carolina. The demonstration included testing of three modules, first with electric heaters and then with spent fuel. The results indicated that the system was conservatively designed, with all heat transfer and shielding design criteria easily met. 5 refs., 45 figs., 9 tabs.

Strope, L.A.; McKinnon, M.A. (Pacific Northwest Lab., Richland, WA (USA)); Dyksterhouse, D.J.; McLean, J.C. (Carolina Power and Light Co., Raleigh, NC (USA))

1990-09-01T23:59:59.000Z

239

The burnup dependence of light water reactor spent fuel oxidation  

SciTech Connect (OSTI)

Over the temperature range of interest for dry storage or for placement of spent fuel in a permanent repository under the conditions now being considered, UO{sub 2} is thermodynamically unstable with respect to oxidation to higher oxides. The multiple valence states of uranium allow for the accommodation of interstitial oxygen atoms in the fuel matrix. A variety of stoichiometric and nonstoichiometric phases is therefore possible as the fuel oxidizers from UO{sub 2} to higher oxides. The oxidation of UO{sub 2} has been studied extensively for over 40 years. It has been shown that spent fuel and unirradiated UO{sub 2} oxidize via different mechanisms and at different rates. The oxidation of LWR spent fuel from UO{sub 2} to UO{sub 2.4} was studied previously and is reasonably well understood. The study presented here was initiated to determine the mechanism and rate of oxidation from UO{sub 2.4} to higher oxides. During the early stages of this work, a large variability in the oxidation behavior of samples oxidized under nearly identical conditions was found. Based on previous work on the effect of dopants on UO{sub 2} oxidation and this initial variability, it was hypothesized that the substitution of fission product and actinide impurities for uranium atoms in the spent fuel matrix was the cause of the variable oxidation behavior. Since the impurity concentration is roughly proportional to the burnup of a specimen, the oxidation behavior of spent fuel was expected to be a function of both temperature and burnup. This report (1) summarizes the previous oxidation work for both unirradiated UO{sub 2} and spent fuel (Section 2.2) and presents the theoretical basis for the burnup (i.e., impurity concentration) dependence of the rate of oxidation (Sections 2.3, 2.4, and 2.5), (2) describes the experimental approach (Section 3) and results (Section 4) for the current oxidation tests on spent fuel, and (3) establishes a simple model to determine the activation energies associated with spent fuel oxidation (Section 5).

Hanson, B.D.

1998-07-01T23:59:59.000Z

240

Method for the regeneration of spent molten zinc chloride  

DOE Patents [OSTI]

In a process for regenerating spent molten zinc chloride which has been used in the hydrocracking of coal or ash-containing polynuclear aromatic hydrocarbonaceous materials derived therefrom and which contains zinc chloride, zinc oxide, zinc oxide complexes and ash-containing carbonaceous residue, by incinerating the spent molten zinc chloride to vaporize the zinc chloride for subsequent condensation to produce a purified molten zinc chloride: an improvement comprising the use of clay in the incineration zone to suppress the vaporization of metals other than zinc. Optionally water is used in conjunction with the clay to further suppress the vaporization of metals other than zinc.

Zielke, Clyde W. (McMurray, PA); Rosenhoover, William A. (Pittsburgh, PA)

1981-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Materials for the pulp and paper industry. Section 1: Development of materials for black liquor recovery boilers  

SciTech Connect (OSTI)

Black liquor recovery boilers are essential components of kraft pulp and paper mills because they are a critical element of the system used to recover the pulping chemicals required in the kraft pulping process. In addition, the steam produced in these boilers is used to generate a significant portion of the electrical power used in the mill. Recovery boilers require the largest capital investment of any individual component of a paper mill, and these boilers are a major source of material problems in a mill. The walls and floors of these boilers are constructed of tube panels that circulate high pressure water. Molten salts (smelt) accumulate on the floor of recovery boilers, and leakage of water into the boiler can result in a violent explosion when the leaked water instantly vaporizes upon contacting the molten smelt. Because corrosion of the conventionally-used carbon steel tubing was found to be excessive in the lower section of recovery boilers, use of stainless steel/carbon steel co-extruded tubing was adopted for boiler walls to lessen corrosion and reduce the likelihood of smelt/water explosions. Eventually, this co-extruded or composite (as it is known in the industry) tubing was selected for use as a portion or all of the floor of recovery boilers, particularly those operating at pressures > 6.2 MPa (900 psi), because of the corrosion problems encountered in carbon steel floor tubes. Since neither the cause of the cracking nor an effective solution has been identified, this program was established to develop a thorough understanding of the degradation that occurs in the composite tubing used for walls and floors. This is being accomplished through a program that includes collection and review of technical reports, examination of unexposed and cracked tubes from boiler floors, computer modeling to predict residual stresses under operating conditions, and operation of laboratory tests to study corrosion, stress corrosion cracking, and thermal fatigue.

Keiser, J.R.; Hubbard, C.R.; Payzant, E.A. [Oak Ridge National Lab., TN (United States)] [and others

1997-04-01T23:59:59.000Z

242

Application of Neutron-Absorbing Structural-Amorphous metal (SAM) Coatings for Spent Nuclear Fuel (SNF) Container to Enhance Criticality Safety Controls  

E-Print Network [OSTI]

241 Pu, etc. ). To prevent nuclear criticality in spent fuelto enhance criticality safety for spent nuclear fuel inSpent Nuclear Fuel (SNF) Container to Enhance Criticality

2006-01-01T23:59:59.000Z

243

Jamaican red clay tobacco pipes  

E-Print Network [OSTI]

JAMAICAN RED CLAY TOBACCO PIPES A Thesis by KENAN PAUL HEIDTKE Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF ARTS December 1992 Major Subject...: Anthropology JAMAICAN RED CLAY TOBACCO PIPES A Thesis by KENAN PAUL HEIDTKE Approved as to style and content by: Dorm L. Hamilton (Chair of Committee) Frederick H. van Doorninck, J (Member) enry C. Schmidt (Member) Vaughn M. Bryant (Head...

Heidtke, Kenan Paul

1992-01-01T23:59:59.000Z

244

Engineering Study for a Full Scale Demonstration of Steam Reforming Black Liquor Gasification at Georgia-Pacific's Mill in Big Island, Virginia  

SciTech Connect (OSTI)

Georgia-Pacific Corporation performed an engineering study to determine the feasibility of installing a full-scale demonstration project of steam reforming black liquor chemical recovery at Georgia-Pacific's mill in Big Island, Virginia. The technology considered was the Pulse Enhanced Steam Reforming technology that was developed and patented by Manufacturing and Technology Conversion, International (MTCI) and is currently licensed to StoneChem, Inc., for use in North America. Pilot studies of steam reforming have been carried out on a 25-ton per day reformer at Inland Container's Ontario, California mill and on a 50-ton per day unit at Weyerhaeuser's New Bern, North Carolina mill.

Robert De Carrera; Mike Ohl

2002-03-19T23:59:59.000Z

245

Recycling practices of spent MgO-C refractories  

SciTech Connect (OSTI)

The recycling options of spent MgO-C refractories from an electrical arc furnace (EAF) have been evaluated. The economic, quality of spent refractories and products made from it, the ease of implementation of a recycling practice and the interest of steel melt shops were considered. It was decided that the best option of most EAF shops would be to recycle spent MgO-C refractory as a foaming slag conditioner because of their MgO content. Crushed MgO-C spent refractories can be reused directly back into an EAF without complex and costly beneficiation. Even though this practice is simple, it is critical to know the optimum amount of MgO in the slag to achieve the best foaming quality. A computer model was designed to find the optimum MgO amount. This modeling also helps the melt shop extend refractory service life, increase the energy efficiency, increase productivity, and decrease the amount of slag. Issues related to the refractory recycling will be discussed.

Kwong, Kyei-Sing; Bennett, James P.

2002-10-01T23:59:59.000Z

246

Methodology for determining criteria for storing spent fuel in air  

SciTech Connect (OSTI)

Dry storage in an air atmosphere is a method being considered for spent light water reactor (LWR) fuel as an alternative to storage in an inert gas environment. However, methods to predict fuel integrity based on oxidation behavior of the fuel first must be evaluated. The linear cumulative damage method has been proposed as a technique for defining storage criteria. Analysis of limited nonconstant temperature data on nonirradiated fuel samples indicates that this approach yields conservative results for a strictly decreasing-temperature history. On the other hand, the description of damage accumulation in terms of remaining life concepts provides a more general framework for making predictions of failure. Accordingly, a methodology for adapting remaining life concepts to UO/sub 2/ oxidation has been developed at Pacific Northwest Laboratory. Both the linear cumulative damage and the remaining life methods were used to predict oxidation results for spent fuel in which the temperature was decreased with time to simulate the temperature history in a dry storage cask. The numerical input to the methods was based on oxidation data generated with nonirradiated UO/sub 2/ pellets. The calculated maximum allowable storage temperatures are strongly dependent on the temperature-time profile and emphasize the conservatism inherent in the linear cumulative damage model. Additional nonconstant temperature data for spent fuel are needed to both validate the proposed methods and to predict temperatures applicable to actual spent fuel storage.

Reid, C.R.; Gilbert, E.R.

1986-11-01T23:59:59.000Z

247

RADIATION ANALYSIS OF A SPENT-FUEL STORAGE CASK  

E-Print Network [OSTI]

RADIATION ANALYSIS OF A SPENT-FUEL STORAGE CASK by J.K. Shultis Department of Mechanical;Radiation Analysis of a Spect-Fuel Storage Cask by J.K.Shultis Dept. Mechanical and Nuclear Engineering compositions for the air, soil, berm and concrete were taken from the references indicated in Table 1. 1.3 Cask

Shultis, J. Kenneth

248

Automatic Red Eye Removal for Digital Photography  

E-Print Network [OSTI]

Chapter 1 Automatic Red Eye Removal for Digital Photography FRANCESCA GASPARINI DISCo, Dipartimento The red eye effect is a well known problem in photography. It is often seen in amateur shots taken with a built-in flash, but the problem is also well known to professional photographers. Red eye is the red

Schettini, Raimondo

249

A Monte Carlo based spent fuel analysis safeguards strategy assessment  

SciTech Connect (OSTI)

Safeguarding nuclear material involves the detection of diversions of significant quantities of nuclear materials, and the deterrence of such diversions by the risk of early detection. There are a variety of motivations for quantifying plutonium in spent fuel assemblies by means of nondestructive assay (NDA) including the following: strengthening the capabilities of the International Atomic Energy Agencies ability to safeguards nuclear facilities, shipper/receiver difference, input accountability at reprocessing facilities and burnup credit at repositories. Many NDA techniques exist for measuring signatures from spent fuel; however, no single NDA technique can, in isolation, quantify elemental plutonium and other actinides of interest in spent fuel. A study has been undertaken to determine the best integrated combination of cost effective techniques for quantifying plutonium mass in spent fuel for nuclear safeguards. A standardized assessment process was developed to compare the effective merits and faults of 12 different detection techniques in order to integrate a few techniques and to down-select among the techniques in preparation for experiments. The process involves generating a basis burnup/enrichment/cooling time dependent spent fuel assembly library, creating diversion scenarios, developing detector models and quantifying the capability of each NDA technique. Because hundreds of input and output files must be managed in the couplings of data transitions for the different facets of the assessment process, a graphical user interface (GUI) was development that automates the process. This GUI allows users to visually create diversion scenarios with varied replacement materials, and generate a MCNPX fixed source detector assessment input file. The end result of the assembly library assessment is to select a set of common source terms and diversion scenarios for quantifying the capability of each of the 12 NDA techniques. We present here the generalized assessment process, the techniques employed to automate the coupled facets of the assessment process, and the standard burnup/enrichment/cooling time dependent spent fuel assembly library. We also clearly define the diversion scenarios that will be analyzed during the standardized assessments. Though this study is currently limited to generic PWR assemblies, it is expected that the results of the assessment will yield an adequate spent fuel analysis strategy knowledge that will help the down-select process for other reactor types.

Fensin, Michael L [Los Alamos National Laboratory; Tobin, Stephen J [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory; Sandoval, Nathan P [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

250

EA-0912: Urgent-Relief Acceptance of Foreign Research Reactor Spent Nuclear Fuel  

Broader source: Energy.gov [DOE]

This EA evaluates the environmental impacts of a proposal to accept 409 spent fuel elements from eight foreign research reactors in seven European countries. The spent fuel would be shipped across...

251

What to Expect When Readying to Move Spent Nuclear Fuel from...  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

What to Expect When Readying to Move Spent Nuclear Fuel from Commercial Nuclear Power Plants What to Expect When Readying to Move Spent Nuclear Fuel from Commercial Nuclear Power...

252

An experiment to simulate the heat transfer properties of a dry, horizontal spent nuclear fuel assembly  

E-Print Network [OSTI]

Nuclear power reactors generate highly radioactive spent fuel assemblies. Initially, the spent fuel assemblies are stored for a period of several years in an on-site storage facility to allow the radioactivity levels of ...

Lovett, Phyllis Maria

1991-01-01T23:59:59.000Z

253

Air Shipment of Spent Nuclear Fuel from Romania to Russia  

SciTech Connect (OSTI)

Romania successfully completed the worlds first air shipment of spent nuclear fuel transported in Type B(U) casks under existing international laws and without shipment license special exceptions when the last Romanian highly enriched uranium (HEU) spent nuclear fuel was transported to the Russian Federation in June 2009. This air shipment required the design, fabrication, and licensing of special 20 foot freight containers and cask tiedown supports to transport the eighteen TUK 19 shipping casks on a Russian commercial cargo aircraft. The new equipment was certified for transport by road, rail, water, and air to provide multi modal transport capabilities for shipping research reactor spent fuel. The equipment design, safety analyses, and fabrication were performed in the Russian Federation and transport licenses were issued by both the Russian and Romanian regulatory authorities. The spent fuel was transported by truck from the VVR S research reactor to the Bucharest airport, flown by commercial cargo aircraft to the airport at Yekaterinburg, Russia, and then transported by truck to the final destination in a secure nuclear facility at Chelyabinsk, Russia. This shipment of 23.7 kg of HEU was coordinated by the Russian Research Reactor Fuel Return Program (RRRFR), as part of the U.S. Department of Energy Global Threat Reduction Initiative (GTRI), in close cooperation with the Rosatom State Atomic Energy Corporation and the International Atomic Energy Agency, and was managed in Romania by the National Commission for Nuclear Activities Control (CNCAN). This paper describes the planning, shipment preparations, equipment design, and license approvals that resulted in the safe and secure air shipment of this spent nuclear fuel.

Igor Bolshinsky; Ken Allen; Lucian Biro; Alexander Buchelnikov

2010-10-01T23:59:59.000Z

254

Storage of LWR spent fuel in air. Volume 3, Results from exposure of spent fuel to fluorine-contaminated air  

SciTech Connect (OSTI)

The Behavior of Spent Fuel in Storage (BSFS) Project has conducted research to develop data on spent nuclear fuel (irradiated U0{sub 2}) that could be used to support design, licensing, and operation of dry storage installations. Test Series B conducted by the BSFS Project was designed as a long-term study of the oxidation of spent fuel exposed to air. It was discovered after the exposures were completed in September 1990 that the test specimens had been exposed to an atmosphere of bottled air contaminated with an unknown quantity of fluorine. This exposure resulted in the test specimens reacting with both the oxygen and the fluorine in the oven atmospheres. The apparent source of the fluorine was gamma radiation-induced chemical decomposition of the fluoro-elastomer gaskets used to seal the oven doors. This chemical decomposition apparently released hydrofluoric acid (HF) vapor into the oven atmospheres. Because the Test Series B specimens were exposed to a fluorine-contaminated oven atmosphere and reacted with the fluorine, it is recommended that the Test Series B data not be used to develop time-temperature limits for exposure of spent nuclear fuel to air. This report has been prepared to document Test Series B and present the collected data and observations.

Cunningham, M.E.; Thomas, L.E.

1995-06-01T23:59:59.000Z

255

High-solids black liquor firing in pulp and paper industry kraft recovery boilers: Phase 1 -- Final report. Volume 2: Project technical results  

SciTech Connect (OSTI)

This project is a multiple-phase effort to develop technologies to improve high-solids black liquor firing in pulp mill recovery boilers. The principal means to this end is to construct and operate a pilot-scale recovery furnace simulator (RFS) in which these technologies can be tested. The Phase 1 objectives are to prepare a preliminary design for the RFS, delineate a project concept for evaluating candidate technologies, establish industrial partners, and report the results. Phase 1 addressed the objectives with seven tasks: Develop a preliminary design of the RFS; estimate the detailed design and construction costs of the RFS and the balance of the project; identify interested parties in the paper industry and key suppliers; plan the Phase 2 and Phase 3 tests to characterize the RFS; evaluate the economic justification for high-solids firing deployment in the industry; evaluate high-solids black liquor property data to support the RFS design; manage the project and reporting results, which included planning the future program direction.

Southards, W.T.; Clement, J.L.; McIlroy, R.A.; Tharp, M.R.; Verrill, C.L.; Wessell, R.A.

1995-11-01T23:59:59.000Z

256

Red Mesa | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revisionEnvReviewNonInvasiveExplorationUT-g Grant of Access Permit5-ID-aRECRaton,RFPs Home NameRecurrentRedRed

257

Red-Black Trees 1 2004 Goodrich, Tamassia Red-Black Trees  

E-Print Network [OSTI]

Red-Black Trees 1© 2004 Goodrich, Tamassia Red-Black Trees 6 3 8 4 v z #12;Red-Black Trees 2© 2004 Goodrich, Tamassia From (2,4) to Red-Black Trees A red-black tree is a representation of a (2,4) tree by means of a binary tree whose nodes are colored red or black In comparison with its associated (2,4) tree

Alechina, Natasha

258

Preliminary study on direct recycling of spent PWR fuel in PWR system  

SciTech Connect (OSTI)

Preliminary study on direct recycling of PWR spent fuel to support SUPEL (Straight Utilization of sPEnt LWR fuel in LWR system) scenario has been conducted. Several spent PWR fuel compositions in loaded PWR fuel has been evaluated to obtain the criticality of reactor. The reactor can achieve it criticality for U-235 enrichment in the loaded fresh fuel is at least 4.0 a% with the minimum fraction of the spent fuel in the core is 15.0 %. The neutron spectra become harder with the escalating of U-235 enrichment in the loaded fresh fuel as well as the amount of the spent fuel in the core.

Waris, Abdul; Nuha; Novitriana; Kurniadi, Rizal; Su'ud, Zaki [Nuclear Physics and Biophysics Research Division, Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Jalan Ganesa 10 Bandung 40132 (Indonesia)

2012-06-06T23:59:59.000Z

259

COGEMA operating experience in the transportation of spent fuel, nuclear materials and radioactive waste  

SciTech Connect (OSTI)

Were a spent fuel transportation accident to occur, no matter how insignificant, the public outcry could jeopardize both reprocessing operations and power plant operations for utilities that have elected to reprocess their spent fuel. Aware of this possibility, COGEMA has become deeply involved in spent fuel transportation to ensure that it is performed according to the highest standards of transportation safety. Spent fuel transportation is a vital link between the reactor site and the reprocessing plant. This paper gives an overview of COGEMA`s experience in the transportation of spent fuel.

Bernard, H. [COGEMA, Velizy-Villacoublay (France)

1993-12-31T23:59:59.000Z

260

Molten tin reprocessing of spent nuclear fuel elements  

DOE Patents [OSTI]

A method and apparatus for reprocessing spent nuclear fuel is described. Within a containment vessel, a solid plug of tin and nitride precipitates supports a circulating bath of liquid tin therein. Spent nuclear fuel is immersed in the liquid tin under an atmosphere of nitrogen, resulting in the formation of nitride precipitates. The layer of liquid tin and nitride precipitates which interfaces the plug is solidified and integrated with the plug. Part of the plug is melted, removing nitride precipitates from the containment vessel, while a portion of the plug remains solidified to support the liquid tin and nitride precipitates remaining in the containment vessel. The process is practiced numerous times until substantially all of the precipitated nitrides are removed from the containment vessel.

Heckman, Richard A. (Castro Valley, CA)

1983-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Test plan for thermogravimetric analyses of BWR spent fuel oxidation  

SciTech Connect (OSTI)

Preliminary studies indicated the need for additional low-temperature spent fuel oxidation data to determine the behavior of spent fuel as a waste form for a tuffy repository. Short-term thermogravimetric analysis tests were recommended in a comprehensive technical approach as the method for providing scoping data that could be used to (1) evaluate the effects of variables such as moisture and burnup on the oxidation rate, (2) determine operative mechanisms, and (3) guide long-term, low-temperature oxidation testing. The initial test series studied the temperature and moisture effects on pressurized water reactor fuel as a function of particle and grain size. This document presents the test matrix for studying the oxidation behavior of boiling water reactor fuel in the temperature range of 140 to 225{degree}C. 17 refs., 7 figs., 3 tabs.

Einziger, R.E.

1988-12-01T23:59:59.000Z

262

Spent fuel utilization in a compact traveling wave reactor  

SciTech Connect (OSTI)

In recent years, several innovative designs of nuclear reactors are proposed. One of them is Traveling Wave Reactor (TWR). The unique characteristic of a TWR is the capability of breeding its own fuel in the reactor. The reactor is fueled by mostly depleted, natural uranium or spent nuclear fuel and a small amount of enriched uranium to initiate the fission process. Later on in the core, the reactor gradually converts the non-fissile material into the fissile in a process like a traveling wave. In this work, a TWR with spent nuclear fuel blanket was studied. Several parameters such as reactivity coefficients, delayed neutron fraction, prompt neutron generation lifetime, and fission power, were analyzed. The discharge burnup composition was also analyzed. The calculation is performed by a continuous energy Monte Carlo code McCARD.

Hartanto, Donny; Kim, Yonghee [Korea Advanced Institute of Science and Technology 373-1 Kusong-dong, Yuseong-gu, Daejeon, 305-701 (Korea, Republic of)

2012-06-06T23:59:59.000Z

263

Removal of arsenic compounds from spent catecholated polymer  

DOE Patents [OSTI]

Described is a process for removing arsenic from petroliferous derived liquids by contacting said liquid at an elevated temperature with a divinylbenzene-crosslinked polystyrene having catechol ligands anchored thereon. Also, described is a process for regenerating spent catecholated polystyrene by removal of the arsenic bound to it from contacting petroliferous liquid as described above and involves: a. treating said spent catecholated polystyrene, at a temperature in the range of about 20.degree. to 100.degree. C. with an aqueous solution of at least one carbonate and/or bicarbonate of ammonium, alkali and alkaline earth metals, said solution having a pH between about 8 and 10 and, b. separating the solids and liquids from each other. Preferably the regeneration treatment is in two steps wherein step (a) is carried out with an aqueous alcoholic carbonate solution containing lower alkyl alcohol, and, steps (a) and (b) are repeated using a bicarbonate.

Fish, Richard H. (Berkeley, CA)

1985-01-01T23:59:59.000Z

264

Gamma Ray Mirrors for Direct Measurement of Spent Nuclear Fuel  

SciTech Connect (OSTI)

Direct measurement of the amount of Pu and U in spent nuclear fuel represents a challenge for the safeguards community. Ideally, the characteristic gamma-ray emission lines from different isotopes provide an observable suitable for this task. However, these lines are generally lost in the fierce flux of radiation emitted by the fuel. The rates are so high that detector dead times limit measurements to only very small solid angles of the fuel. Only through the use of carefully designed view ports and long dwell times are such measurements possible. Recent advances in multilayer grazing-incidence gamma-ray optics provide one possible means of overcoming this difficulty. With a proper optical and coating design, such optics can serve as a notch filter, passing only narrow regions of the overall spectrum to a fully shielded detector that does not view the spent fuel directly. We report on the design of a mirror system and a number of experimental measurements.

Pivovaroff, Dr. Michael J. [Lawrence Livermore National Laboratory (LLNL)] [Lawrence Livermore National Laboratory (LLNL); Ziock, Klaus-Peter [ORNL] [ORNL; Harrison, Mark J [ORNL] [ORNL; Soufli, Regina [Lawrence Livermore National Laboratory (LLNL)] [Lawrence Livermore National Laboratory (LLNL)

2014-01-01T23:59:59.000Z

265

Nuclear Waste Imaging and Spent Fuel Verification by Muon Tomography  

E-Print Network [OSTI]

This paper explores the use of cosmic ray muons to image the contents of shielded containers and detect high-Z special nuclear materials inside them. Cosmic ray muons are a naturally occurring form of radiation, are highly penetrating and exhibit large scattering angles on high Z materials. Specifically, we investigated how radiographic and tomographic techniques can be effective for non-invasive nuclear waste characterization and for nuclear material accountancy of spent fuel inside dry storage containers. We show that the tracking of individual muons, as they enter and exit a structure, can potentially improve the accuracy and availability of data on nuclear waste and the contents of Dry Storage Containers (DSC) used for spent fuel storage at CANDU plants. This could be achieved in near real time, with the potential for unattended and remotely monitored operations. We show that the expected sensitivity, in the case of the DSC, exceeds the IAEA detection target for nuclear material accountancy.

Jonkmans, G; Jewett, C; Thompson, M

2012-01-01T23:59:59.000Z

266

Prototype spent-fuel canister design, analysis, and test  

SciTech Connect (OSTI)

Sandia National Laboratories was asked by the US Energy Research and Development Administration (now US Department of Energy) to design the spent fuel shipping cask system for the Clinch River Breeder Reactor Plant (CRBRP). As a part of this task, a canister which holds liquid sodium and the spent fuel assembly was designed, analyzed, and tested. The canister body survived the regulatory Type-B 9.1-m (30-ft) drop test with no apparent leakage. However, the commercially available metal seal used in this design leaked after the tests. This report describes the design approach, analysis, and prototype canister testing. Recommended work for completing the design, when funding is available, is included.

Leisher, W.B.; Eakes, R.G.; Duffey, T.A.

1982-03-01T23:59:59.000Z

267

Technical strategy for the management of INEEL spent nuclear fuel  

SciTech Connect (OSTI)

This report presents evaluations, findings, and recommendations of the Idaho National Engineering and Environmental Laboratory (INEEL) Spent Nuclear Fuel Task Team. The technical strategy developed by the Task Team includes stabilization, near term storage, packaging, transport, and ultimate disposal. Key issues identified and discussed include waste characterization, criticality, packaging, waste form performance, and special fuels. Current plans focus on onsite needs, and include three central elements: (1) resolution of near-term vulnerabilities, (2) consolidation of storage locations, and (3) achieving dry storage in transportable packages. In addition to the Task Team report, appendices contain information on the INEEL spent fuel inventory; regulatory decisions and agreements; and analyses of criticality, packaging, storage, transportation, and system performance of a geological repository. 16 refs., 6 figs., 4 tabs.

NONE

1997-03-01T23:59:59.000Z

268

Thermomechanical modeling of the Spent Fuel Test-Climax  

SciTech Connect (OSTI)

The Spent Fuel Test-Climax (SFT-C) was conducted to evaluate the feasibility of retrievable deep geologic storage of commercially generated spent nuclear-reactor fuel assemblies. One of the primary aspects of the test was to measure the thermomechanical response of the rock mass to the extensive heating of a large volume of rock. Instrumentation was emplaced to measure stress changes, relative motion of the rock mass, and tunnel closures during three years of heating from thermally decaying heat sources, followed by a six-month cooldown period. The calculations reported here were performed using the best available input parameters, thermal and mechanical properties, and power levels which were directly measured or inferred from measurements made during the test. This report documents the results of these calculations and compares the results with selected measurements made during heating and cooling of the SFT-C.

Butkovich, T.R.; Patrick, W.C.

1986-02-01T23:59:59.000Z

269

Spent Nuclear Fuel Project Canister Storage Building Functions and Requirements  

SciTech Connect (OSTI)

In 1998, a major change in the technical strategy for managing Multi Canister Overpacks (MCO) while stored within the Canister Storage Building (CSB) occurred. The technical strategy is documented in Baseline Change Request (BCR) No. SNF-98-006, Simplified SNF Project Baseline (MCO Sealing) (FDH 1998). This BCR deleted the hot conditioning process initially adopted for the Spent Nuclear Fuel Project (SNF Project) as documented in WHC-SD-SNF-SP-005, Integrated Process Strategy for K Basins Spent Nuclear Fuel (WHC 199.5). In summary, MCOs containing Spent Nuclear Fuel (SNF) from K Basins would be placed in interim storage following processing through the Cold Vacuum Drying (CVD) facility. With this change, the needs for the Hot Conditioning System (HCS) and inerting/pressure retaining capabilities of the CSB storage tubes and the MCO Handling Machine (MHM) were eliminated. Mechanical seals will be used on the MCOs prior to transport to the CSB. Covers will be welded on the MCOs for the final seal at the CSB. Approval of BCR No. SNF-98-006, imposed the need to review and update the CSB functions and requirements baseline documented herein including changing the document title to ''Spent Nuclear Fuel Project Canister Storage Building Functions and Requirements.'' This revision aligns the functions and requirements baseline with the CSB Simplified SNF Project Baseline (MCO Sealing). This document represents the Canister Storage Building (CSB) Subproject technical baseline. It establishes the functions and requirements baseline for the implementation of the CSB Subproject. The document is organized in eight sections. Sections 1.0 Introduction and 2.0 Overview provide brief introductions to the document and the CSB Subproject. Sections 3.0 Functions, 4.0 Requirements, 5.0 Architecture, and 6.0 Interfaces provide the data described by their titles. Section 7.0 Glossary lists the acronyms and defines the terms used in this document. Section 8.0 References lists the references used for this document.

KLEM, M.J.

2000-10-18T23:59:59.000Z

270

NAC-1 cask dose rate calculations for LWR spent fuel  

SciTech Connect (OSTI)

A Nuclear Assurance Corporation nuclear fuel transport cask, NAC-1, is being considered as a transport and storage option for spent nuclear fuel located in the B-Cell of the 324 Building. The loaded casks will be shipped to the 200 East Area Interim Storage Area for dry interim storage. Several calculations were performed to assess the photon and neutron dose rates. This report describes the analytical methods, models, and results of this investigation.

CARLSON, A.B.

1999-02-24T23:59:59.000Z

271

Study on concrete cask storage of spent fuel in Japan  

SciTech Connect (OSTI)

The present report describes the status of the first year`s work of a five-year-long study on concrete cask storage of spent fuel in Japan. Firstly, the proposed study program is elaborated to clarify the position of the present work. Then, the results of the study which have been obtained so far are described and the technical issues are addressed to make the concrete cask storage viable in Japan.

Itoh, C. [Central Research Inst. of Electric Power Industry, Abiko, Chiba (Japan). Nuclear Fuel Cycle Dept.; Onodera, A.; Yamada, N. [Hitachi Zosen Corp., Tokyo (Japan). Nuclear Div.

1993-12-31T23:59:59.000Z

272

Method For Processing Spent (Trn,Zr)N Fuel  

DOE Patents [OSTI]

A new process for recycling spent nuclear fuels, in particular, mixed nitrides of transuranic elements and zirconium. The process consists of two electrorefiner cells in series configuration. A transuranic element such as plutonium is reduced at the cathode in the first cell, zirconium at the cathode in the second cell, and nitrogen-15 is released and captured for reuse to make transuranic and zirconium nitrides.

Miller, William E. (Naperville, IL); Richmann, Michael K. (Woodridge, IL)

2004-07-27T23:59:59.000Z

273

Adsorption of phenol from aqueous systems onto spent oil shale  

SciTech Connect (OSTI)

To evaluate its ability to remove phenol from aqueous solution, Jordanian {open_quotes}spent{close_quotes} oil shale, an abundant natural resource, has been used in an experimental adsorption study. Equilibrium of the system has been determined at three temperatures: 30, 40, and 55{degrees}C. The resulting experimental equilibrium isotherms are well represented by Frendlich, Langmuir, and Redlich-Peterson isotherms. The relevant parameters for these isotherms, as regressed from the experimental equilibrium data, are presented. Effects of solution pH (in the range of 3-11), in addition to effects of three inorganic salts (Kl, KCl, and NaCl), on the equilibrium isotherms were also investigated. The effects of pH in the presence of KI and NaCl were also investigated for a possible interaction between salts and solution pH. The initial concentration of phenol in the aqueous system studied ranges from 10 to 200 ppm. Experimental results show that while an acidic solution has no effect on the adsorption capacity of spent oil shale to phenol, a highly basic solution reduces its adsorbability. No sound effect was observed for the inorganic salts studied on the adsorption of phenol on spent oil shale. The experimental results show that there is no interaction between the pH of solution and the presence of salts. In spite of its ability to remove phenol, spent oil shale showed a very low equilibrium capacity (of an order of magnitude of 1 mg/g). Should the adsorption capacity of the shale be improved (by different treatment processes, such as grafting, surface conditioning), results of this study will find a direct practical implication in serving as {open_quotes}raw{close_quotes} reference data for comparison purposes.

Darwish, N.A.; Halhouli, K.A.; Al-Dhoon, N.M. [Jordan Univ. of Science and Technology, Irbid (Jordan)

1996-03-01T23:59:59.000Z

274

RED with ACK Spoofing Dept. of Electrical Engineering  

E-Print Network [OSTI]

RED with ACK Spoofing Zhong Xu Dept. of Electrical Engineering University of California, Riverside Early Detection (RED). Using simulation, we compare RED/Spoofing with Tail Drop, RED, and RED/ECN. Our results show that RED/Spoofing performs as well as RED/ECN, even though it avoids ECN's deployment problem

Molle, Mart

275

Characterization of spent fuel approved testing material: ATM-103  

SciTech Connect (OSTI)

The characterization data obtained to date are described for Approved Testing Material (ATM)-103, which is spent fuel from Assembly D101 of pressurized-water reactor Calvert Cliffs, No. 1. This report is one in a series being written by the Materials Characterization Center (MCC) at Pacific Northwest Laboratory (PNL) on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well-characterized spent fuel for testing in the US nuclear waste repository program. ATM-103 consists of 176 full-length irradiated fuel rods with rod-average burnups of about 2600 GJ/kgM (30 MWd/kgM) and less than 1% fission gas release. Characterization data include 1) as-fabricated fuel design, irradiation history, and subsequent storage and handling; 2) isotopic gamma scans; 3) fission gas analyses; 4) ceramography of the fuel and metallography of the cladding; 5) special fuels studies involving analytical transmission electron microscopy (AEM); 6) calculated nuclide inventories and radioactivities in the fuel and cladding; and 7) radiochemical analyses of the fuel and cladding. Additional analyses of the fuel are being conducted and will be included in planned revisions of this report. 10 refs., 103 figs., 63 tabs.

Guenther, R.J.; Blahnik, D.E.; Campbell, T.K.; Jenquin, U.P.; Mendel, J.E.; Thomas, L.E.; Thornhill, C.K.

1988-04-01T23:59:59.000Z

276

Characterization of spent fuel approved testing material: ATM-106  

SciTech Connect (OSTI)

The characterization data obtained to date are described for Approved Testing Material (ATM)-106 spent fuel from Assembly BT03 of pressurized-water reactor Calvert Cliffs No. 1. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well- characterized spent fuel for testing in the US Department of Energy Office of Civilian Radioactive Waste Management (OCWRM) program. ATM-106 consists of 20 full-length irradiated fuel rods with rod-average burnups of about 3700 GJ/kgM (43 MWd/kgM) and expected fission gas release of /approximately/10%. Characterization data include (1) as-fabricated fuel design, irradiation history, and subsequent storage and handling; (2) isotopic gamma scans; (3) fission gas analyses; (4) ceramography of the fuel and metallography of the cladding; (5) calculated nuclide inventories and radioactivities in the fuel and cladding; and (6) radiochemical analyses of the fuel and cladding. Additional analyses of the fuel rod are being conducted and will be included in planned revisions of this report. 12 refs., 110 figs., 81 tabs.

Guenther, R.J.; Blahnik, D.E.; Campbell, T.K.; Jenquin, U.P.; Mendel, J.E.; Thornhill, C.K.

1988-10-01T23:59:59.000Z

277

Characterization of spent fuel approved testing material---ATM-105  

SciTech Connect (OSTI)

The characterization data obtained to data are described for Approved Testing Material 105 (ATM-105), which is spent fuel from Bundles CZ346 and CZ348 of the Cooper Nuclear Power Plant, a boiling-water reactor. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory (PNL) on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well-characterized spent fuel for testing in the US Department of Energy Office of Civilian Radioactive Waste Management (OCRWM) Program. ATM-105 consists of 88 full-length irradiated fuel rods with rod-average burnups of about 2400 GJ/kgM (28 MWd/kgM) and expected fission gas release of about 1%. Characterization data include (1) descriptions of as-fabricated fuel design, irradiation history, and subsequent storage and handling; (2) isotopic gamma scans; (3) fission gas analyses; (4) ceramography of the fuel and metallography of the cladding; (5) special fuel studies involving analytical transmission electron microscopy (AEM); (6) calculated nuclide inventories and radioactivities in the fuel and cladding; and (7) radiochemical analyses of the fuel and cladding. Additional analyses of the fuel are being conducted and will be included in planned revisions of this report.

Guenther, R.J.; Blahnik, D.E.; Campbell, T.K.; Jenquin, U.P.; Mendel, J.E.; Thomas, L.E.; Thornhill, C.K.

1991-12-01T23:59:59.000Z

278

Characterization of spent fuel approved testing material--ATM-104  

SciTech Connect (OSTI)

The characterization data obtained to date are described for Approved Testing Material 104 (ATM-104), which is spent fuel from Assembly DO47 of the Calvert Cliffs Nuclear Power Plant (Unit 1), a pressurized-water reactor. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory (PNL) on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well-characterized spent fuel for testing in the US Department of Energy Office of Civilian Radioactive Waste Management (OCRWM) Program. ATM-104 consists of 128 full-length irradiated fuel rods with rod-average burnups of about 42 MWd/kgM and expected fission gas release of about 1%. A variety of analyses were performed to investigate cladding characteristics, radionuclide inventory, and redistribution of fission products. Characterization data include (1) fabricated fuel design, irradiation history, and subsequent storage and handling history; (2) isotopic gamma scans; (3) fission gas analyses; (4) ceramography of the fuel and metallography of the cladding; (5) special fuel studies involving analytical transmission electron microscopy (AEM) and electron probe microanalyses (EPMA); (6) calculated nuclide inventories and radioactivities in the fuel and cladding; and (7) radiochemical analyses of the fuel and cladding.

Guenther, R.J.; Blahnik, D.E.; Jenquin, U.P.; Mendel, J.E.; Thomas, L.E.; Thornhill, C.K.

1991-12-01T23:59:59.000Z

279

Standard guide for drying behavior of spent nuclear fuel  

E-Print Network [OSTI]

1.1 This guide is organized to discuss the three major components of significance in the drying behavior of spent nuclear fuel: evaluating the need for drying, drying spent nuclear fuel, and confirmation of adequate dryness. 1.1.1 The guide addresses drying methods and their limitations in drying spent nuclear fuels that have been in storage at water pools. The guide discusses sources and forms of water that remain in SNF, its container, or both, after the drying process and discusses the importance and potential effects they may have on fuel integrity, and container materials. The effects of residual water are discussed mechanistically as a function of the container thermal and radiological environment to provide guidance on situations that may require extraordinary drying methods, specialized handling, or other treatments. 1.1.2 The basic issue in drying is to determine how dry the SNF must be in order to prevent issues with fuel retrievability, container pressurization, or container corrosion. Adequate d...

American Society for Testing and Materials. Philadelphia

2008-01-01T23:59:59.000Z

280

Thermoelectric powered wireless sensors for spent fuel monitoring  

SciTech Connect (OSTI)

This paper describes using thermoelectric generators to power wireless sensors to monitor spent nuclear fuel during dry-cask storage. OrigenArp was used to determine the decay heat of the spent fuel at different times during the service life of the dry-cask. The Engineering Equation Solver computer program modeled the temperatures inside the spent fuel storage facility during its service life. The temperature distribution in a thermoelectric generator and heat sink was calculated using the computer program Finite Element Heat Transfer. From these temperature distributions the power produced by the thermoelectric generator was determined as a function of the service life of the dry-cask. In addition, an estimation of the path loss experienced by the wireless signal can be made based on materials and thickness of the structure. Once the path loss is known, the transmission power and thermoelectric generator power requirements can be determined. This analysis estimates that a thermoelectric generator can produce enough power for a sensor to function and transmit data from inside the dry-cask throughout its service life. (authors)

Carstens, T.; Corradini, M.; Blanchard, J. [Dept. of Engineering Physics, Univ. of Wisconsin-Madison, Madison, WI 53706 (United States); Ma, Z. [Dept. of Electrical and Computer Engineering, Univ. of Wisconsin-Madison, Madison, WI 53706 (United States)

2011-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Comparative analysis of LWR and FBR spent fuels for nuclear forensics evaluation  

SciTech Connect (OSTI)

Some interesting issues are attributed to nuclide compositions of spent fuels from thermal reactors as well as fast reactors such as a potential to reuse as recycled fuel, and a possible capability to be manage as a fuel for destructive devices. In addition, analysis on nuclear forensics which is related to spent fuel compositions becomes one of the interesting topics to evaluate the origin and the composition of spent fuels from the spent fuel foot-prints. Spent fuel compositions of different fuel types give some typical spent fuel foot prints and can be estimated the origin of source of those spent fuel compositions. Some technics or methods have been developing based on some science and technological capability including experimental and modeling or theoretical aspects of analyses. Some foot-print of nuclear forensics will identify the typical information of spent fuel compositions such as enrichment information, burnup or irradiation time, reactor types as well as the cooling time which is related to the age of spent fuels. This paper intends to evaluate the typical spent fuel compositions of light water (LWR) and fast breeder reactors (FBR) from the view point of some foot prints of nuclear forensics. An established depletion code of ORIGEN is adopted to analyze LWR spent fuel (SF) for several burnup constants and decay times. For analyzing some spent fuel compositions of FBR, some coupling codes such as SLAROM code, JOINT and CITATION codes including JFS-3-J-3.2R as nuclear data library have been adopted. Enriched U-235 fuel composition of oxide type is used for fresh fuel of LWR and a mixed oxide fuel (MOX) for FBR fresh fuel. Those MOX fuels of FBR come from the spent fuels of LWR. Some typical spent fuels from both LWR and FBR will be compared to distinguish some typical foot-prints of SF based on nuclear forensic analysis.

Permana, Sidik; Suzuki, Mitsutoshi; Su'ud, Zaki [Department of Science and Technology for Nuclear Material Management (STNM), Japan Atomic Energy Agency (JAEA), 2-4 Shirane, Shirakata, Tokai Mura, Naka-gun, Ibaraki 319-1195 Nuclear Physics and Bio (Indonesia); Department of Science and Technology for Nuclear Material Management (STNM), Japan Atomic Energy Agency (JAEA), 2-4 Shirane, Shirakata, Tokai Mura, Naka-gun, Ibaraki 319-1195 (Japan); Nuclear Physics and Bio Physics Research Group, Department of Physics, Bandung Institute of Technology, Gedung Fisika, Jl. Ganesha 10, Bandung 40132 (Indonesia)

2012-06-06T23:59:59.000Z

282

An approach to determine a defensible spent fuel ratio.  

SciTech Connect (OSTI)

Sabotage of spent nuclear fuel casks remains a concern nearly forty years after attacks against shipment casks were first analyzed and has a renewed relevance in the post-9/11 environment. A limited number of full-scale tests and supporting efforts using surrogate materials, typically depleted uranium dioxide (DUO2), have been conducted in the interim to more definitively determine the source term from these postulated events. In all the previous studies, the postulated attack of greatest interest was by a conical shape charge (CSC) that focuses the explosive energy much more efficiently than bulk explosives. However, the validity of these large-scale results remain in question due to the lack of a defensible Spent Fuel Ratio (SFR), defined as the amount of respirable aerosol generated by an attack on a mass of spent fuel compared to that of an otherwise identical DUO2 surrogate. Previous attempts to define the SFR have resulted in estimates ranging from 0.42 to 12 and include suboptimal experimental techniques and data comparisons. Different researchers have suggested using SFR values of 3 to 5.6. Sound technical arguments exist that the SFR does not exceed a value of unity. A defensible determination of the SFR in this lower range would greatly reduce the calculated risk associated with the transport and dry storage of spent nuclear fuel. Currently, Oak Ridge National Laboratory (ORNL) is in possession of several samples of spent nuclear fuel (SNF) that were used in the original SFR studies in the 1980's and were intended for use in a modern effort at Sandia National Laboratories (SNL) in the 2000's. A portion of these samples are being used for a variety of research efforts. However, the entirety of SNF samples at ORNL is scheduled for disposition at the Waste Isolation Pilot Plant (WIPP) by approximately the end of 2015. If a defensible SFR is to be determined for use in storage and transportation security analyses, the need to begin this effort is urgent in order to secure the only known available SNF samples with a clearly defined path to disposal.

Durbin, Samuel G.; Lindgren, Eric Richard

2014-03-01T23:59:59.000Z

283

EA-1692: Red River Environmental Products, LLC Activated Carbon...  

Broader source: Energy.gov (indexed) [DOE]

2: Red River Environmental Products, LLC Activated Carbon Manufacturing Facility, Red River Parish, LA EA-1692: Red River Environmental Products, LLC Activated Carbon Manufacturing...

284

Red Band Needle Blight TERMS OF REFERENCE  

E-Print Network [OSTI]

Red Band Needle Blight TERMS OF REFERENCE Purpose 1. The Programme Board has been formed to have an overview of the administration and science of Red Band Needle Blight (RBNB), to underpin decisions made

285

EIS-0203: Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs  

Broader source: Energy.gov [DOE]

Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs

286

3, 383408, 2006 The northern Red  

E-Print Network [OSTI]

BGD 3, 383­408, 2006 The northern Red Sea ­ A system in balance? C. H¨ase et al. Title Page in balance? ­ Implications of deep vertical mixing for the nitrogen budget in the northern Red Sea, including The northern Red Sea ­ A system in balance? C. H¨ase et al. Title Page Abstract Introduction Conclusions

Paris-Sud XI, Université de

287

Tuning RED for Web Traffic* Mikkel Christiansen,**  

E-Print Network [OSTI]

139 Tuning RED for Web Traffic* Mikkel Christiansen,** Kevin Jeffay, David Ott, F. Donelson Smith http://www.cs.unc.edu/Research/dirt Abstract We study the effects of RED on the performance of Web -- response time for HTTP request-response pairs. We empirically evaluate RED across a range of parameter

Jeffay, Kevin

288

Conservation Plan for Red Squirrels in Wales  

E-Print Network [OSTI]

#12;Conservation Plan for Red Squirrels in Wales Meeting the challenge to keep reds in Wales to enable effective red squir- rel conservation and grey squirrel management in Wales. The Wales Squirrel squirrel conservation and grey squirrel management in Wales. The Forum and Partnership are currently

289

Italian Herb Red Potato Salad Ingredients  

E-Print Network [OSTI]

Italian Herb Red Potato Salad Ingredients: 1 1/2 pounds red potatoes 1 green pepper 1 red onion 1/4 teaspoon garlic powder 1/4 teaspoon ground black pepper Directions 1. Wash potatoes, and cut into quarters. Place potatoes in sauce pan with cool water, cover and bring to a boil, turn to low and cook until

Liskiewicz, Maciej

290

Far-Red Fluorescent Protein Excitable with Red Lasers for Flow Cytometry and Superresolution STED Nanoscopy  

E-Print Network [OSTI]

Far-Red Fluorescent Protein Excitable with Red Lasers for Flow Cytometry and Superresolution STED Biology, Yale University School of Medicine, New Haven, Connecticut ABSTRACT Far-red fluorescent proteins are required for deep-tissue and whole-animal imaging and multicolor labeling in the red wavelength range

Verkhusha, Vladislav V.

291

Adaptive RED: An Algorithm for Increasing the Robustness of RED's Active Queue Management  

E-Print Network [OSTI]

Adaptive RED: An Algorithm for Increasing the Robustness of RED's Active Queue Management Sally, under submission Abstract The RED active queue management algorithm allows net- work operators is quite sensitive to the level of congestion and to the RED parameter settings, and is therefore not pre

Floyd, Sally

292

Red Band Needle Blight Programme Red Band Needle Blight of Pine Programme Group  

E-Print Network [OSTI]

Red Band Needle Blight Programme Group Red Band Needle Blight of Pine Programme Group Minutes Support Welcome and introduction 1. Jim thanked everyone for attending the first meeting of the Red Band and that the private 1 | Paper 1 - Minutes | Debbie Erskine | 23/01/2009 #12;Red Band Needle Blight Programme Group

293

Adaptive RED: An Algorithm for Increasing the Robustness of RED's Active Queue Management  

E-Print Network [OSTI]

Adaptive RED: An Algorithm for Increasing the Robustness of RED's Active Queue Management Sally, under submission Abstract The RED active queue management algorithm allows net­ work operators is quite sensitive to the level of congestion and to the RED parameter settings, and is therefore not pre

Floyd, Sally

294

Equipment Design and Cost Estimation for Small Modular Biomass Systems, Synthesis Gas Cleanup, and Oxygen Separation Equipment; Task 2: Gas Cleanup Design and Cost Estimates -- Black Liquor Gasification  

SciTech Connect (OSTI)

As part of Task 2, Gas Cleanup and Cost Estimates, Nexant investigated the appropriate process scheme for removal of acid gases from black liquor-derived syngas for use in both power and liquid fuels synthesis. Two 3,200 metric tonne per day gasification schemes, both low-temperature/low-pressure (1100 deg F, 40 psi) and high-temperature/high-pressure (1800 deg F, 500 psi) were used for syngas production. Initial syngas conditions from each of the gasifiers was provided to the team by the National Renewable Energy Laboratory and Princeton University. Nexant was the prime contractor and principal investigator during this task; technical assistance was provided by both GTI and Emery Energy.

Nexant Inc.

2006-05-01T23:59:59.000Z

295

Proliferation Vulnerability Red Team report  

SciTech Connect (OSTI)

This report is the product of a four-month independent technical assessment of potential proliferation vulnerabilities associated with the plutonium disposition alternatives currently under review by DOE/MD. The scope of this MD-chartered/Sandia-led study was limited to technical considerations that could reduce proliferation resistance during various stages of the disposition processes below the Stored Weapon/Spent Fuel standards. Both overt and covert threats from host nation and unauthorized parties were considered. The results of this study will be integrated with complementary work by others into an overall Nonproliferation and Arms Control Assessment in support of a Secretarial Record of Decision later this year for disposition of surplus U.S. weapons plutonium.

Hinton, J.P.; Barnard, R.W.; Bennett, D.E. [and others

1996-10-01T23:59:59.000Z

296

Corn steep liquor and fermented ammoniated condensed whey as protein sources for lactating cows and yearling heifers grazing winter native range  

SciTech Connect (OSTI)

Corn steep liquor (CSL) and fermented ammoniated condensed whey (FACW) were compared to cottonseed meal (CSM) as protein sources for wintering 61 lactating first-calf Hereford heifers and 32 yearling Hereford heifers on native range. Cattle were allotted by weight and individually fed 6 days per week for 12 weeks one of four protein treatments: negative control (NC), positive control (PC), CSL and FACW to provide .7, 1.5, .15 and 1.5 lb crude protein (CP) per day, respectively, to the lacating heifers and .2, .4, .4 and .4lb cP per day, respectively, to the yearling heifers. CMS was supplied in the CSL and FACW treatments at the same level as in the negative control. Lactating heifers fed the NC lost more (P less than .005) weight and body condition (120 lb and 1.6 units) than those fed the PC (45.8 lb and .9 units). Weight and condition losses were similar (P more than .05) for lactating heifers fed PC, CSL and FACW. Yearling heifers fed the NC lost more (P less than .005) weight than those fed the PC (49.4 vs 10.6 lb). Yearling heifers fed CSL and FACW gained more (P less than .005) weight than those fed the PC (17.6 and 9.3 vs - 10.6 lb). Feeding CSL resulted in signficantly lower rumen pH, lower ruminal acetate and higher ruminal butyrate, isovalerate and caproate levels than did feeding either control. Supplementing with FACW produced significantly lower rumen pH, higher rumen ammonia and soluble carbohydrate levels, lower ruminal acetate, and higher ruminal propionate and butyrate concentrations than did either control supplement. Corn steep liquor and FDCW appear to be effective protein sources for cows and heifers grazing winter native range.

Wagner, J.J.; Lusby, K.S.; Horn, G.W.; Dvorak, M.J.

1982-06-01T23:59:59.000Z

297

Black Liquor Combustion Validated Recovery Boiler Modeling, Final Year Report, Volume 2: Appendix I, Section 5, and Appendix II, Section 1  

SciTech Connect (OSTI)

This project was initiated in October 1990 with the objective of developing and validating a new computer model of a recovery boiler furnace using a computational fluid dynamics (CFD) code specifically tailored to the requirements for solving recovery boiler flows, and using improved submodels for black liquor combustion based on continued laboratory fundamental studies. Many of these objectives were accomplished at the end of the first five years and documented in a comprehensive report on that work (DOE/CE/40936-T3, 1996). A critical review of recovery boiler modeling, carried out in 1995, concluded that further enhancements of the model were needed to make reliable predictions of key output variables. In addition, there was a need for sufficient understanding of fouling and plugging processes to allow model outputs to be interpreted in terms of the effect on plugging and fouling. As a result, the project was restructured and reinitiated at the end of October 1995, and was completed in June 1997. The entire project is now complete and this report summarizes all of the work done on the project since it was restructured. The key tasks to be accomplished under the restructured project were to (1) Complete the development of enhanced furnace models that have the capability to accurately predict carryover, emissions behavior, dust concentrations, gas temperatures, and wall heat fluxes; (2) Validate the enhanced furnace models, so that users can have confidence in the results; (3) Obtain fundamental information on aerosol formation, deposition, and hardening so as to develop the knowledge base needed to relate furnace model outputs to plugging and fouling in the convective sections of the boiler; and (4) Facilitate the transfer of codes, black liquor submodels, and fundamental knowledge to the U.S. kraft pulp industry.

T.M. Grace, W.J. Frederick, M. Salcudean, R.A. Wessel

1998-08-01T23:59:59.000Z

298

Black Liquor Combustion Validated Recovery Boiler Modeling, Final Year Report, Volume 1: Main Text and Appendix I, Sections 1-4  

SciTech Connect (OSTI)

This project was initiated in October 1990 with the objective of developing and validating a new computer model of a recovery boiler furnace using a computational fluid dynamics (CFD) code specifically tailored to the requirements for solving recovery boiler flows, and using improved submodels for black liquor combustion based on continued laboratory fundamental studies. Many of these objectives were accomplished at the end of the first five years and documented in a comprehensive report on that work (DOE/CE/40936-T3, 1996). A critical review of recovery boiler modeling, carried out in 1995, concluded that further enhancements of the model were needed to make reliable predictions of key output variables. In addition, there was a need for sufficient understanding of fouling and plugging processes to allow model outputs to be interpreted in terms of the effect on plugging and fouling. As a result, the project was restructured and reinitiated at the end of October 1995, and was completed in June 1997. The entire project is now complete and this report summarizes all of the work done on the project since it was restructured. The key tasks to be accomplished under the restructured project were to (1) Complete the development of enhanced furnace models that have the capability to accurately predict carryover, emissions behavior, dust concentrations, gas temperatures, and wall heat fluxes; (2) Validate the enhanced furnace models, so that users can have confidence in the results; (3) Obtain fundamental information on aerosol formation, deposition, and hardening so as to develop the knowledge base needed to relate furnace model outputs to plugging and fouling in the convective sections of the boiler. Facilitate the transfer of codes, black liquor submodels, and fundamental knowledge to the U.S. kraft pulp industry.

T.M. Grace, W.J. Frederick, M. Salcudean, R.A. Wessel

1998-08-01T23:59:59.000Z

299

Red-black Trees To know what a red-black tree is (10.1).  

E-Print Network [OSTI]

809 CHAPTER 10 Red-black Trees Objectives · To know what a red-black tree is (§10.1). · To convert a red-black tree to a 2-4 tree and vice versa (§10.2). · To design the RBTree class that extends the BinaryTree class (§10.3). · To insert an element in a red-black tree and resolve the double red problem

Liang, Y. Daniel

300

A novel process for the treatment of spent potlining  

SciTech Connect (OSTI)

A description of a new process for the treatment of spent potlining (SPL) is presented in this paper together with a comparison between laboratory results and those obtained from a 100kg demonstration plant. The process uses a series of aqueous leaching steps, conducted at low temperature, to extract cyanide from SPL and recover the fluoride values as smelter grade AlF{sup 3} or acid grade CaF{sup 2}. The final carbonaceous residue contains the refractory compounds corundum and sodium beta-aluminate and TCLP tests demonstrate that it meets environmental requirements for land filling. 2 refs., 2 figs., 5 tabs.

Besida, J.; Pong, T.K.; Adrien, R.J. [Univ. of Melbourne, Parkville (Australia)] [and others

1996-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

A process for treatment and recovery of spent potliner (SPL)  

SciTech Connect (OSTI)

Spent potliner (SPL) is classified as a hazardous waste as it contains cyanides and high levels of fluorides. This paper describes a novel process for the conversion of SPL at near ambient temperatures for the recovery of useful products and a benign residue. The initial treatment of crushed SPL removes over 90% of the cyanide and a large percentage of the fluoride. By appropriate selection of the chemical species and wash conditions aluminum fluoride and other fluorides are effectively recovered in subsequent stages. After this treatment by a series of chemical washes the residue produced is a carbonaceous material containing only carbon and brick fragments, i.e. refractory aluminum compounds.

Adrien, R.J.; Besida, J.; Pong, T.K.; O`Donnell, T.A.; Wood, D.G.; Covey, G.H. [Univ. of Melbourne, Parkville, Victoria (Australia). Dept. of Chemical Engineering; Giansiracusa, J.J.; Price, D.E. [DEPCO-TRH Pty. Ltd., Melbourne, Victoria (Australia)

1996-10-01T23:59:59.000Z

302

APPLICATIONS OF CURRENT TECHNOLOGY FOR CONTINUOUS MONITORING OF SPENT FUEL  

SciTech Connect (OSTI)

Advancements in technology have opened many opportunities to improve upon the current infrastructure surrounding the nuclear fuel cycle. Embedded devices, very small sensors, and wireless technology can be applied to Security, Safety, and Nonproliferation of Spent Nuclear Fuel. Security, separate of current video monitoring systems, can be improved by integrating current wireless technology with a variety of sensors including motion detection, altimeter, accelerometer, and a tagging system. By continually monitoring these sensors, thresholds can be set to sense deviations from nominal values. Then alarms or notifications can be activated as needed. Safety can be improved in several ways. First, human exposure to ionizing radiation can be reduced by using a wireless sensor package on each spent fuel cask to monitor radiation, temperature, humidity, etc. Since the sensor data is monitored remotely operator stay-time is decreased and distance from the spent fuel increased, so the overall radiation exposure is reduced as compared to visual inspections. The second improvement is the ability to monitor continuously rather than periodically. If changes occur to the material, alarm thresholds could be set and notifications made to provide advanced notice of negative data trends. These sensor packages could also record data to be used for scientific evaluation and studies to improve transportation and storage safety. Nonproliferation can be improved for spent fuel transportation and storage by designing an integrated tag that uses current infrastructure for reporting and in an event; tracking can be accomplished using the Iridium satellite system. This technology is similar to GPS but with higher signal strength and penetration power, but lower accuracy. A sensor package can integrate all or some of the above depending on the transportation and storage requirements and regulations. A sensor package can be developed using off the shelf technology and applying it to each specific need. There are products on the market for smart meters, industrial lighting control and home automation that can be applied to the Back End Fuel Cycle. With a little integration and innovation a cost effective solution is achievable.

Drayer, R.

2013-06-09T23:59:59.000Z

303

Corrosion of Spent Nuclear Fuel: The Long-Term Assessment  

SciTech Connect (OSTI)

Spent nuclear fuel, essentially U{sub 2}, accounts for over 95% of the total radioactivity of all of the radioactive wastes in the United States that require disposal, disposition or remediation. The UO{sub 2} in SNF is not stable under oxiding conditions and may also be altered under reducing conditions. The alteration of SNF results in the formation of new uranium phases that can cause the release or retardation of actinide and fission product radionuclides. Over the long term, and depending on the extent to which the secondary uranium phases incorporate fission products and actinides, these alteration phases become the near-field source term.

Rodney C. Ewing

2004-10-07T23:59:59.000Z

304

Spent nuclear fuel storage -- Performance tests and demonstrations  

SciTech Connect (OSTI)

This report summarizes the results of heat transfer and shielding performance tests and demonstrations conducted from 1983 through 1992 by or in cooperation with the US Department of Energy (DOE), Office of Commercial Radioactive Waste Management (OCRWM). The performance tests consisted of 6 to 14 runs involving one or two loadings, usually three backfill environments (helium, nitrogen, and vacuum backfills), and one or two storage system orientations. A description of the test plan, spent fuel load patterns, results from temperature and dose rate measurements, and fuel integrity evaluations are contained within the report.

McKinnon, M.A.; DeLoach, V.A.

1993-04-01T23:59:59.000Z

305

Extending dry storage of spent LWR fuel for 100 years.  

SciTech Connect (OSTI)

Because of delays in closing the back end of the fuel cycle in the U.S., there is a need to extend dry inert storage of spent fuel beyond its originally anticipated 20-year duration. Many of the methodologies developed to support initial licensing for 20-year storage should be able to support the longer storage periods envisioned. This paper evaluates the applicability of existing information and methodologies to support dry storage up to 100 years. The thrust of the analysis is the potential behavior of the spent fuel. In the USA, the criteria for dry storage of LWR spent fuel are delineated in 10 CFR 72 [1]. The criteria fall into four general categories: maintain subcriticality, prevent the release of radioactive material above acceptable limits, ensure that radiation rates and doses do not exceed acceptable levels, and maintain retrievability of the stored radioactive material. These criteria need to be considered for normal, off-normal, and postulated accident conditions. The initial safety analysis report submitted for licensing evaluated the fuel's ability to meet the requirements for 20 years. It is not the intent to repeat these calculations, but to look at expected behavior over the additional 80 years, during which the temperatures and radiation fields are lower. During the first 20 years, the properties of the components may change because of elevated temperatures, presence of moisture, effects of radiation, etc. During normal storage in an inert atmosphere, there is potential for the cladding mechanical properties to change due to annealing or interaction with cask materials. The emissivity of the cladding could also change due to storage conditions. If there is air leakage into the cask, additional degradation could occur through oxidation in breached rods, which could lead to additional fission gas release and enlargement of cladding breaches. Air in-leakage could also affect cover gas conductivity, cladding oxidation, emissivity changes, and excessive creep and mechanical property changes. Postulated accident scenarios would be the same for 20-year or 100-year storage, because they are mostly governed by operational or outside events, and not by the cask or fuel. Analyses of accident scenarios during extended dry storage could be impacted by fuel and cask changes that would result from the extended period of storage. Overall, the results of this work indicate that, based on fuel behavior, spent fuel at burnups below {approximately}45 GWd/MTU can be dry stored for 100 years. Long-term storage of higher burnup fuel or fuels with newer cladding will require the determination of temperature limits based on evaluation of stress-driven degradation mechanisms of the cladding.

Einziger, R. E.

1998-12-16T23:59:59.000Z

306

Smelting Associated with the Advanced Spent Fuel Conditioning Process  

SciTech Connect (OSTI)

The smelting process associated with the advanced spent fuel conditioning process (ACP) of Korea Atomic Energy Research Institute was studied by using surrogate materials. Considering the vaporization behaviors of input materials, the operation procedure of smelting was set up as (1) removal of residual salts, (2) melting of metal powder, and (3) removal of dross from a metal ingot. The behaviors of porous MgO crucible during smelting were tested and the chemical stability of MgO in the salt-being atmosphere was confirmed.

Hur, J-M.; Jeong, M-S.; Lee, W-K.; Cho, S-H.; Seo, C-S.; Park, S-W.

2004-10-03T23:59:59.000Z

307

Closure mechanism and method for spent nuclear fuel canisters  

DOE Patents [OSTI]

A canister is provided for storing, transporting, and/or disposing of spent nuclear fuel. The canister includes a canister shell, a top shield plug disposed within the canister, and a leak-tight closure arrangement. The closure arrangement includes a shear ring which forms a containment boundary of the canister, and which is welded to the canister shell and top shield plug. An outer seal plate, forming an outer seal, is disposed above the shear ring and is welded to the shield plug and the canister.

Doman, Marvin J. (Monroeville, PA)

2004-11-23T23:59:59.000Z

308

Spent Fuel Transportation Risk Assessment | Department of Energy  

Office of Environmental Management (EM)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May Jun Jul(Summary) "of Energy Power.pdf11-161-LNGInternational Energy AgencyImpactSouthDepartment of09-01Special Topics inSpent

309

Spent Fuel Analyses for Nuclear Safeguards | ornl.gov  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas ConchasPassiveSubmittedStatus Tom Fletcher,Future |CarlosSpeakersSpectroscopySpencer R.Spent

310

Instrumented, Shielded Test Canister System for Evaluation of Spent Nuclear Fuel in Dry Storage  

SciTech Connect (OSTI)

This document describes the development of an instrumented, shielded test canister system to store and monitor aluminum-based spent nuclear duel under dry storage conditions.

Sindelar, R.L.

1999-10-21T23:59:59.000Z

311

POTENTIAL USES OF SPENT SHALE IN THE TREATMENT OF OIL SHALE RETORT WATERS  

E-Print Network [OSTI]

study of retorted oil shale," Lawrence Livermore Laboratoryb) using columns of spent shale. REFERENCES Burnham, Alankinetics between and oil-shale residual carbon. 1. co Effect

Fox, J.P.

2013-01-01T23:59:59.000Z

312

Brittle Failure Design Criteria for Ductile Cast Iron Spent-Fuel  

Office of Scientific and Technical Information (OSTI)

for Ductile and Brittle Failure Design Criteria for Ductile Cast Iron Spent-Fuel Shipping Containers This report was prepared as an account of work sponsored by an...

313

E-Print Network 3.0 - advanced spent fuel Sample Search Results  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

facilities should have more advanced technical monitoring... of the cycle to extract fis- sile material from the spent fuel removed from reactors. Although a complete... of...

314

Dose Rates for Various Loading Patterns of Spent Fuel Assemblies in a Dry Cask  

SciTech Connect (OSTI)

Shielding calculations were performed to assess the impact of loading various combinations of spent fuel on dose rates and fuel temperature in a dry storage cask.

Jenquin, Urban P. (BATTELLE (PACIFIC NW LAB))

2001-01-01T23:59:59.000Z

315

Effects of Acid Additives on Spent Acid Flowback through Carbonate Cores  

E-Print Network [OSTI]

Limestone and the non-emulsifying agent M-NEA the worst for Texas Cream Chalk for spent acid recovery after gas flowback....

Nasir, Ehsaan Ahmad

2012-07-16T23:59:59.000Z

316

Report to Congress on Plan for Interim Storage of Spent Nuclear...  

Broader source: Energy.gov (indexed) [DOE]

Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from Decommissioned Reactors More Documents & Publications Information Request, "THE REPORT TO THE PRESIDENT...

317

Fracture behavior of high-burnup spent-fuel cladding  

SciTech Connect (OSTI)

PCI-like, brittle-type failures, characterized by pseudocleavage-plus-fluting features in the fracture surface, branching cracks, and small diametral strain, were observed to occur at 292 to 325/sup 0/C in some batches of spent power-reactor fuel-cladding tubes under internal gas-pressurization and expanding-mandrel loading conditions in which the tests were not influenced by fission product simulants. Fractographic characteristics per se do not provide evidence for a PCI failure mechanism but should be deemed only as cooroborative in nature. Evaluation of TEM thin-foil specimens, obtained from regions adjacent to the brittle-type fracture sites, characteristically revealed extensive amounts of Zr/sub 3/O precipitates and a lack of slip dislocations. The precipitation of the Zr/sub 3/O phase appears to be enhanced by a high density of irradiation-induced defects. The brittle-type failure produced in the spent-fuel cladding tubes appears to be associated with segregation of oxygen to dislocation substructures and irradiation-induced defects, which leads to the formation of an ordered zirconium-oxygen phase of Zr/sub 3/O, an immobilization of dislocations, and minimal plastic deformation in the cladding material.

Chung, H.M.; Yaggee, F.L.; Kassner, T.F.

1983-10-01T23:59:59.000Z

318

Delayed Gamma-Ray Spectroscopy for Spent Nuclear Fuel Assay  

SciTech Connect (OSTI)

High-energy, beta-delayed gamma-ray spectroscopy is investigated as a non-destructive assay technique for the determination of plutonium mass in spent nuclear fuel. This approach exploits the unique isotope-specific signatures contained in the delayed gamma-ray emission spectra detected following active interrogation with an external neutron source. A high fidelity modeling approach is described that couples radiation transport, analytical decay/depletion, and a newly developed gamma-ray emission source reconstruction code. Initially simulated and analyzed was a one-pass delayed gamma-ray assay that focused on the long-lived signatures. Also presented are the results of an independent study that investigated pulsed mode measurements, to capture the more isotope-specific, short-lived signatures. Initial modeling results outlined in this paper suggest that delayed gamma-ray assay of spent nuclear fuel assemblies can be accomplished with a neutron generator of sufficient strength and currently available gamma-ray detectors.

Campbell, Luke W.; Hunt, Alan W.; Ludewigt, Bernhard A.; Mozin, Vladimir V.

2012-04-01T23:59:59.000Z

319

Dry oxidation and fracture of LWR spent fuels  

SciTech Connect (OSTI)

This report evaluates the characteristics of oxidation and fracture of light-water reactor (LWR) spent fuel in dry air. It also discusses their effects on radionuclide releases in the anticipated high-level waste repository environment. A sphere model may describe diffusion-limited formation of lower oxides, such as U{sub 4}O{sub 9}, in the oxidation of the spent fuel (SF) matrix. Detrimental higher oxides, such as U{sub 3}O{sub 8}, may not form at temperatures below a threshold temperature. The nucleation process suggests that a threshold temperature exists. The calculated results regarding fracture properties of the SF matrix agree with experimental observations. Oxidation and fracture of Zircaloy may not be significant under anticipated conditions. Under saturated or unsaturated aqueous conditions, oxidation of the SF matrix is believed to increase the releases of Pu-(239+240), Am-(241+243), C-14, Tc-99, I-129, and Cs-135. Under dry conditions, I-129 releases are likely to be small, unlike C-14, in lower oxides; Cl-36, Tc-99, I-129, and Cs-135 may be released fast in higher oxides. 79 refs.

Ahn, T.M.

1996-11-01T23:59:59.000Z

320

Spent nuclear fuel recycling with plasma reduction and etching  

DOE Patents [OSTI]

A method of extracting uranium from spent nuclear fuel (SNF) particles is disclosed. Spent nuclear fuel (SNF) (containing oxides of uranium, oxides of fission products (FP) and oxides of transuranic (TRU) elements (including plutonium)) are subjected to a hydrogen plasma and a fluorine plasma. The hydrogen plasma reduces the uranium and plutonium oxides from their oxide state. The fluorine plasma etches the SNF metals to form UF6 and PuF4. During subjection of the SNF particles to the fluorine plasma, the temperature is maintained in the range of 1200-2000 deg K to: a) allow any PuF6 (gas) that is formed to decompose back to PuF4 (solid), and b) to maintain stability of the UF6. Uranium (in the form of gaseous UF6) is easily extracted and separated from the plutonium (in the form of solid PuF4). The use of plasmas instead of high temperature reactors or flames mitigates the high temperature corrosive atmosphere and the production of PuF6 (as a final product). Use of plasmas provide faster reaction rates, greater control over the individual electron and ion temperatures, and allow the use of CF4 or NF3 as the fluorine sources instead of F2 or HF.

Kim, Yong Ho

2012-06-05T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
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321

Natural convection heat transfer within horizontal spent nuclear fuel assemblies  

SciTech Connect (OSTI)

Natural convection heat transfer is experimentally investigated in an enclosed horizontal rod bundle, which characterizes a spent nuclear fuel assembly during dry storage and/or transport conditions. The basic test section consists of a square array of sixty-four stainless steel tubular heaters enclosed within a water-cooled rectangular copper heat exchanger. The heaters are supplied with a uniform power generation per unit length while the surrounding enclosure is maintained at a uniform temperature. The test section resides within a vacuum/pressure chamber in order to subject the assembly to a range of pressure statepoints and various backfill gases. The objective of this experimental study is to obtain convection correlations which can be used in order to easily incorporate convective effects into analytical models of horizontal spent fuel systems, and also to investigate the physical nature of natural convection in enclosed horizontal rod bundles in general. The resulting data consist of: (1) measured temperatures within the assembly as a function of power, pressure, and backfill gas; (2) the relative radiative contribution for the range of observed temperatures; (3) correlations of convective Nusselt number and Rayleigh number for the rod bundle as a whole; and (4) correlations of convective Nusselt number as a function of Rayleigh number for individual rods within the array.

Canaan, R.E.

1995-12-01T23:59:59.000Z

322

Spent Fuel Storage Operational Experience With Increased Crud Activities  

SciTech Connect (OSTI)

A significant part of the electricity production in Hungary is provided by 4 units of VVER 440 nuclear reactors at the Paks Nuclear Power Plant. Interim dry storage of the spent fuel assemblies that are generated during the operation of the reactors is provided in a Modular Vault Dry Storage (MVDS) facility that is located in the immediate vicinity of the Paks Nuclear Power Plant. The storage capacity of the MVDS is being continuously extended in accordance with spent the fuel production rate from the four reactors. An accident occurred at unit 2 of the Paks Nuclear Power Plant in 2003, when thirty irradiated fuel assemblies were damaged during a cleaning process. The fuel assemblies were not inside the reactor at the time of the accident, but in a separate tank within the adjacent fuel decay pool. As a result of this accident, contamination from the badly damaged fuel assemblies spread to the decay pool water and also became deposited onto the surface of (hermetic) spent fuel assemblies within the decay pool. Therefore, it was necessary to review the design basis of the MVDS and assess the effects of taking the surface contaminated spent fuel assemblies into dry storage. The contaminated hermetic assemblies were transferred from the unit 2 pool to the interim storage facility in the period between 2005 and 2007. Continuous inspection and measurement was carried out during the transfer of these fuel assemblies. On the basis of the design assessments and measurement of the results during the fuel transfer, it was shown that radiological activity values increased due to the consequences of the accident but that these levels did not compromise the release and radiation dose limits for the storage facility. The aim of this paper is to show the effect on the operation of the MVDS interim storage facility as a result of the increased activity values due to the accident that occurred in 2003, as well as to describe the measurements that were taken, and their results and experience gained. In summary: On the basis of the design assessments and measurement of the results during the fuel transfer operations, it was shown that radiological activity values increased due to the consequences of the 2003 accident but that these levels did not compromise the release and dose limits for the fuel storage facility. In the environment there was no measurable radioactivity as a result of the operation of the Paks ISFSI. The exposure of the surrounding population was calculated on measured releases and meteorological data. The calculations show negligible doses until 2004. Due to the increased surface contamination on the spent fuel assemblies the dose rate increased almost 5 times compared to the least annual value, but still less then 0.01 percent of the allowed dose restriction. (authors)

Barnabas, I. [Public Agency for Radioactive Waste, Management (PURAM) (Hungary); Eigner, T. [Paks NPP (Hungary); Gresits, I. [Technical University of Budapest (Hungary); Ordagh, M. [SOM System Llc, (Hungary)

2008-07-01T23:59:59.000Z

323

Sandia National Laboratories: Red LED  

Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -theErik SpoerkeSolar Regional TestClimateResearchRecovery Act (ARRA) ProjectsRed

324

Integration of the Mini-Sulfide Sulfite Anthraquinone (MSS-AQ) Pulping Process and Black Liquor Gasification in a Pulp Mill  

SciTech Connect (OSTI)

As many of the recovery boilers and other pieces of large capital equipment of U.S. pulp mills are nearing the end of their useful life, the pulp and paper industry will soon need to make long-term investments in new technologies. The ability to install integrated, complete systems that are highly efficient will impact the industrys energy use for decades to come. Developing a process for these new systems is key to the adoption of state-of-the-art technologies in the Forest Products industry. This project defined an integrated process model that combines mini-sulfide sulfite anthraquinone (MSS-AQ) pulping and black liquor gasification with a proprietary desulfurization process developed by the Research Triangle Institute. Black liquor gasification is an emerging technology that enables the use of MSS-AQ pulping, which results in higher yield, lower bleaching cost, lower sulfur emissions, and the elimination of causticization requirements. The recently developed gas cleanup/absorber technology can clean the product gas to a state suitable for use in a gas turbine and also regenerate the pulping chemicals needed to for the MSS-AQ pulping process. The combination of three advanced technologies into an integrated design will enable the pulping industry to achieve a new level of efficiency, environmental performance, and cost savings. Because the three technologies are complimentary, their adoption as a streamlined package will ensure their ability to deliver maximum energy and cost savings benefits. The process models developed by this project will enable the successful integration of new technologies into the next generation of chemical pulping mills. When compared to the Kraft reference pulp, the MSS-AQ procedures produced pulps with a 10-15 % yield benefit and the ISO brightness was 1.5-2 times greater. The pulp refined little easier and had a slightly lower apparent sheet density (In both the cases). At similar levels of tear index the MSS-AQ pulps also produced a comparable tensile and burst index pulps. Product gas composition determined using computer simulations The results demonstrate that RVS-1 can effectively remove > 99.8% of the H2S present in simulated synthesis gas generated from the gasification of black liquor. This level of sulfur removal was consistent over simulated synthesis gas mixtures that contained from 6 to 9.5 vol % H2S.A significant amount of the sulfur in the simulated syngas was recovered as SO2 during regeneration. The average recovery of sulfur as SO2 was about 75%. Because these are first cycle results, this sulfur recovery is expected to improve. Developed WINGems model of the process.The total decrease in variable operating costs for the BLG process compared to the HERB was in excess of $6,200,000 per year for a mill producing 350,000 tons of pulp per year. This represents a decrease in operating cost of about $17.7/ton of oven dry pulp produced. There will be additional savings in labor and maintenance cost that has not been taken into account. The capital cost for the MSSAQ based gasifier system was estimated at $164,000,000, which is comparable to a High Efficiency Recovery Boiler. The return on investment was estimated at 4%. A gasifier replacement cannot be justified on its own, however if the recovery boiler needs to be replaced the MSSAQ gasifier system shows significantly higher savings. Before black liquor based gasifer technology can be commercialized more work is necessary. The recovery of the absorbed sulfur in the absorbent as sulfur dioxide is only 75%. This needs to be greater than 90% for economical operation. It has been suggested that as the number of cycles is increased the sulfur dioxide recovery might improve. Further research is necessary. Even though a significant amount of work has been done on a pilot scale gasifiers using liquors containing sulfur, both at low and high temperatures the lack of a commercial unit is an impediment to the implementation of the MSSAQ technology. The implementation of a commercial unit needs to be facilated before the benefits of

Hasan Jameel, North Carolina State University; Adrianna Kirkman, North Carolina State University; Ravi Chandran,Thermochem Recovery International Brian Turk Research Triangle Institute; Brian Green, Research Triangle Institute

2010-01-27T23:59:59.000Z

325

International Atomic Energy Agency (IAEA) activities on spent fuel management options  

SciTech Connect (OSTI)

Many countries have in the past several decades opted for storage of spent fuel for undefined periods of time. They have adopted the 'wait and see' strategy for spent fuel management. A relatively small number of countries have adopted reprocessing and use of MOX fuel as part of their strategy in spent fuel management. From the 10, 000 tonnes of heavy metal that is removed annually from nuclear reactors throughout the world, only approximately 30 % is currently being reprocessed. Continuous re-evaluation of world energy resources, announcement of the Global Nuclear Energy Partnership (GNEP) and the Russian initiative to form international nuclear centers, including reprocessing, are changing the stage for future development of nuclear energy. World energy demand is expected to more than double by 2050, and expansion of nuclear energy is a key to meeting this demand while reducing pollution and greenhouse gases. Since its foundation, the International Atomic Energy Agency (IAEA) has served as an interface between countries in exchanging information on the peaceful development of nuclear energy and at the same time guarding against proliferation of materials that could be used for nuclear weapons. The IAEA's Department of Nuclear Energy has been generating technical documents, holding meetings and conferences, and supporting technical cooperation projects to facilitate this exchange of information. This paper focuses on the current status of IAEA activities in the field of spent fuel management being carried out by the Division of Nuclear Fuel Cycle and Waste Technology. Information on those activities could be found on the web site link www.iaea.org/OurWork/ST/NE/NEFW/nfcms. To date, the IAEA has given priority in its spent fuel management activities to supporting Member States in their efforts to deal with growing accumulations of spent power reactor fuel. There is technical consensus that the present technologies for spent fuel storage, wet and dry, provide adequate protection to people and environment. As storage durations grow, the IAEA has expanded its work related to the implications of extended storage periods. Operation and maintenance of containers for storage and transport have also been investigated related to long term storage periods. In addition, as international interest in reprocessing of spent fuel increases, the IAEA continues to serve as a crossroads for sharing the latest developments in spent fuel treatment options. A Coordinated Research Project is currently addressing spent fuel performance assessment and research to evaluate long term effects of storage on spent fuel. The effect of increased burnup and mixed oxide fuels on spent fuel management is also the focus of interest as it follows the trend in optimizing the use of nuclear fuel. Implications of damaged fuel on storage and transport as well as burnup credit in spent fuel applications are areas that the IAEA is also investigating. Since spent fuel management considerations require social stability and institutional control, those aspects are taken into account in most IAEA activities. Data requirements and records management as storage durations extend were also investigated as well as the potential for regional spent fuel storage facilities. Spent fuel management activities continue to be coordinated with others in the IAEA to ensure compliance and consistency with efforts in the Department of Safety and Security and the Department of Safeguards, as well as with activities related to geologic disposal. Either disposal of radioactive waste or spent fuel will be an ultimate consideration in all spent fuel management options. Updated information on spent fuel treatment options that include fuel reprocessing as well as transmutation of minor actinides are investigated to optimize the use of nuclear fuel and minimize impact on environment. Tools for spent fuel management economics are also investigated to facilitate assessment of industrial applicability for these options. Most IAEA spent fuel management activities will ultimately be reported in o

Lovasic, Z.; Danker, W. [International Atomic Energy Agency (IAEA) Vienna (Austria)

2007-07-01T23:59:59.000Z

326

Commercial Spent Nuclear Fuel Waste Package Misload Analysis  

SciTech Connect (OSTI)

The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1 and Table 1). For this calculation, a misloaded waste package is defined as a waste package that has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package design. An example of this type of misload is a fuel assembly designated for the 21-PWR Control Rod waste package being incorrectly loaded into a 21-PWR Absorber Plate waste package. This constitutes a misloaded 21-PWR Absorber Plate waste package, because the reactivity (i.e., enrichment and/or burnup) of a 21-PWR Control Rod waste package fuel assembly is outside the design of a 21-PWR Absorber Plate waste package. These types of misloads (i.e., fuel assembly with enrichment and/or burnup outside waste package design) are the only types that are evaluated in this calculation. This calculation utilizes information from ''Frequency of SNF Misload for Uncanistered Fuel Waste Package'' (CRWMS M&O 1998) as the starting point. The scope of this calculation is limited to the information available. The information is based on the whole population of fuel assemblies and the whole population of waste packages, because there is no information about the arrival of the waste stream at this time. The scope of this calculation deviates from that specified in ''Technical Work Plan for: Risk and Criticality Department'' (BSC 2002a, Section 2.1.30) in that only waste package misload is evaluated. The remaining issues identified (i.e., flooding and geometry reconfiguration) will be addressed elsewhere. The intended use of the calculation is to provide information and inputs to the Preclosure Safety Analysis Department. Before using the results of this calculation, the reader is cautioned to verify that the assumptions made in this calculation regarding the waste stream, the loading process, and the staging of the spent nuclear fuel assemblies are applicable.

A. Alsaed

2005-07-28T23:59:59.000Z

327

Commercial Spent Nuclear Fuel Waste Package Misload Analysis  

SciTech Connect (OSTI)

The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1 and Table 1). For this calculation, a misloaded waste package is defined as a waste package that has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package design. An example of this type of misload is a fuel assembly designated for the 21-PWR Control Rod waste package being incorrectly loaded into a 21-PWR Absorber Plate waste package. This constitutes a misloaded 21-PWR Absorber Plate waste package, because the reactivity (i.e., enrichment and/or burnup) of a 21-PWR Control Rod waste package fuel assembly is outside the design of a 21-PWR Absorber Plate waste package. These types of misloads (i.e., fuel assembly with enrichment and/or burnup outside waste package design) are the only types that are evaluated in this calculation. This calculation utilizes information from ''Frequency of SNF Misload for Uncanistered Fuel Waste Package'' (CRWMS M&O 1998) as the starting point. The scope of this calculation is limited to the information available. The information is based on the whole population of fuel assemblies and the whole population of waste packages, because there is no information about the arrival of the waste stream at this time. The scope of this calculation deviates from that specified in ''Technical Work Plan for: Risk and Criticality Department'' (BSC 2002a, Section 2.1.30) in that only waste package misload is evaluated. The remaining issues identified (i.e., flooding and geometry reconfiguration) will be addressed elsewhere. The intended use of the calculation is to provide information and inputs to the Preclosure Safety Analysis Department. Before using the results of this calculation, the reader is cautioned to verify that the assumptions made in this calculation regarding the waste stream, the loading process, and the staging of the spent nuclear fuel assemblies are applicable.

J.K. Knudson

2003-10-02T23:59:59.000Z

328

Test plan for reactions between spent fuel and J-13 well water under unsaturated conditions  

SciTech Connect (OSTI)

The Yucca Mountain Site Characterization Project is evaluating the long-term performance of a high-level nuclear waste form, spent fuel from commercial reactors. Permanent disposal of the spent fuel is possible in a potential repository to be located in the volcanic tuff beds near Yucca Mountain, Nevada. During the post-containment period the spent fuel could be exposed to water condensation since of the cladding is assumed to fail during this time. Spent fuel leach (SFL) tests are designed to simulate and monitor the release of radionuclides from the spent fuel under this condition. This Test Plan addresses the anticipated conditions whereby spent fuel is contacted by small amounts of water that trickle through the spent fuel container. Two complentary test plans are presented, one to examine the reaction of spent fuel and J-13 well water under unsaturated conditions and the second to examine the reaction of unirradiated UO{sub 2} pellets and J-13 well water under unsaturated conditions. The former test plan examines the importance of the water content, the oxygen content as affected by radiolysis, the fuel burnup, fuel surface area, and temperature. The latter test plant examines the effect of the non-presence of Teflon in the test vessel.

Finn, P.A.; Wronkiewicz, D.J.; Hoh, J.C.; Emery, J.W.; Hafenrichter, L.D.; Bates, J.K.

1993-01-01T23:59:59.000Z

329

Spent fuel and fuel pool component integrity. Annual report, FY 1980  

SciTech Connect (OSTI)

During program FY 1980 staff members of the Spent Fuel and Fuel Pool Component Integrity Program at Pacific Northwest Laboratory (PNL) completed the following major tasks: represented DOE on the international Behavior of Fuel Assemblies in Storage (BEFAST) Committee; the program manager, A.B. Johnson, Jr., participated in an International Survey of Water Reactor Spent Fuel Storage Experience, which was conducted jointly by the International Atomic Energy Agency (Vienna) and the Nuclear Energy Agency (Paris); provided written testimony and cross statement for the Proposed Rulemaking on Storage and Disposal of Nuclear Waste; acquired and began examination of the world's oldest pool-stored Zircaloy-clad fuel from the Shippingport reactor, stored approx. 21 years in deionized water; acquired and began examination of stainless-clad spent fuel from the Connecticut Yankee Reactor (PWR); negotiated for specimens from components stored in spent fuel pools at fuel storage facilities from the Savannah River Plant, Aiken, South Carolina, Zion (PWR) spent fuel pool, Zion, Illinois, and La Crosse (BWR) spent fuel pool, La Crosse, Wisconsin; planned for examinations in FY 81 of specimens from the three spent fuel pools; investigated a low-temperature stress corrosion cracking mechanism that developed in piping at a few PWR spent fuel pools. This report summarizes the results of these activities and investigations. Details are provided in the presentationsand publications generated under this program and summarized in Appendix A.

Johnson, A.B. Jr.; Bailey, W.J.; Bradley, E.R.; Bruemmer, S.M.; Langstaff, D.C.

1981-09-01T23:59:59.000Z

330

Fracture behavior of zircaloy spent-fuel cladding  

SciTech Connect (OSTI)

The Zircaloy cladding of water reactor fuel rods is susceptible to local breach-type failure, commonly known as pellet-cladding interaction (PCI) failure, during operational and off-normal power transients after the fuel has achieved a sufficiently high burnup. An optimization of power ramp procedures or fuel rod fabrication to minimize the cladding failure would result in a significant decrease in radiation exposure of plant personnel due to background and airborne radioactivity as well as an extension of core life in terms of allowable off-gas radioactivity. As part of a program to provide a better understanding of the fuel rod faiure phenomenon and to facilitate the formulation of a better failure criterion, a mechanistic study of the deformation and fracture behavior of high-burnup spent-fuel cladding is in progress under simulated PCI conditions.

Chung, H.M.; Yaggee, F.L.; Kassner, T.F.

1983-10-01T23:59:59.000Z

331

SPENT FUEL MANAGEMENT AT THE SAVANNAH RIVER SITE  

SciTech Connect (OSTI)

Spent nuclear fuels are received from reactor sites around the world and are being stored in the L-Basin at the Savannah River Site (SRS) in Aiken, South Carolina. The predominant fuel types are research reactor fuel with aluminum-alloy cladding and aluminum-based fuel. Other fuel materials include stainless steel and Zircaloy cladding with uranium oxide fuel. Chemistry control and corrosion surveillance programs have been established and upgraded since the early 1990's to minimize corrosion degradation of the aluminum cladding materials, so as to maintain fuel integrity and minimize personnel exposure from radioactivity in the basin water. Recent activities have been initiated to support additional decades of wet storage which include fuel inspection and corrosion testing to evaluate the effects of specific water impurity species on corrosion attack.

Vormelker, P; Robert Sindelar, R; Richard Deible, R

2007-11-03T23:59:59.000Z

332

Structural analysis of extracts from spent hydroprocessing catalysts  

SciTech Connect (OSTI)

Solvent extracts from spent commercial naphtha and gas oil hydrotreating catalysts were examined in order to elucidate the structure of adsorbed poisons. Amides were identified in the extracts and made up 20-30% of the basic compounds. The oxygen content of the extracts was as high as 28% by weight. Some of this oxygen may be associated with metal complexes or present as inorganic material. Infrared spectroscopic analysis revealed very strong absorptions due to carbonyls, suggesting that compounds such as ketones and carboxylic acids were present. The extracted compounds consisted of saturated (paraffinic and naphthenic) structures and aromatic groups, with >50% boiling at +343/sup 0/c. These results suggest polymerization of species on the surface of the catalyst, rather than condensation of aromatic structures to form coke.

Choi, J.H.K.; Gray, M.R.

1988-09-01T23:59:59.000Z

333

Radiochemical analyses of several spent fuel Approved Testing Materials  

SciTech Connect (OSTI)

Radiochemical characterization data are described for UO{sub 2} and UO{sub 2} plus 3 wt% Gd{sub 2}O{sub 3} commercial spent nuclear fuel taken from a series of Approved Testing Materials (ATMs). These full-length nuclear fuel rods include MLA091 of ATM-103, MKP070 of ATM-104, NBD095 and NBD131 of ATM-106, and ADN0206 of ATM-108. ATMs 103, 104, and 106 were all irradiated in the Calvert Cliffs Nuclear Power Plant (Reactor No.1), a pressurized-water reactor that used fuel fabricated by Combustion Engineering. ATM-108 was part of the same fuel bundle designed as ATM-105 and came from boiling-water reactor fuel fabricated by General Electric and irradiated in the Cooper Nuclear Power Plant. Rod average burnups and expected fission gas releases ranged from 2,400 to 3,700 GJ/kgM. (25 to 40 Mwd/kgM) and from less than 1% to greater than 10%, respectively, depending on the specific ATM. The radiochemical analyses included uranium and plutonium isotopes in the fuel, selected fission products in the fuel, fuel burnup, cesium and iodine on the inner surfaces of the cladding, {sup 14}C in the fuel and cladding, and analyses of the gases released to the rod plenum. Supporting examinations such as fuel rod design and material descriptions, power histories, and gamma scans used for sectioning diagrams are also included. These ATMs were examined as part of the Materials Characterization Center Program conducted at Pacific Northwest Laboratory provide a source of well-characterized spent fuel for testing in support of the US Department of Energy Office of Civilian Radioactive Waste Management Program.

Guenther, R.J.; Blahnik, D.E.; Wildung, N.J.

1994-09-01T23:59:59.000Z

334

Deformation and fracture characteristics of spent Zircaloy fuel cladding  

SciTech Connect (OSTI)

For a better understanding of Zircaloy fuel-rod failure by the pellet-cladding interaction (PCI) phenomenon, a mechanistic study of deformation and fracture behavior of spent power reactor fuel cladding under simulated PCI conditions was conducted. Zircaloy-2 cladding specimens, obtained from fuel assemblies of operating power reactors, were deformed to fracture at 325/sup 0/C by internal gas pressurization in the absence of fission product simulants. Fracture characteristics and microstructures were examined via SEM, TEM, and HVEM. Numerous dislocation tangles and cell structures, observed in TEM specimens of cladding tubes that failed in a ductile manner, were consistent with SEM observations of a limited number of dimples characteristic of microvoid coalescence. A number of brittle-type failures were produced without the influence of fission product simulants. The brittle cracks occurred near the areas compressed by the Swagelok fittings of the internally pressurized tube and propagated from the outer to the inner surface. Since the outer surface was isolated and maintained under a flowing stream of pure helium, it is unlikely that the brittle-type failure was influenced by any fission product traces. SEM fractography of the brittle-type failure revealed a large area of transgranular pseudocleavage with limited areas of ductile fluting, which were similar in appearance to the surfaces produced by in-reactor PCI-type failures. A TEM evaluation of the cladding in the vicinity of the through-wall crack revealed numerous locations that contained an extensive amount of second-phase precipitate (Zr/sub 3/O). We believe that the brittle-type failures of the irradiated spent fuel cladding in the stress rupture experiments are associated with segregation of oxygen, which leads to the formation of the order structure, an immobilization of dislocations, and minimal plastic deformation in the material.

Chung, H.M.; Yaggee, F.L.

1982-09-01T23:59:59.000Z

335

Utilizing Divers in Support of Spent Fuel Basin Closure Subproject  

SciTech Connect (OSTI)

A number of nuclear facilities in the world are aging and with this comes the fact that we have to either keep repairing them or decommission them. At the Department of Energy Idaho Site (DOEID) there are a number of facilities that are being decommissioned, but the facilities that pose the highest risk to the large aquifer that flows under the site are given highest priorities. Aging spent nuclear fuel pools at DOE-ID are among the facilities that pose the highest risk, therefore four pools were targeted for decommissioning in Fiscal Year 2004. To accomplish this task the Idaho Completion Project (ICP) of Bechtel BWXT Idaho, LLC, put together an integrated Basin Closure Subproject team. The team was assigned a goal to look beyond traditional practices at the Idaho National Engineering and Environmental Laboratory (INEEL) to find ways to get the basin closure work done safer and more efficiently. The Idaho Completion Project (ICP) was faced with a major challenge cleaning and preparing aging spent nuclear fuel basins for closure by removing sludge and debris, as necessary, and removing water to eliminate a potential risk to the Snake River Plain Aquifer. The project included cleaning and removing water from four basins. Two of the main challenges to a project like this is the risk of contamination from the basin walls and floors becoming airborne as the water is removed and keeping personnel exposures ALARA. ICPs baseline plan had workers standing at the edges of the basins and on rafts or bridge cranes and then using long-handled tools to manually scrub the walls of basin surfaces. This plan had significant risk of skin contamination events, workers falling into the water, or workers sustaining injuries from the awkward working position. Analysis of the safety and radiation dose risks presented by this approach drove the team to look for smarter ways to get the work done.

Allen Nellesen

2005-01-01T23:59:59.000Z

336

Managing Spent Nuclear Fuel at the Idaho National Laboratory  

SciTech Connect (OSTI)

The Idaho National Laboratory (INL) has a large inventory of diverse types of spent nuclear fuel (SNF). This legacy derives from the history of the INL as the National Reactor Testing Station, and from its mission to recover HEU from SNF and to test and examine SNF after irradiation. The INL also has a large diversity of SNF storage facilities, some 50 years old. SNF at INL has many formsfrom intact assemblies down to metallurgical mounts, and some fuel has been wet stored for over 40 years. SNF is stored bare or in metal cans under water, or dry in vaults, caissons or casks. Inspection shows varying corrosion and degradation of the SNF and its storage cans. SNF has been stored in 10 different facilities: 5 pools, one cask storage pad, one vault, two generations of caisson facilities, and one modular Independent Spent Fuel Storage Installation (ISFSI). The pools range in age from 40 years old to the most modern in the US Department of Energy (DOE) complex. The near-term objective is to move SNF from older pools to interim dry storage, allowing shutdown and decommissioning of the older facilities. This move involves drying methods that are dependent on fuel type. The long-term objective is to have INL SNF in safe dry storage and ready to be shipped to the National Repository. The unique features of the INL SNF requires special treatments and packaging to meet the proposed repository acceptance criteria and SNF will be repackaged in standardized canisters for shipment and disposal in the National Repository. Disposal will use the standardized canisters that can be co-disposed with High Level Waste glass logs to limit the total fissile material in a repository waste package. The DOE standardized canister also simplifies the repository handling of the multitude of DOE SNF sizes and shapes.

Thomas Hill; Denzel L. Fillmore

2005-10-01T23:59:59.000Z

337

Fort Calhoun Station disposal of spent fuel pool racks  

SciTech Connect (OSTI)

The original plan was to have the racks pulled out of the pool, washed down and wrapped and placed in Sea/Lands to be sent to a vendor for free release and disposal. In the winter of 93 the proposed quotations on the Spent Fuel Rerack Processing were all rejected. With the rerack job starting in March of 94 and the closing of Barnwell in July we were faced with what to do with the racks. Processing of the existing racks were required since if the racks were sent to Barnwell for burial intact the cost would be prohibitive, that is, if Barnwell would have stayed open. If the racks were sent to a smelter, such as Scientific Ecology Group (SEG), there are restrictions on the length of the components that can go through the smelter. If SEG were to do the rack processing (sectioning) at their facility, the cost would also be prohibitive and they would not be in a position to receive the racks until June, 1995. Therefore, bid specifications were requested for on-site volume reduction processing of the existing spent fuel storage racks, with further ultimate disposal to be performed by SEG. The processing of the racks included piping and supports. Volume reduction (VR) was an issue in the evaluation since after this process the racks were to be shipped to SEG. If a low VR ratio option was chosen, OPPD would need a significant number of shipping containers and required more radwaste shipments versus if a high VR ratio option were chosen.

Jamieson, T.W. [Omaha Public Power District, Fort Calhoun Station, NE (United States)

1995-09-01T23:59:59.000Z

338

Savannah River Site, Spent Nuclear Fuel Management, Draft Environmental Impact Statement  

SciTech Connect (OSTI)

The proposed DOE action described in this environmental impact statement (EIS) is to implement appropriate processes for the safe and efficient management of spent nuclear fuel and targets assigned to the Savannah River Site (SRS), including placing these materials in forms suitable for ultimate disposition. Options to treat, package, and store this material are discussed. The material included in this EIS consists of approximately 68 metric tons heavy metal (MTHM) of spent nuclear fuel (20 MTHM of aluminum-based spent nuclear fuel at SRS, as much as 28 MTHM of aluminum-clad spent nuclear fuel from foreign and domestic research reactors to be shipped to SRS through 2035, and 20 MTHM of stainless-steel or zirconium-clad spent nuclear fuel and some programmatic material stored at SRS for repackaging and dry storage pending shipment offsite).

N /A

1998-12-24T23:59:59.000Z

339

Direct Investigations of the Immobilization of Radionuclides in the Alteration Products of Spent Nuclear Fuel  

SciTech Connect (OSTI)

Safe disposal of the nation's nuclear waste in a geological repository involves unique scientific and engineering challenges owing to the very long-lived radioactivity of the waste. The repository must retain a variety of radionuclides that have vastly different chemical characters for several thousand years. Most of the radioactivity that will be housed in the proposed repository at Yucca Mountain will be associated with spent nuclear fuel, much of which is derived from commercial reactors. DOE is custodian of approximately 8000 tons of spent nuclear fuel that is also intended for eventual disposal in a geological repository. Unlike the spent fuel from commercial reactors, the DOE fuel is diverse in composition with more than 250 varieties. Safe disposal of spent fuel requires a detailed knowledge of its long-term behavior under repository conditions, as well as the fate of radionuclides released from the spent fuel as waste containers are breached.

Peter C. Burns; Robert J. Finch; David J. Wronkiewicz

2004-12-27T23:59:59.000Z

340

Red-Black Trees 11/26/2007 11:09 AM Red-Black Trees 1 2004 Goodrich, Tamassia  

E-Print Network [OSTI]

Red-Black Trees 11/26/2007 11:09 AM 1 Red-Black Trees 1© 2004 Goodrich, Tamassia Red-Black Trees 6 3 8 4 v z Red-Black Trees 2© 2004 Goodrich, Tamassia From (2,4) to Red-Black Trees A red-black tree is a representation of a (2,4) tree by means of a binary tree whose nodes are colored red or black In comparison

Alechina, Natasha

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Red-Black Trees 11/11/2004 10:02 AM Red-Black Trees 1 2004 Goodrich, Tamassia  

E-Print Network [OSTI]

Red-Black Trees 11/11/2004 10:02 AM 1 Red-Black Trees 1© 2004 Goodrich, Tamassia Red-Black Trees 6 3 8 4 v z Red-Black Trees 2© 2004 Goodrich, Tamassia From (2,4) to Red-Black Trees A red-black tree is a representation of a (2,4) tree by means of a binary tree whose nodes are colored red or black In comparison

Alechina, Natasha

342

Red blood cell malformations Cell shapes Modeling and simulation of red blood cell light scattering  

E-Print Network [OSTI]

that have a "sickle" appearance (see figure to left). This malformed geometry prevents cells from traveling Red blood cell malformations Cell shapes Modeling and simulation of red blood cell light to various diseases and acute conditions, the shape and composition of erythrocytes (red blood cells

California at Berkeley, University of

343

Do red giants have short mode lifetimes?  

E-Print Network [OSTI]

We show evidence that the red giant star ksi Hya has an oscillation mode lifetime, tau, of about 2 days significantly shorter than predicted by theory (tau = 17 days, Houdek & Gough 2002). If this is a general trend of red giants it would limit the prospects of asteroseismology on these stars because of poor coherence of the oscillations.

D. Stello; H. Kjeldsen; T. R. Bedding; D. Buzasi

2005-10-18T23:59:59.000Z

344

*Please do NOT put out food if both red and grey squirrels are present* Feeding red squirrels  

E-Print Network [OSTI]

*Please do NOT put out food if both red and grey squirrels are present* Feeding red squirrels The UK Red Squirrel Group does not generally recommend that people put out food for red squirrels, there are risks to red squirrels by enticing them into your garden, or other premises. These include disease

345

Studies on reaction runaways for Urex/Purex solvent-nitric acid and red-oil synthesis  

SciTech Connect (OSTI)

In PUREX/UREX processes for recycling of spent nuclear fuels, 30% TBP solvent is used, This solvent has a small solubility in the aqueous phase. During concentration of the process solutions by an evaporation route, a runaway reaction between TBP and nitric acid is initiated at above 130 deg. C, leading to rapid pressurization and finally containment failure if proper venting is not provided. Red oil was synthesized for the first time in India, and its physical properties as well as thermodynamic parameters for the reaction were determined. It was experimentally established that the presence of metallic nitrates was not essential for red-oil formation as thought earlier. Various experiments have been completed for single-phase as well as two-phase runs. The most important finding of this work was lowering of the limiting acid concentration from the conventional values. In fact, in these experiments, red oil could be formed even at 2 N aqueous acidity. Thus, safety guidelines based on the classical literature are obsolete. New guidelines for the red-oil-safety are required. (authors)

Kumar, Shekhar; Kumar, Rajnish; Koganti, S.B. [Reprocessing R and D Division, Reprocessing Group, Indira Gandhi Centre for Atomic Research, Kalpakkam 603102 (India)

2008-07-01T23:59:59.000Z

346

Dry Storage of Research Reactor Spent Nuclear Fuel - 13321  

SciTech Connect (OSTI)

Spent fuel from domestic and foreign research reactors is received and stored at the Savannah River Site's L Area Material Storage (L Basin) Facility. This DOE-owned fuel consists primarily of highly enriched uranium in metal, oxide or silicide form with aluminum cladding. Upon receipt, the fuel is unloaded and transferred to basin storage awaiting final disposition. Disposition alternatives include processing via the site's H Canyon facility for uranium recovery, or packaging and shipment of the spent fuel to a waste repository. A program has been developed to provide a phased approach for dry storage of the L Basin fuel. The initial phase of the dry storage program will demonstrate loading, drying, and storage of fuel in twelve instrumented canisters to assess fuel performance. After closure, the loaded canisters are transferred to pad-mounted concrete overpacks, similar to those used for dry storage of commercial fuel. Unlike commercial spent fuel, however, the DOE fuel has high enrichment, very low to high burnup, and low decay heat. The aluminum cladding presents unique challenges due to the presence of an oxide layer that forms on the cladding surface, and corrosion degradation resulting from prolonged wet storage. The removal of free and bound water is essential to the prevention of fuel corrosion and radiolytic generation of hydrogen. The demonstration will validate models predicting pressure, temperature, gas generation, and corrosion performance, provide an engineering scale demonstration of fuel handling, drying, leak testing, and canister backfill operations, and establish 'road-ready' storage of fuel that is suitable for offsite repository shipment or retrievable for onsite processing. Implementation of the Phase I demonstration can be completed within three years. Phases II and III, leading to the de-inventory of L Basin, would require an additional 750 canisters and 6-12 years to complete. Transfer of the fuel from basin storage to dry storage requires integration with current facility operations, and selection of equipment that will allow safe operation within the constraints of existing facility conditions. Examples of such constraints that are evaluated and addressed by the dry storage program include limited basin depth, varying fuel lengths up to 4 m, (13 ft), fissile loading limits, canister closure design, post-load drying and closure of the canisters, instrument selection and installation, and movement of the canisters to storage casks. The initial pilot phase restricts the fuels to shorter length fuels that can be loaded to the canister directly underwater; subsequent phases will require use of a shielded transfer system. Removal of the canister from the basin, followed by drying, inerting, closure of the canister, and transfer of the canister to the storage cask are completed with remotely operated equipment and appropriate shielding to reduce personnel radiation exposure. (authors)

Adams, T.M.; Dunsmuir, M.D.; Leduc, D.R.; Severynse, T.F.; Sindelar, R.L. [Savannah River National Laboratory (United States)] [Savannah River National Laboratory (United States); Moore, E.N. [Moore Nuclear Energy, LLC (United States)] [Moore Nuclear Energy, LLC (United States)

2013-07-01T23:59:59.000Z

347

Fast Reactor Spent Fuel Processing: Experience and Criticality Safety  

SciTech Connect (OSTI)

This paper discusses operational and criticality safety experience associated with the Idaho National Laboratory Fuel Conditioning Facility which uses a pyrometallurgical process to treat spent fast reactor metallic fuel. The process is conducted in an inert atmosphere hot cell. The process starts with chopping metallic fuel elements into a basket. The basket is lowered into molten salt (LiCl-KCl) along with a steel mandrel. Active metal fission products, transuranic metals and sodium metal in the spent fuel undergo chemical oxidation and form chlorides. Voltage is applied between the basket, which serves as an anode, and the mandrel, which serves as a cathode, causing metallic uranium in the spent fuel to undergo electro-chemical oxidation thereby forming uranium chloride. Simultaneously at the cathode, uranium chloride undergoes electro-chemical reduction and deposits uranium metal onto the mandrel. The uranium metal and accompanying entrained salt are placed in a distillation furnace where the uranium melts forming an ingot and the entrained salt boils and subsequently condenses in a separate crucible. The uranium ingots are placed in long term storage. During the ten year operating history, over one hundred criticality safety evaluations were prepared. All criticality safety related limits and controls for the entire process are contained in a single document which required over thirty revisions to accommodate the process changes. Operational implementation of the limits and controls includes use of a near real-time computerized tracking system. The tracking system uses an Oracle database coupled with numerous software applications. The computerized tracking system includes direct fuel handler interaction with every movement of material. Improvements to this system during the ten year history include introduction of web based operator interaction, tracking of moderator materials and the development of a plethora database queries to assist in day to day operations as well as obtaining historical information. Over 12,000 driver fuel elements have been processed resulting in the production of 2500 kg of 20% enriched uranium. Also, over one thousand blanket fuel elements have been processed resulting in the production of 2400 kg of depleted uranium. These operations required over 35,000 fissile material transfers between zones and over 6000 transfers between containers. Throughout all of these movements, no mass limit violations occurred. Numerous lessons were learned over the ten year operating history. From a criticality safety perspective, the most important lesson learned was the involvement of a criticality safety practitioner in daily operations. A criticality safety engineer was assigned directly to facility operations, and was responsible for implementation of limits and controls including upkeep of the associated computerized tracking files. The criticality safety engineer was also responsible for conducting fuel handler training activities including serving on fuel handler qualification oral boards, and continually assessing operations from a criticality control perspective. The criticality safety engineer also attended bimonthly project planning meetings to identify upcoming process changes that would require criticality safety evaluation. Finally, the excellent criticality safety record was due in no small part to the continual support, involvement, trust, and confidence of project and operations mana

Chad Pope

2007-05-01T23:59:59.000Z

348

Qualitative human reliability analysis for spent fuel handling  

SciTech Connect (OSTI)

Human reliability analysis (HRA) methods have been developed primarily to provide information for use in probabilistic risk assessments (PRAs) that analyze nuclear power plant (NPP) operations. Given the original emphasis of these methods, it is understandable that many HRAs have not ventured far from NPP control room applications. Despite this historical focus on the control room, there has been growing interest and discussion regarding the application of HRA methods to other NPP activities such as spent fuel handling (SFH) or operations in different types of facilities. One recently developed HRA method, 'A Technique for Human Event Analysis' (ATHEANA) has been proposed as a promising candidate for diverse applications due to its particular approach for systematically uncovering the dynamic, contextual conditions influencing human performance. This paper describes one successful test of this proposition by presenting portions of a recently completed project in which a scoping study was performed to accomplish the following goals: (1) investigate what should be included in a qualitative HRA for spent fuel and cask handling operations; and (2) demonstrate that the ATHEANA HRA technique can be usefully applied to these operations. The preliminary, scoping qualitative HRA examined, in a generic manner, how human performance of SFH and dry cask storage operations (DCSOs) can plausibly lead to radiological consequences that impact the public and the environment. The study involved the performance of typical, qualitative HRA tasks such as collecting relevant information and the preliminary identification of human failure events or unsafe actions, relevant influences (e.g., performance shaping factors, other contextual factors), event scenario development and categorization of human failure event (HFE) scenario groupings. Information from relevant literature sources was augmented with subject matter expert interviews and analysis of an edited video of selected operations. Elements of NUREG-1792, Good Practices for Implementing Human Reliability Analyses (HRA) and NUREG-1624, Rev. 1, Technical Basis and Implementation Guidelines for A Technique for Human Event Analysis (ATHEANA) formed critical parts of the technical basis for the preliminary analysis. Mis-loading of spent fuel into a cask and dropping of a loaded cask were the two human failure event groupings of primary interest, although all human performance aspects of DCSOs were considered to some extent. Of important note is that HRA is typically performed in the context of a plant-specific PRA study. This analysis was performed without the benefit of the context provided by a larger PRA study, nor was it plant specific, and so it investigated only generic HRA issues relevant to SFH. However, the improved understanding of human performance issues provided by the study will likely enhance the ability to carry out a detailed qualitative HRA for a specific NPP at some point in the future. Furthermore, support was obtained regarding the potential for applying ATHEANA beyond NPP settings. This paper provides a description of the process followed during the analysis, a description of the HFE scenario groupings, discussion regarding general human performance vulnerabilities, and a detailed examination of one HFE scenario developed in the study. (authors)

Brewer, J. D. [Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185-0748 (United States); Amico, P. [Science Applications International Corporation (United States); Cooper, S. E. [United Stated Nuclear Regulatory Commission (United States)

2006-07-01T23:59:59.000Z

349

In-Situ Safeguards Verification of Low Burn-up Pressurized Water Reactor Spent Fuel Assemblies  

SciTech Connect (OSTI)

A novel in-situ gross defect verification method for light water reactor spent fuel assemblies was developed and investigated by a Monte Carlo study. This particular method is particularly effective for old pressurized water reactor spent fuel assemblies that have natural uranium in their upper fuel zones. Currently there is no method or instrument that does verification of this type of spent fuel assemblies without moving the spent fuel assemblies from their storage positions. The proposed method uses a tiny neutron detector and a detector guiding system to collect neutron signals inside PWR spent fuel assemblies through guide tubes present in PWR assemblies. The data obtained in such a manner are used for gross defect verification of spent fuel assemblies. The method uses 'calibration curves' which show the expected neutron counts inside one of the guide tubes of spent fuel assemblies as a function of fuel burn-up. By examining the measured data in the 'calibration curves', the consistency of the operator's declaration is verified.

Ham, Y S; Sitaraman, S; Park, I; Kim, J; Ahn, G

2008-04-16T23:59:59.000Z

350

Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 1, Appendix D, Part B: Naval spent nuclear fuel management  

SciTech Connect (OSTI)

This volume contains the following attachments: transportation of Naval spent nuclear fuel; description of Naval spent nuclear receipt and handling at the Expended Core Facility at the Idaho National Engineering Laboratory; comparison of storage in new water pools versus dry container storage; description of storage of Naval spent nuclear fuel at servicing locations; description of receipt, handling, and examination of Naval spent nuclear fuel at alternate DOE facilities; analysis of normal operations and accident conditions; and comparison of the Naval spent nuclear fuel storage environmental assessment and this environmental impact statement.

Not Available

1994-06-01T23:59:59.000Z

351

Spent-fuel dry-storage testing at E-MAD (March 1978-March 1982)  

SciTech Connect (OSTI)

From March 1978 through March 1982, spent fuel dry storage tests were conducted at the Engine Maintenance, Assembly and Disassembly (E-MAD) facility on the Nevada Test Site to confirm that commercial reactor spent fuel could be encapsulated and passively stored in one or more interim dry storage cell concepts. These tests were: electrically heated drywell, isolated and adjacent drywell, concrete silo, fuel assembly internal temperature measurement, and air-cooled vault. This document presents the test data and results as well as results from supporting test operations (spent fuel calorimetry and canister gas sampling).

Unterzuber, R.; Milnes, R.D.; Marinkovich, B.A.; Kubancsek, G.M.

1982-09-01T23:59:59.000Z

352

On bitcoin and red balloons  

E-Print Network [OSTI]

Many large decentralized systems rely on information propagation to ensure their proper function. We examine a common scenario in which only participants that are aware of the information can compete for some reward, and thus informed participants have an incentive not to propagate information to others. One recent example in which such tension arises is the 2009 DARPA Network Challenge (finding red balloons). We focus on another prominent example: Bitcoin, a decentralized electronic currency system. Bitcoin represents a radical new approach to monetary systems. It has been getting a large amount of public attention over the last year, both in policy discussions and in the popular press [Davis 2011; Surowiecki 2011]. Its cryptographic fundamentals have largely held up even as its usage has become increasingly widespread. We find, however, that it exhibits a fundamental problem of a different nature, based on how its incentives are structured. We propose a modification to the protocol that can eliminate this problem. Bitcoin relies on a peer-to-peer network to track transactions that are performed with the currency. For this purpose, every transaction a node learns about should be transmitted to its neighbors in the network. As the protocol is currently defined and implemented, it does not provide an incentive for nodes to broadcast transactions they are aware of. In fact, it provides an incentive not to do so. Our solution is to augment the

Moshe Babaioff; Silicon Valley; Shahar Dobzinski; Sigal Oren

2012-01-01T23:59:59.000Z

353

On Bitcoin and Red Balloons  

E-Print Network [OSTI]

We study scenarios in which the goal is to ensure that some information will propagate through a large network of nodes. In these scenarios all nodes that are aware of the information compete for the same prize, and thus have an incentive not to propagate information. One example for such a scenario is the 2009 DARPA Network Challenge (finding red balloons). We give special attention to a second domain, Bitcoin, a decentralized electronic currency system. Bitcoin, which has been getting a large amount of public attention over the last year, represents a radical new approach to monetary systems which has appeared in policy discussions and in the popular press. Its cryptographic fundamentals have largely held up even as its usage has become increasingly widespread. We find, however, that it exhibits a fundamental problem of a different nature, based on how its incentives are structured. We propose a modification to the protocol that can fix this problem. Bitcoin relies on a peer-to-peer network to track transac...

Babaioff, Moshe; Oren, Sigal; Zohar, Aviv

2011-01-01T23:59:59.000Z

354

A NOVEL APPROACH TO SPENT FUEL POOL DECOMMISSIONING  

SciTech Connect (OSTI)

The Idaho National Laboratory (INL) has been at the forefront of developing methods to reduce the cost and schedule of deactivating spent fuel pools (SFP). Several pools have been deactivated at the INL using an underwater approach with divers. These projects provided a basis for the INL cooperation with the Dresden Nuclear Power Station Unit 1 SFP (Exelon Generation Company) deactivation. It represents the first time that a commercial nuclear power plant (NPP) SFP was decommissioned using this underwater coating process. This approach has advantages in many aspects, particularly in reducing airborne contamination and allowing safer, more cost effective deactivation. The INL pioneered underwater coating process was used to decommission three SFPs with a total combined pool volume of over 900,000 gallons. INL provided engineering support and shared project plans to successfully initiate the Dresden project. This report outlines the steps taken by INL and Exelon to decommission SFPs using the underwater coating process. The rationale used to select the underwater coating process and the advantages and disadvantages are described. Special circumstances are also discussed, such as the use of a remotely-operated underwater vehicle to visually and radiologically map the pool areas that were not readily accessible. A larger project, the INTEC-603 SFP in-situ (grouting) deactivation, is reviewed. Several specific areas where special equipment was employed are discussed and a Lessons Learned evaluation is included.

R. L. Demmer

2011-04-01T23:59:59.000Z

355

Radionuclide release rates from spent fuel for performance assessment modeling  

SciTech Connect (OSTI)

In a scenario of aqueous transport from a high-level radioactive waste repository, the concentration of radionuclides in water in contact with the waste constitutes the source term for transport models, and as such represents a fundamental component of all performance assessment models. Many laboratory experiments have been done to characterize release rates and understand processes influencing radionuclide release rates from irradiated nuclear fuel. Natural analogues of these waste forms have been studied to obtain information regarding the long-term stability of potential waste forms in complex natural systems. This information from diverse sources must be brought together to develop and defend methods used to define source terms for performance assessment models. In this manuscript examples of measures of radionuclide release rates from spent nuclear fuel or analogues of nuclear fuel are presented. Each example represents a very different approach to obtaining a numerical measure and each has its limitations. There is no way to obtain an unambiguous measure of this or any parameter used in performance assessment codes for evaluating the effects of processes operative over many millennia. The examples are intended to suggest by example that in the absence of the ability to evaluate accuracy and precision, consistency of a broadly based set of data can be used as circumstantial evidence to defend the choice of parameters used in performance assessments.

Curtis, D.B.

1994-11-01T23:59:59.000Z

356

Packaging and transportation system for K-Basin spent fuel  

SciTech Connect (OSTI)

This paper describes the cask/transportation system that was designed, procured and delivered to the Hanford K-Basin site at Richland, Washington. The performance requirements and design of the various components -- cask, trailer with cask tie-down system, and the cask operation equipment for the load-out pit -- will be discussed. The presentation will include the details of the factory acceptance testing and its results. The performance requirements for the cask/transportation system was dictated by the constraints imposed by the large number of high priority shipments and the spent fuel pool environment, and the complex interface requirements with other equipment and facility designs. The results of the testing form the basis for the conclusion that the system satisfies the site performance requirements. The cask/transportation system design was driven by the existing facility constraints and the limitations imposed by the large number of shipments over a short two-year period. This system may be useful information for other DOE facilities that may be or will be in a similar situation.

Kee, A.T.

1998-03-03T23:59:59.000Z

357

Interim Storage of Hanford Spent Fuel & Associated Sludge  

SciTech Connect (OSTI)

The Hanford site is currently dealing with a number of types of Spent Nuclear Fuel. The route to interim dry storage for the various fuel types branches along two different paths. Fuel types such as metallic N reactor fuel and Shippingport Core 2 Blanket assemblies are being placed in approximately 4 m long canisters which are then stored in tubes below grade in a new canister storage building. Other fuels such as TRIGA{trademark} and Light Water Reactor fuel will be relocated and stored in stand-alone casks on a concrete pad. Varying degrees of sophistication are being applied with respect to the drying and/or evacuation of the fuel interim storage canisters depending on the reactivity of the fuel, the degree of damaged fuel and the previous storage environment. The characterization of sludge from the Hanford K Basins is nearly complete and canisters are being designed to store the sludge (including uranium particles from fuel element cleaning) on an interim basis.

MAKENAS, B.J.

2002-07-01T23:59:59.000Z

358

Safe Advantage on Dry Interim Spent Nuclear Fuel Storage  

SciTech Connect (OSTI)

This paper aims to present the advantages of dry cask storage in comparison with the wet storage (cooling water pools) for SNF. When the nuclear fuel is removed from the core reactor, it is moved to a storage unit and it wait for a final destination. Generally, the spent nuclear fuel (SNF) remains inside water pools within the reactors facility for the radioactive activity decay. After some period of time in pools, SNF can be sent to a definitive deposition in a geological repository and handled as radioactive waste or to reprocessing facilities, or still, wait for a future solution. Meanwhile, SNF remains stored for a period of time in dry or wet facilities, depending on the method adopted by the nuclear power plant or other plans of the country. Interim storage, up to 20 years ago, was exclusively wet and if the nuclear facility had to be decommissioned another storage solution had to be found. At the present time, after a preliminary cooling of the SNF elements inside the water pool, the elements can be stored in dry facilities. This kind of storage does not need complex radiation monitoring and it is safer then wet one. Casks, either concrete or metallic, are safer, especially on occurrence of earthquakes, like that occurred at Kashiwazaki-Kariwa nuclear power plant, in Japan on July 16, 2007. (authors)

Romanato, L.S. [Centro Tecnologico da Marinha em S.Paulo, Brazilian Navy Technological Center, Sao Paulo (Brazil)

2008-07-01T23:59:59.000Z

359

Seismic Behavior of Spent Fuel Dry Cask Storage Systems  

SciTech Connect (OSTI)

The U. S. Nuclear Regulatory Commission (NRC) is conducting a research program to investigate technical issues concerning the dry cask storage systems of spent nuclear fuel by conducting confirmatory research for establishing criteria and review guidelines for the seismic behavior of these systems. The program focuses on developing 3-D finite element analysis models that address the dynamic coupling of a module/cask, a flexible concrete pad, and an underlying soil/rock foundation, in particular, the soil-structure-interaction. Parametric analyses of the coupled models are performed to include variations in module/cask geometry, site seismicity, underlying soil properties, and cask/pad interface friction. The analyses performed include: 1) a rectangular dry cask module typical of Transnuclear West design at a site in Western USA where high seismicity is expected; 2) a cylindrical dry cask typical of Holtec design at a site in Eastern USA where low seismicity is expected; and 3) a cylindrical dry cask typical of Holtec design at a site in Western USA with medium high seismicity. The paper includes assumptions made in seismic analyses performed, results, and conclusions. (authors)

Shaukat, Syed K. [U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001 (United States); Luk, Vincent K. [Sandia National Laboratories, PO Box 5800. Albuquerque, New Mexico 87185-0744 (United States)

2002-07-01T23:59:59.000Z

360

Accelerator-driven transmutation of spent fuel elements  

DOE Patents [OSTI]

An apparatus and method is described for transmuting higher actinides, plutonium and selected fission products in a liquid-fuel subcritical assembly. Uranium may also be enriched, thereby providing new fuel for use in conventional nuclear power plants. An accelerator provides the additional neutrons required to perform the processes. The size of the accelerator needed to complete fuel cycle closure depends on the neutron efficiency of the supported reactors and on the neutron spectrum of the actinide transmutation apparatus. Treatment of spent fuel from light water reactors (LWRs) using uranium-based fuel will require the largest accelerator power, whereas neutron-efficient high temperature gas reactors (HTGRs) or CANDU reactors will require the smallest accelerator power, especially if thorium is introduced into the newly generated fuel according to the teachings of the present invention. Fast spectrum actinide transmutation apparatus (based on liquid-metal fuel) will take full advantage of the accelerator-produced source neutrons and provide maximum utilization of the actinide-generated fission neutrons. However, near-thermal transmutation apparatus will require lower standing

Venneri, Francesco (Los Alamos, NM); Williamson, Mark A. (Los Alamos, NM); Li, Ning (Los Alamos, NM)

2002-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

T-678: Red Hat Enterprise Virtualization Hypervisor VLAN Packet...  

Broader source: Energy.gov (indexed) [DOE]

8: Red Hat Enterprise Virtualization Hypervisor VLAN Packet Processing Flaw Lets Remote Users Deny Service T-678: Red Hat Enterprise Virtualization Hypervisor VLAN Packet...

362

T-649: Red Hat Network Satellite Server Request Validation Flaw...  

Broader source: Energy.gov (indexed) [DOE]

49: Red Hat Network Satellite Server Request Validation Flaw Permits Cross-Site Request Forgery Attacks T-649: Red Hat Network Satellite Server Request Validation Flaw Permits...

363

U-200: Red Hat Directory Server Information Disclosure Security...  

Broader source: Energy.gov (indexed) [DOE]

0: Red Hat Directory Server Information Disclosure Security Issue and Vulnerability U-200: Red Hat Directory Server Information Disclosure Security Issue and Vulnerability June 27,...

364

Spent Shale Grouting of Abandoned In-Situ Oil Shale Retorts  

E-Print Network [OSTI]

for the grout. SPENT SHALE Oil shale, which is a low-gradeMineral Reactions in Colorado Oil Shale," Lawrence Livermore1978. of Decomposition of Colorado Oil Shale: II. Livermore

Fox, J.P.; Persoff, P.

1980-01-01T23:59:59.000Z

365

EIS-0306: Treatment and Management of Sodium-Bonded Spent Nuclear Fuel  

Broader source: Energy.gov [DOE]

This EIS evaluates thepotential environmental impacts of the proposed electrometallurgical treatment of DOE-owned sodium bonded spent nuclear fuel in the Fuel Conditioning Facility at Argonne...

366

324 Building spent fuel segments pieces and fragments removal summary report  

SciTech Connect (OSTI)

As part of the 324 Building Deactivation Project, all Spent Nuclear Fuel (SNF) and Special Nuclear Material were removed. The removal entailed packaging the material into a GNS-12 cask and shipping it to the Central Waste Complex (CWC).

SMITH, C L

2003-01-09T23:59:59.000Z

367

Concrete Shield Performance of the VSC-17 Spent Nuclear Fuel Cask  

SciTech Connect (OSTI)

The VSC-17 Spent Nuclear Fuel Storage Cask was surveyed for degradation of the concrete shield by radiation measurement, temperature measurement, and ultrasonic testing. No general loss of shielding function was identified.

Koji Shirai

2006-04-01T23:59:59.000Z

368

EA-1117: Management of Spent Nuclear Fuel on the Oak Ridge Reservation, Oak Ridge, Tennessee  

Broader source: Energy.gov [DOE]

This EA evaluates the environmental impacts of the proposal for the management of spent nuclear fuel on the U.S. Department of Energy's Oak Ridge Reservation to implement the preferred alternative...

369

Advanced dry head-end reprocessing of light water reactor spent nuclear fuel  

SciTech Connect (OSTI)

A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450.degree. C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gas comprising nitrogen monoxide and oxygen at a temperature ranging from 0-80.degree. C. The first zone and the second zone can be separate. A voloxidation system is also disclosed.

Collins, Emory D.; Delcul, Guillermo D.; Hunt, Rodney D.; Johnson, Jared A.; Spencer, Barry B.

2014-06-10T23:59:59.000Z

370

The characteristic assessment of spent ion exchange resin from PUSPATI TRIGA REACTOR (RTP) for immobilization process  

SciTech Connect (OSTI)

In this paper, spent ion exchange resin generated from PUSPATI TRIGA reactor (RTP) in Malaysian Nuclear Agency were characterized based on the water content, radionuclide content and radionuclide leachability. The result revealed that the water content in the spent resin is 48%. Gamma spectrometry analysis indicated the presence of {sup 134}Cs, {sup 137}Cs, {sup 152}Eu, {sup 54}Mn, {sup 58}Co, {sup 60}Co and {sup 65}Zn. The leachability test shows a small concentrations (<1 Bq/l) of {sup 152}Eu and {sup 134}Cs were leached out from the spent resin while {sup 60}Co activity concentrations slightly exceeded the limit generally used for industrial wastewater i.e. 1 Bq/l. Characterization of spent ion exchange resin sampled from RTP show that this characterization is important as a basis to immobilize this radioactive waste using geopolymer technology.

Wahida, Nurul [School of Applied Physics, Universiti Kebangsaan Malaysia, 43600 Bangi, Selangor, Malaysia and Malaysian Nuclear Agency, Bangi 43000 Kajang, Selangor (Malaysia); Yasir, Muhamad Samudi; Majid, Amran Ab; Irwan, M. N. [School of Applied Physics, Universiti Kebangsaan Malaysia, 43600 Bangi, Selangor (Malaysia); Wahab, Mohd Abd; Marzukee, Nik; Paulus, Wilfred; Phillip, Esther; Thanaletchumy [Malaysian Nuclear Agency, Bangi 43000 Kajang, Selangor (Malaysia)

2014-09-03T23:59:59.000Z

371

Advanced dry head-end reprocessing of light water reactor spent nuclear fuel  

DOE Patents [OSTI]

A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450.degree. C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gas comprising nitrogen monoxide and oxygen at a temperature ranging from 0-80.degree. C. The first zone and the second zone can be separate. A voloxidation system is also disclosed.

Collins, Emory D; Delcul, Guillermo D; Hunt, Rodney D; Johnson, Jared A; Spencer, Barry B

2013-11-05T23:59:59.000Z

372

Development of Gd-Enriched Alloys for Spent Nuclear Fuel Applications--Part 1: Preliminary Characterization  

E-Print Network [OSTI]

of Gd-containing alloys for storage, transport, and disposal of spent nuclear fuel. However, unlike, the basket materials must be corrosion resistant under the projected stor- age conditions. Recent research

DuPont, John N.

373

Standard guide for characterization of spent nuclear fuel in support of geologic repository disposal  

E-Print Network [OSTI]

1.1 This guide provides guidance for the types and extent of testing that would be involved in characterizing the physical and chemical nature of spent nuclear fuel (SNF) in support of its interim storage, transport, and disposal in a geologic repository. This guide applies primarily to commercial light water reactor (LWR) spent fuel and spent fuel from weapons production, although the individual tests/analyses may be used as applicable to other spent fuels such as those from research and test reactors. The testing is designed to provide information that supports the design, safety analysis, and performance assessment of a geologic repository for the ultimate disposal of the SNF. 1.2 The testing described includes characterization of such physical attributes as physical appearance, weight, density, shape/geometry, degree, and type of SNF cladding damage. The testing described also includes the measurement/examination of such chemical attributes as radionuclide content, microstructure, and corrosion product c...

American Society for Testing and Materials. Philadelphia

2009-01-01T23:59:59.000Z

374

International management of spent fuel storage : technical alternatives and constraints, topical report  

E-Print Network [OSTI]

Some of the important technical issues involved in the implementation of a spent fuel storage regime under international auspices are discussed. In particular, we consider: the state of the art as far as the different ...

Miller, Marvin M.

1978-01-01T23:59:59.000Z

375

THE TEMPERATURES OF RED SUPERGIANTS  

SciTech Connect (OSTI)

We present a re-appraisal of the temperatures of red supergiants (RSGs) using their optical and near-infrared spectral energy distributions (SEDs). We have obtained data of a sample of RSGs in the Magellanic Clouds using VLT+XSHOOTER, and we fit MARCS model atmospheres to different regions of the spectra, deriving effective temperatures for each star from (1) the TiO bands, (2) line-free continuum regions of the SEDs, and (3) the integrated fluxes. We show that the temperatures derived from fits to the TiO bands are systematically lower than the other two methods by several hundred kelvin. The TiO fits also dramatically overpredict the flux in the near-IR, and imply extinctions which are anomalously low compared to neighboring stars. In contrast, the SED temperatures provide good fits to the fluxes at all wavelengths other than the TiO bands, are in agreement with the temperatures from the flux integration method, and imply extinctions consistent with nearby stars. After considering a number of ways to reconcile this discrepancy, we conclude that three-dimensional effects (i.e., granulation) are the most likely cause, as they affect the temperature structure in the upper layers where the TiO lines form. The continuum, however, which forms at much deeper layers, is apparently more robust to such effects. We therefore conclude that RSG temperatures are much warmer than previously thought. We discuss the implications of this result for stellar evolution and supernova progenitors, and provide relations to determine the bolometric luminosities of RSGs from single-band photometry.

Davies, Ben [Astrophysics Research Institute, Liverpool John Moores University, Egerton Wharf, Birkenhead CH41 1LD (United Kingdom)] [Astrophysics Research Institute, Liverpool John Moores University, Egerton Wharf, Birkenhead CH41 1LD (United Kingdom); Kudritzki, Rolf-Peter; Gazak, Zach [Institute for Astronomy, University of Hawaii, 2680 Woodlawn Drive, Honolulu, HI 96822 (United States)] [Institute for Astronomy, University of Hawaii, 2680 Woodlawn Drive, Honolulu, HI 96822 (United States); Plez, Bertrand [Laboratoire Univers et Particules de Montpellier, Universite Montpellier 2, CNRS, F-34095 Montpellier (France)] [Laboratoire Univers et Particules de Montpellier, Universite Montpellier 2, CNRS, F-34095 Montpellier (France); Trager, Scott [Kapteyn Institute, University of Groningen, P.O. Box 800, 9700-AV Groningen (Netherlands)] [Kapteyn Institute, University of Groningen, P.O. Box 800, 9700-AV Groningen (Netherlands); Lancon, Ariane [Observatoire Astronomique and CNRS UMR 7550, Universite de Strasbourg, F-67000 Strasbourg (France)] [Observatoire Astronomique and CNRS UMR 7550, Universite de Strasbourg, F-67000 Strasbourg (France); Bergemann, Maria [Max-Planck-Institute for Astrophysics, Karl-Schwarzschild-Str. 1, D-85741 Garching (Germany)] [Max-Planck-Institute for Astrophysics, Karl-Schwarzschild-Str. 1, D-85741 Garching (Germany); Evans, Chris [UK Astronomy Technology Centre, Royal Observatory Edinburgh, Blackford Hill, Edinburgh EH9 3HJ (United Kingdom)] [UK Astronomy Technology Centre, Royal Observatory Edinburgh, Blackford Hill, Edinburgh EH9 3HJ (United Kingdom); Chiavassa, Andrea [CNRS Laboratoire Lagrange, Universite de Nice Sophia-Antipolis, Observatoire de la Cote d'Azur, BP 4229, F-06304 Nice Cedex 4 (France)] [CNRS Laboratoire Lagrange, Universite de Nice Sophia-Antipolis, Observatoire de la Cote d'Azur, BP 4229, F-06304 Nice Cedex 4 (France)

2013-04-10T23:59:59.000Z

376

Redding Electric- Earth Advantage Rebate Program  

Broader source: Energy.gov [DOE]

The Earth Advantage Rebate Program was designed to offer rebates to residential and business customers of Redding Electric Utility (REU) for solar PV, solar thermal, and geothermal heat pump...

377

Viscoelastic transient of confined Red Blood Cells  

E-Print Network [OSTI]

The unique ability of a red blood cell to flow through extremely small microcapillaries depends on the viscoelastic properties of its membrane. Here, we study in vitro the response time upon flow startup exhibited by red blood cells confined into microchannels. We show that the characteristic transient time depends on the imposed flow strength, and that such a dependence gives access to both the effective viscosity and the elastic modulus controlling the temporal response of red cells. A simple theoretical analysis of our experimental data, validated by numerical simulations, further allows us to compute an estimate for the two-dimensional membrane viscosity of red blood cells, $\\eta_{mem}^{2D}\\sim 10^{-7}$ N$\\cdot$s$\\cdot$m$^{-1}$. By comparing our results with those from previous studies, we discuss and clarify the origin of the discrepancies found in the literature regarding the determination of $\\eta_{mem}^{2D}$, and reconcile seemingly conflicting conclusions from previous works.

Gal Prado; Alexander Farutin; Chaouqi Misbah; Lionel Bureau

2014-09-17T23:59:59.000Z

378

Right Turn on Red! | Department of Energy  

Broader source: Energy.gov (indexed) [DOE]

benefits for the country, helping us all save money by saving energy. Prior to the 1970's, some states already allowed drivers to turn right on a red light, but many others -...

379

Conceptual design report for the ICPP spent nuclear fuel dry storage project  

SciTech Connect (OSTI)

The conceptual design is presented for a facility to transfer spent nuclear fuel from shipping casks to dry storage containers, and to safely store those containers at ICPP at INEL. The spent fuels to be handled at the new facility are identified and overall design and operating criteria established. Physical configuration of the facility and the systems used to handle the SNF are described. Detailed cost estimate for design and construction of the facility is presented.

NONE

1996-07-01T23:59:59.000Z

380

The French national program for spent fuel and high-level waste management  

SciTech Connect (OSTI)

From its very beginning, the French national program for spent fuel and HLW management is aimed at the recycling of energetic materials and the safe disposal of nuclear waste. Spent fuel reprocessing is the cornerstone of this program, since it directly opens the way to energetic material recycling, waste minimization and safe conditioning. It is complemented by the HLW management program which is defined by the HLW disposal regulation and the Waste Act issued in 1991.

Giraud, J.P.; Demontalembert, J.A. [COGEMA, Velizy-Villacoublay (France)

1993-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Licensing of spent fuel dry storage and consolidated rod storage: A Review of Issues and Experiences  

SciTech Connect (OSTI)

The results of this study, performed by Pacific Northwest Laboratory (PNL) and sponsored by the US Department of Energy (DOE), respond to the nuclear industry's recommendation that a report be prepared that collects and describes the licensing issues (and their resolutions) that confront a new applicant requesting approval from the US Nuclear Regulatory Commission (NRC) for dry storage of spent fuel or for large-scale storage of consolidated spent fuel rods in pools. The issues are identified in comments, questions, and requests from the NRC during its review of applicants' submittals. Included in the report are discussions of (1) the 18 topical reports on cask and module designs for dry storage fuel that have been submitted to the NRC, (2) the three license applications for dry storage of spent fuel at independent spent fuel storage installations (ISFSIs) that have been submitted to the NRC, and (3) the three applications (one of which was later withdrawn) for large-scale storage of consolidated fuel rods in existing spent fuel storage pools at reactors that were submitted tot he NRC. For each of the applications submitted, examples of some of the issues (and suggestions for their resolutions) are described. The issues and their resolutions are also covered in detail in an example in each of the three subject areas: (1) the application for the CASTOR V/21 dry spent fuel storage cask, (2) the application for the ISFSI for dry storage of spent fuel at Surry, and (3) the application for full-scale wet storage of consolidated spent fuel at Millstone-2. The conclusions in the report include examples of major issues that applicants have encountered. Recommendations for future applicants to follow are listed. 401 refs., 26 tabs.

Bailey, W.J.

1990-02-01T23:59:59.000Z

382

Achieving increased spent fuel storage capacity at the High Flux Isotope Reactor (HFIR)  

SciTech Connect (OSTI)

The HFIR facility was originally designed to store approximately 25 spent cores, sufficient to allow for operational contingencies and for cooling prior to off-site shipment for reprocessing. The original capacity has now been increased to 60 positions, of which 53 are currently filled (September 1994). Additional spent cores are produced at a rate of about 10 or 11 per year. Continued HFIR operation, therefore, depends on a significant near-term expansion of the pool storage capacity, as well as on a future capability of reprocessing or other storage alternatives once the practical capacity of the pool is reached. To store the much larger inventory of spent fuel that may remain on-site under various future scenarios, the pool capacity is being increased in a phased manner through installation of a new multi-tier spent fuel rack design for higher density storage. A total of 143 positions was used for this paper as the maximum practical pool capacity without impacting operations; however, greater ultimate capacities were addressed in the supporting analyses and approval documents. This paper addresses issues related to the pool storage expansion including (1) seismic effects on the three-tier storage arrays, (2) thermal performance of the new arrays, (3) spent fuel cladding corrosion concerns related to the longer period of pool storage, and (4) impacts of increased spent fuel inventory on the pool water quality, water treatment systems, and LLLW volume.

Cook, D.H.; Chang, S.J.; Dabs, R.D.; Freels, J.D.; Morgan, K.A.; Rothrock, R.B. [Oak Ridge National Lab., TN (United States); Griess, J.C. [Griess (J.C.), Knoxville, TN (United States)

1994-12-31T23:59:59.000Z

383

Deployment evaluation methodology for the electrometallurgical treatment of DOE-EM spent nuclear fuel  

SciTech Connect (OSTI)

Part of the Department of Energy (DOE) spent nuclear fuel (SNF) inventory may require some type of treatment to meet acceptance criteria at various disposition sites. The current focus for much of this spent nuclear fuel is the electrometallurgical treatment process under development at Argonne National Laboratory. Potential flowsheets for this treatment process are presented. Deployment of the process for the treatment of the spent nuclear fuel requires evaluation to determine the spent nuclear fuel program need for treatment and compatibility of the spent nuclear fuel with the process. The evaluation of need includes considerations of cost, technical feasibility, process material disposition, and schedule to treat a proposed fuel. A siting evaluation methodology has been developed to account for these variables. A work breakdown structure is proposed to gather life-cycle cost information to allow evaluation of alternative siting strategies on a similar basis. The evaluation methodology, while created specifically for the electrometallurgical evaluation, has been written such that it could be applied to any potential treatment process that is a disposition option for spent nuclear fuel. Future work to complete the evaluation of the process for electrometallurgical treatment is discussed.

Dahl, C.A.; Adams, J.P.; Ramer, R.J.

1998-07-01T23:59:59.000Z

384

MANAGING SPENT NUCLEAR FUEL WASTES AT THE IDAHO NATIONAL LABORATORY  

SciTech Connect (OSTI)

The Idaho National Engineering Laboratory (INL) has a large inventory of diverse types of spent nuclear fuel (SNF). This legacy is in part due to the history of the INL as the National Reactor Testing Station, in part to its mission to recover highly enriched uranium from SNF and in part to its mission to test and examine SNF after irradiation. The INL also has a large diversity of SNF storage facility, some dating back 50 years in the site history. The success of the INL SNF program is measured by its ability to: 1) achieve safe existing storage, 2) continue to receive SNF from other locations, both foreign and domestic, 3) repackage SNF from wet storage to interim dry storage, and 4) prepare the SNF for dispositioning in a federal repository. Because of the diversity in the SNF and the facilities at the INL, the INL is addressing almost very condition that may exist in the SNF world. Many of solutions developed by the INL are applicable to other SNF storage sites as they develop their management strategy. The SNF being managed by the INL are in a variety of conditions, from intact assemblies to individual rods or plates to powders, rubble, and metallurgical mounts. Some of the fuel has been in wet storage for over forty years. The fuel is stored bare, or in metal cans and either wet under water or dry in vaults, caissons or casks. Inspections have shown varying degrees of corrosion and degradation of the fuel and the storage cans. Some of the fuel has been recanned under water, and the conditions of the fuel inside the second or third can are unknown. The fuel has been stored in one of 10 different facilities: five wet pools and one casks storage pad, one vault, two generations of caisson facilities, and one modular Independent Spent Fuel Storage Installation (ISFSI). The wet pools range from forty years old to the most modern pool in the US Department of Energy (DOE) complex. The near-term objective is moving the fuel in the older wet storage facilities to interim dry storage facilities, thus permitting the shutdown and decommission of the older facilities. Two wet pool facilities, one at the Idaho Nuclear Technology and Engineering Center and the other at Test Area North, were targeted for initial SNF movements since these were some of the oldest at the INL. Because of the difference in the SNF materials different types of drying processes had to be developed. Passive drying, as is done with typical commercial SNF was not an option because on the condition of some of the fuel, the materials to be dried, and the low heat generation of some of the SNF. There were also size limitations in the existing facility. Active dry stations were designed to address the specific needs of the SNF and the facilities.

Hill, Thomas J

2005-09-01T23:59:59.000Z

385

Uncanistered Spent Nuclear fuel Disposal Container System Description Document  

SciTech Connect (OSTI)

The Uncanistered Spent Nuclear Fuel (SNF) Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded with intact uncanistered assemblies and/or individually canistered SNF assemblies and sealed in the surface waste handling facilities, transferred to the underground through the access drifts, and emplaced in the emplacement drifts. The Uncanistered SNF Disposal Container provides long-term confinement of the commercial SNF placed inside, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The Uncanistered SNF Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual SNF assembly temperatures after emplacement, limits the introduction of moderator into the disposal container during the criticality control period, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Multiple boiling water reactor (BWR) and pressurized water reactor (PWR) disposal container designs are needed to accommodate the expected range of spent fuel assemblies and provide long-term confinement of the commercial SNF. The disposal container will include outer and inner cylinder walls, outer cylinder lids (two on the top, one on the bottom), inner cylinder lids (one on the top, one on the bottom), and an internal metallic basket structure. Exterior labels will provide a means by which to identify the disposal container and its contents. The two metal cylinders, in combination with the cladding, Emplacement Drift System, drip shield, and natural barrier, will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel and the outer cylinder and outer cylinder lid will be made of high-nickel alloy. The basket will assist criticality control, provide structural support, and improve heat transfer. The Uncanistered SNF Disposal Container System interfaces with the emplacement drift environment and internal waste by transferring heat from the SNF to the external environment and by protecting the SFN assemblies and their contents from damage/degradation by the external environment. The system also interfaces with the SFN by limiting access of moderator and oxidizing agents of the SFN. The waste package interfaces with the Emplacement Drift System's emplacement drift pallets upon which the wasted packages are placed. The disposal container interfaces with the Assembly Transfer System, Waste Emplacement/Retrieval System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement and retrieval of the disposal container/waste package.

NONE

2000-10-12T23:59:59.000Z

386

POPULATION BIOLOGY OF RED ABAWNES, HALIOTIS RUFESCENS, IN SOUTHERN CALIFORNIA AND MANAGEMENT OF THE RED AND  

E-Print Network [OSTI]

ABSTRACT Population dynamics of red abalones. Hal·wti.s rufeSC611,8 Swainson. were studied at Johnsons Lee

387

Spent Nuclear Fuel (SNF) Project Design Basis Capacity Study  

SciTech Connect (OSTI)

This study of the design basis capacity of process systems was prepared by Fluor Federal Services for the Spent Nuclear Fuel Project. The evaluation uses a summary level model of major process sub-systems to determine the impact of sub-system interactions on the overall time to complete fuel removal operations. The process system model configuration and time cycle estimates developed in the original version of this report have been updated as operating scenario assumptions evolve. The initial document released in Fiscal Year (FY) 1996 varied the number of parallel systems and transport systems over a wide range, estimating a conservative design basis for completing fuel processing in a two year time period. Configurations modeling planned operations were updated in FY 1998 and FY 1999. The FY 1998 Base Case continued to indicate that fuel removal activities at the basins could be completed in slightly over 2 years. Evaluations completed in FY 1999 were based on schedule modifications that delayed the start of KE Basin fuel removal, with respect to the start of KW Basin fuel removal activities, by 12 months. This delay resulted in extending the time to complete all fuel removal activities by 12 months. However, the results indicated that the number of Cold Vacuum Drying (CVD) stations could be reduced from four to three without impacting the projected time to complete fuel removal activities. This update of the design basis capacity evaluation, performed for FY 2000, evaluates a fuel removal scenario that delays the start of KE Basin activities such that staffing peaks are minimized. The number of CVD stations included in all cases for the FY 2000 evaluation is reduced from three to two, since the scenario schedule results in minimal time periods of simultaneous fuel removal from both basins. The FY 2000 evaluation also considers removal of Shippingport fuel from T Plant storage and transfer to the Canister Storage Building for storage.

CLEVELAND, K.J.

2000-08-17T23:59:59.000Z

388

Newtonian gravity, red shift, confinement, asymptotic freedom and quarks oscillations  

E-Print Network [OSTI]

Quarks oscillations give the Newtonian gravity law, the red shift, the confinement and the asymptotic freedom.

G. Quznetsov

2008-10-18T23:59:59.000Z

389

Improved ``Optical Highlighter'' Probes Derived from Discosoma Red Fluorescent Protein  

E-Print Network [OSTI]

, Minneapolis, Minnesota ABSTRACT The tetrameric red fluorescent protein, DsRed, undergoes a rapid red to green-emitting species of DsRed and an enhancement of emission from the ``immature'' green species, likely caused by dequenching of fluorescence resonance energy transfer occurring within the protein tetramer. Here, we have

Marchant, Jonathan

390

Bureau of Commercial Fisheries Symposium on Red Tide  

E-Print Network [OSTI]

21 Bureau of Commercial Fisheries Symposium on Red Tide By James E. Sykes Marine Biological, Donald L. McKernan, Director Bureau of Commercial Fisheries Symposium on Red Tide By James E. Sykes causing Red-Tide blooms as deduced from field observations 2 Red- Tide research at the Florida State

391

Red giant variables: OGLE--II and MACHO  

E-Print Network [OSTI]

We review the recent impact of microlensing projects on our understanding of pulsating red giant stars. Discussed are red giant stars' pulsation properties (period--luminosity relations, period changes, mode switchings), Red Giant Branch pulsations, metallicity effects and the use of red giant variables to explore galactic structure.

L. L. Kiss; P. Lah

2005-09-21T23:59:59.000Z

392

A monomeric red fluorescent protein Robert E. Campbell*, Oded Tour*  

E-Print Network [OSTI]

A monomeric red fluorescent protein Robert E. Campbell*, Oded Tour* , Amy E. Palmer*, Paul A, and the obligate tetramerization of the red fluorescent protein from Discosoma (DsRed). Although the weak, the obligate tet- ramerization of DsRed has greatly hindered its use as a genetically encoded fusion tag. We

Tsien, Roger Y.

393

RED Revisited Tuan Anh Trinh and Sandor Molnar  

E-Print Network [OSTI]

RED Revisited Tuan Anh Trinh and S´andor Moln´ar High Speed Networks Laboratory Department- ternet is RED. However, research results on RED perfor- mance are highly mixed, especially in the field of tuning its parameters. In this paper, we revisit some features in RED and study them in greater details

Molnár, Sándor

394

UK Red Squirrel Group Terms of Reference Introduction  

E-Print Network [OSTI]

UK Red Squirrel Group Terms of Reference Introduction The red squirrel Sciurus vulgaris has of the Bern Convention, is Lower Risk ­near threatened on the IUCN Red List and is protected under Schedules 5-ordinate, support and provide advice on the implementation of conservation measures for the red squirrel in the UK

395

Guide to Red Fluorescent Proteins and Biosensors for Flow Cytometry  

E-Print Network [OSTI]

CHAPTER 17 Guide to Red Fluorescent Proteins and Biosensors for Flow Cytometry Kiryl D. PiatkevichH Stability of Fluorescence F. Optimization of Nucleotide and Amino Acid Sequences III. Modern Advanced Red-Shifted FPs A. Orange Fluorescent Proteins B. Red Fluorescent Proteins C. Far-Red Fluorescent Proteins IV

Verkhusha, Vladislav V.

396

Red fluorescent proteins: chromophore formation and cellular applications  

E-Print Network [OSTI]

Red fluorescent proteins: chromophore formation and cellular applications Atsushi Miyawaki1,2 , Daria M Shcherbakova3,4 and Vladislav V Verkhusha3,4 In the last decade, a number of red fluorescent proteins (RFPs) that emit orange, red, and far-red fluorescence have been isolated from anthozoans (corals

Verkhusha, Vladislav V.

397

RED Revisited Tuan Anh Trinh and Sandor Molnar  

E-Print Network [OSTI]

RED Revisited Tuan Anh Trinh and S??andor Moln??ar High Speed Networks Laboratory Department­ ternet is RED. However, research results on RED perfor­ mance are highly mixed, especially in the field of tuning its parameters. In this paper, we revisit some features in RED and study them in greater details

Molnár, Sándor

398

UK RED SQUIRREL GROUP WEDNESDAY 7 OCTOBER 2009  

E-Print Network [OSTI]

1 UK RED SQUIRREL GROUP WEDNESDAY 7 OCTOBER 2009 Northumberland Wildlife Trust Newcastle MINUTES in conjunction with grey squirrel culling, the outcome for the red squirrel has substantially improved.with 11 red squirrels and 24 grey squirrels recorded in 2004 changing to 103 red squirrels and 3 grey

399

MFR PAPER 1229 Red Snappers of the Carolina Coast  

E-Print Network [OSTI]

Coast to the Campeche Banks. A closely related species, the Caribbean red snapper, Lutjanus pur- pureus

400

COBRA-SFS (Spent-Fuel Storage) thermal-hydraulic analyses of the CASTOR-1C and REA 2023 BWR storage casks containing consolidated spent fuel  

SciTech Connect (OSTI)

Consolidation of spent nuclear fuel rods is being considered as one option for more efficient and compact storage of reactor spent fuel assemblies. In this concept, rods from two disassembled spent fuel assemblies will be consolidated in a space originally intended to store a single unconsolidated assembly. The thermal performance of consolidated fuel rods in dry storage, especially in multiassembly storage systems, is one of the major issues that must be addressed prior to implementation. In this study, Pacific Northwest Laboratory researchers performed thermal-hydraulic analyses for both the REA 2023 cask and the CASTOR-1C cask containing either unconsolidated or consolidated BWR spent fuel assemblies. The objective was to determine the effect of consolidating spent fuel assemblies on the temperature distributions within both types of casks. Two major conclusions resulted from this study. First, a lumping technique (combining rods and flow channels), which reduces the number of computational nodes required to model complex multiassembly geometries, could be used for both unconsolidated and consolidated rods with negligible effect on prediction accuracies. Second, with a relatively high thermal conductivity backfill gas (e.g., helium), the predicted peak fuel rod temperature in a canister of consolidated rods generating the same amount of heat as an unconsolidated assembly is essentially the same as the peak temperature in the unconsolidated assembly. In contrast, with a relatively low thermal conductivity backfill gas (e.g., nitrogen), the opposite is true and the predicted peak temperature in a consolidated canister is significantly higher than in an unconsolidated assembly. Therefore, when rods are consolidated, selection of the backfill gas is important in maintaining peak rod temperatures below allowable values for rods with relatively high decay heat generation rates.

Rector, D.R.; Cuta, J.M.; Lombardo, N.J.

1986-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Conserving Scotland's Red Squirrels Scotland supports an estimated 75% of the UK red squirrel population. Although one  

E-Print Network [OSTI]

Conserving Scotland's Red Squirrels Scotland supports an estimated 75% of the UK red squirrel population. Although one of the most popular mammal species in the country, red squirrels currently face a number of ecological problems and their range within the UK has been much reduced. It means that the red

402

CUTTING SOLAR RED TAPECUTTING SOLAR RED TAPE Evergreen State Solar PartnershipEvergreen State Solar Partnership  

E-Print Network [OSTI]

CUTTING SOLAR RED TAPECUTTING SOLAR RED TAPE Evergreen State Solar PartnershipEvergreen State Solar Partnership Rooftop Solar Challenge 1 Sunshot #12;WASHINGTON PV CONTEXTWASHINGTON PV CONTEXT 285 cities, 39 Installations happen where process is easier #12;EVERGREEN STATE SOLAR PARTNERSHIP Commerce NWSEEDEdmonds

403

7X performance results - final report : ASCI Red vs Red Storm.  

SciTech Connect (OSTI)

The goal of the 7X performance testing was to assure Sandia National Laboratories, Cray Inc., and the Department of Energy that Red Storm would achieve its performance requirements which were defined as a comparison between ASCI Red and Red Storm. Our approach was to identify one or more problems for each application in the 7X suite, run those problems at multiple processor sizes in the capability computing range, and compare the results between ASCI Red and Red Storm. The first part of this report describes the two computer systems, the applications in the 7X suite, the test problems, and the results of the performance tests on ASCI Red and Red Storm. During the course of the testing on Red Storm, we had the opportunity to run the test problems in both single-core mode and dual-core mode and the second part of this report describes those results. Finally, we reflect on lessons learned in undertaking a major head-to-head benchmark comparison.

Dinge, Dennis C. (Cray Inc., Albuquerque, NM); Davis, Michael E. (Cray Inc., Albuquerque, NM); Haskell, Karen H.; Ballance, Robert A.; Gardiner, Thomas Anthony; Stevenson, Joel O.; Noe, John P.

2011-04-01T23:59:59.000Z

404

Spent nuclear fuel integrity during dry storage - performance tests and demonstrations  

SciTech Connect (OSTI)

This report summarizes the results of fuel integrity surveillance determined from gas sampling during and after performance tests and demonstrations conducted from 1983 through 1996 by or in cooperation with the US DOE Office of Commercial Radioactive Waste Management (OCRWM). The cask performance tests were conducted at Idaho National Engineering Laboratory (INEL) between 1984 and 1991 and included visual observation and ultrasonic examination of the condition of the cladding, fuel rods, and fuel assembly hardware before dry storage and consolidation of fuel, and a qualitative determination of the effects of dry storage and fuel consolidation on fission gas release from the spent fuel rods. The performance tests consisted of 6 to 14 runs involving one or two loading, usually three backfill environments (helium, nitrogen, and vacuum backfills), and one or two storage system orientations. The nitrogen and helium backfills were sampled and analyzed to detect leaking spent fuel rods. At the end of each performance test, periodic gas sampling was conducted on each cask. A spent fuel behavior project (i.e., enhanced surveillance, monitoring, and gas sampling activities) was initiated by DOE in 1994 for intact fuel in a CASTOR V/21 cask and for consolidated fuel in a VSC-17 cask. The results of the gas sampling activities are included in this report. Information on spent fuel integrity is of interest in evaluating the impact of long-term dry storage on the behavior of spent fuel rods. Spent fuel used during cask performance tests at INEL offers significant opportunities for confirmation of the benign nature of long-term dry storage. Supporting cask demonstration included licensing and operation of an independent spent fuel storage installation (ISFSI) at the Virginia Power (VP) Surry reactor site. A CASTOR V/21, an MC-10, and a Nuclear Assurance NAC-I28 have been loaded and placed at the VP ISFSI as part of the demonstration program. 13 refs., 14 figs., 9 tabs.

McKinnon, M.A.; Doherty, A.L.

1997-06-01T23:59:59.000Z

405

Spent fuel sabotage aerosol ratio program : FY 2004 test and data summary.  

SciTech Connect (OSTI)

This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program has been underway for several years. This program provides data that are relevant to some sabotage scenarios in relation to spent fuel transport and storage casks, and associated risk assessments. The program also provides significant technical and political benefits in international cooperation. We are quantifying the Spent Fuel Ratio (SFR), the ratio of the aerosol particles released from HEDD-impacted actual spent fuel to the aerosol particles produced from surrogate materials, measured under closely matched test conditions, in a contained test chamber. In addition, we are measuring the amounts, nuclide content, size distribution of the released aerosol materials, and enhanced sorption of volatile fission product nuclides onto specific aerosol particle size fractions. These data are the input for follow-on modeling studies to quantify respirable hazards, associated radiological risk assessments, vulnerability assessments, and potential cask physical protection design modifications. This document includes an updated description of the test program and test components for all work and plans made, or revised, during FY 2004. It also serves as a program status report as of the end of FY 2004. All available test results, observations, and aerosol analyses plus interpretations--primarily for surrogate material Phase 2 tests, series 2/5A through 2/9B, using cerium oxide sintered ceramic pellets are included. Advanced plans and progress are described for upcoming tests with unirradiated, depleted uranium oxide and actual spent fuel test rodlets. This spent fuel sabotage--aerosol test program is coordinated with the international Working Group for Sabotage Concerns of Transport and Storage Casks (WGSTSC) and supported by both the U.S. Department of Energy and the Nuclear Regulatory Commission.

Brucher, Wenzel (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Koch, Wolfgang (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Pretzsch, Gunter Guido (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Loiseau, Olivier (Institut de Radioprotection et de Surete Nucleaire, France); Mo, Tin (U.S. Nuclear Regulatory Commission, Washington, DC); Billone, Michael C. (Argonne National Laboratory, Argonne, IL); Autrusson, Bruno A. (Institut de Radioprotection et de Surete Nucleaire, France); Young, F. I. (U.S. Nuclear Regulatory Commission, Washington, DC); Coats, Richard Lee; Burtseva, Tatiana (Argonne National Laboratory, Argonne, IL); Luna, Robert Earl; Dickey, Roy R.; Sorenson, Ken Bryce; Nolte, Oliver (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Thompson, Nancy Slater (U.S. Department of Energy, Washington, DC); Hibbs, Russell S. (U.S. Department of Energy, Washington, DC); Gregson, Michael Warren; Lange, Florentin (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Molecke, Martin Alan; Tsai, Han-Chung (Argonne National Laboratory, Argonne, IL)

2005-07-01T23:59:59.000Z

406

Red mud characterization using nuclear analytical techniques  

SciTech Connect (OSTI)

Red mud is a toxic waste left as a byproduct in aluminum production Bayer process. Since it contains significant concentrations of other chemical elements interesting for industry, including REE, it is also potential secondary ore source. Recent events in some countries have shown that red mud presents a serious environmental hazard if not properly stored. The subject of our study is the red mud from an ex-aluminum plant in Obrovac, Croatia, left from processing of bauxite mined during late 70's and early 80's at the eastern Adriatic coast and since than stored in open concrete basins for more than 30 years. We have used energy dispersive x-ray fluorescence analysis (both tube and radioactive source excitation), fast neutron activation analysis and passive gamma spectrometry to identify a number of elements present in the red mud, their concentration levels and radioactivity in the red mud. The high concentrations of Al, Si, Ca, Ti and Fe have been measured. Chemical elements Sc, Cr, Mn, Co, Ni, Cu, Zn, Ga, As, Se, Br, Y, La, Ce, Pr, Nd, Sm, Eu, Gd, Tb, Dy, Ho, Er, Tm, Pb, Th and U were found in lower concentrations. No significant levels of radioactivity have been measured. (authors)

Obhodas, J.; Sudac, D.; Matjacic, L. [Dept. of Experimental Physics, Inst. Ruder Boskovic, Zagreb (Croatia); Valkovic, V. [A.C.T.d.o.o., Prilesje 4, Zagreb (Croatia)

2011-07-01T23:59:59.000Z

407

Savannah River Site Spent Nuclear Fuel Management Final Environmental Impact Statement  

SciTech Connect (OSTI)

The proposed DOE action considered in this environmental impact statement (EIS) is to implement appropriate processes for the safe and efficient management of spent nuclear fuel and targets at the Savannah River Site (SRS) in Aiken County, South Carolina, including placing these materials in forms suitable for ultimate disposition. Options to treat, package, and store this material are discussed. The material included in this EIS consists of approximately 68 metric tons heavy metal (MTHM) of spent nuclear fuel 20 MTHM of aluminum-based spent nuclear fuel at SRS, as much as 28 MTHM of aluminum-clad spent nuclear fuel from foreign and domestic research reactors to be shipped to SRS through 2035, and 20 MTHM of stainless-steel or zirconium-clad spent nuclear fuel and some Americium/Curium Targets stored at SRS. Alternatives considered in this EIS encompass a range of new packaging, new processing, and conventional processing technologies, as well as the No Action Alternative. A preferred alternative is identified in which DOE would prepare about 97% by volume (about 60% by mass) of the aluminum-based fuel for disposition using a melt and dilute treatment process. The remaining 3% by volume (about 40% by mass) would be managed using chemical separation. Impacts are assessed primarily in the areas of water resources, air resources, public and worker health, waste management, socioeconomic, and cumulative impacts.

N /A

2000-04-14T23:59:59.000Z

408

MANAGEMENT OF RESEARCH AND TEST REACTOR ALUMINUM SPENT NUCLEAR FUEL - A TECHNOLOGY ASSESSMENT  

SciTech Connect (OSTI)

The Department of Energy's Environmental Management (DOE-EM) Program is responsible for the receipt and storage of aluminum research reactor spent nuclear fuel or used fuel until ultimate disposition. Aluminum research reactor used fuel is currently being stored or is anticipated to be returned to the U.S. and stored at DOE-EM storage facilities at the Savannah River Site and the Idaho Nuclear Technology and Engineering Center. This paper assesses the technologies and the options for safe transportation/receipt and interim storage of aluminum research reactor spent fuel and reviews the comprehensive strategy for its management. The U.S. Department of Energy uses the Appendix A, Spent Nuclear Fuel Acceptance Criteria, to identify the physical, chemical, and isotopic characteristics of spent nuclear fuel to be returned to the United States under the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program. The fuel is further evaluated for acceptance through assessments of the fuel at the foreign sites that include corrosion damage and handleability. Transport involves use of commercial shipping casks with defined leakage rates that can provide containment of the fuel, some of which are breached. Options for safe storage include wet storage and dry storage. Both options must fully address potential degradation of the aluminum during the storage period. This paper focuses on the various options for safe transport and storage with respect to technology maturity and application.

Vinson, D.

2010-07-11T23:59:59.000Z

409

A source-term method for determining spent-fuel transport cask containment requirements: Executive summary  

SciTech Connect (OSTI)

This Executive Summary presents the methodology for determining containment requirements for spent-fuel transport casks under normal and hypothetical accident conditions. Three sources of radioactive material are considered: (1) the spent fuel itself, (2) radioactive material, referred to as CRUD, attached to the outside surfaces of fuel rod cladding, and (3) residual contamination adhering to interior surfaces of the cask cavity. The methodologies for determining the concentrations of freely suspended radioactive materials within a spent-fuel transport cask for these sources are discussed in much greater detail in three companion reports: A Method for Determining the Spent-Fuel Contribution to Transport Cask Containment Requirements,'' Estimate of CRUD Contribution to Shipping Cask Containment Requirements,'' and A Methodology for Estimating the Residual Contamination Contribution to the Source Term in a Spent-Fuel Transport Cask.'' Examples of cask containment requirements that combine the individually determined containment requirements for the three sources are provided, and conclusions from the three companion reports to this Executive Summary are presented.

Sanders, T.L.; Seager, K.D. (Sandia National Labs., Albuquerque, NM (United States)); Reardon, P.C. (GRAM, Inc., Albuquerque, NM (United States))

1993-02-01T23:59:59.000Z

410

The Evolution of Dry Spent Fuel Storage in the United States  

SciTech Connect (OSTI)

This paper reviews the evolution of Dry Spent Fuel storage technology and application in the United States. Dating back to the legislation signed by Jimmy Carter on April 7, 1977, to outlaw spent fuel reprocessing, the nations spent fuel pools are gradually becoming filled to capacity. This has necessitated the development of new technologies to store spent fuel in dry casks, predominantly at nuclear power plant sites, awaiting the availability of the federal repository at Yucca Mountain. Site-specific conditions and changes in types of fuel being discharged from reactors have driven a constant evolution of technologies to support this critical need. This paper provides an overview of those changes, which have influenced the evolution of dry storage technology. Focus is provided more towards current technology and cask loading practices, as opposed to those technologies, which are no longer in heavy use. Detailed pictorial material is presented showing the loading sequences of various systems in current use. This paper provides a critical primer on Dry Spent Fuel Storage technology. It provides anyone who is new to dry storage, or who is contemplating initiating dry storage at a nuclear plant site, with useful background and history upon which to build programmatic decisions. (authors)

McGough, M.S. [Duratek Inc., 695 Bamesley Lane, Alpharetta, GA 30022 (United States); Bland, D.W. [TriVis, Inc., 1001 Yeager Parkway, Pelham, AL 35124 (United States)

2006-07-01T23:59:59.000Z

411

Environmental Assessment of Urgent-Relief Acceptance of Foreign Research Reactor Spent Nuclear Fuel  

SciTech Connect (OSTI)

The Department of Energy has completed the Environmental Assessment (EA) of Urgent-Relief Acceptance of Foreign Research Reactor Spent Nuclear Fuel and issued a Finding of No Significant Impact (FONSI) for the proposed action. The EA and FONSI are enclosed for your information. The Department has decided to accept a limited number of spent nuclear fuel elements (409 elements) containing uranium that was enriched in the United States from eight research reactors in Austria, Denmark, Germany, Greece, the Netherlands, Sweden, and Switzerland. This action is necessary to maintain the viability of a major US nuclear weapons nonproliferation program to limit or eliminate the use of highly enriched uranium in civil programs. The purpose of the EA is to maintain the cooperation of the foreign research reactor operators with the nonproliferation program while a more extensive Environmental Impact Statement (EIS) is prepared on a proposed broader policy involving the acceptance of up to 15,000 foreign research reactor spent fuel elements over a 10 to 15 year period. Based on an evaluation of transport by commercial container liner or chartered vessel, five eastern seaboard ports, and truck and train modes of transporting the spent fuel overland to the Savannah River Sits, the Department has concluded that no significant impact would result from any combination of port and made of transport. In addition, no significant impacts were found from interim storage of spent fuel at the Savannah River Site.

Not Available

1994-04-01T23:59:59.000Z

412

High-solids black liquor firing in pulp and paper industry kraft recovery boilers: Phase Ia - Low-temperature gasifier evaluation. Final report, November 1, 1995--October 31, 1996  

SciTech Connect (OSTI)

This project, conducted under The United States Department of Energy (DOE) Cooperative Agreement DE-FC36-94GO10002/A002, was part of a multiple-phase effort to develop technologies that improve the energy efficiency and economics of chemical process recovery in the pulp and paper industry. The approach taken was to consider two major alternatives in two phases. Phase I, conducted previously, considered means to improve pulp mill recovery boilers using high-solids advanced combustion of black liquor; while this project, Phase la, considered means to recover kraft pulping mill process chemicals by low-temperature black liquor gasification. The principal steps previously proposed in this program were: (1) Evaluate these two technologies, high-solids advanced combustion and gasification, and then select a path forward using the more promising of these two options for future work. (2) Design and construct a pilot-scale unit based on the selected technology, and using that unit, develop the precompetitive data necessary to make commercialization attractive. (3) Develop and deploy a first-of-a-kind (FOAK) commercial unit in a kraft pulp mill. Phase I, which evaluated the high-solids advanced combustion option, was concluded in 1995. Results of that project phase were reported previously. This report describes the work conducted in Phase Ia. The work is described in Sections 1 through 4 and six appendices provide additional detail.

Southards, W.T.; Blude, J.D.; Dickinson, J.A. [and others

1997-06-01T23:59:59.000Z

413

State of Nevada comments on the OCRWM from-reactor spent fuel shipping cask preliminary design reports  

SciTech Connect (OSTI)

The design of spent fuels shipping casks is described. Two casks from two different contractors are presented. The design needs are based on the OCRWM'S program specifications. (CBS)

Halstead, R.J.; Audin, L.; Hoskins, R.E.; Snedeker, D.F.

1990-12-01T23:59:59.000Z

414

A Critical Review of Practice of Equating the Reactivity of Spent Fuel to Fresh Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent Fuel Pool Storage  

SciTech Connect (OSTI)

This research examines the practice of equating the reactivity of spent fuel to that of fresh fuel for the purpose of performing burnup credit criticality safety analyses for PWR spent fuel pool (SFP) storage conditions. The investigation consists of comparing k{sub inf} estimates based on reactivity equivalent fresh fuel enrichment (REFFE) to k{sub inf} estimates using the actual spent fuel isotopics. Analyses of selected storage configurations common in PWR SFPs show that this practice yields nonconservative results (on the order of a few tenths of a percent) in configurations in which the spent fuel is adjacent to higher-reactivity assemblies (e.g., fresh or lower-burned assemblies) and yields conservative results in configurations in which spent fuel is adjacent to lower-reactivity assemblies (e.g., higher-burned fuel or empty cells). When the REFFE is determined based on unborated water moderation, analyses for storage conditions with soluble boron present reveal significant nonconservative results associated with the use of the REFFE. This observation is considered to be important, especially considering the recent allowance of credit for soluble boron up to 5% in reactivity. Finally, it is shown that the practice of equating the reactivity of spent fuel to fresh fuel is acceptable, provided the conditions for which the REFFE was determined remain unchanged. Determination of the REFFE for a reference configuration and subsequent use of the REFFE for different configurations violates the basis used for the determination of the REFFE and, thus, may lead to inaccurate, and possibly, nonconservative estimates of reactivity. A significant concentration ({approximately}2000 ppm) of soluble boron is typically (but not necessarily required to be) present in PWR SFPs, of which only a portion ({le} 500 ppm) may be credited in safety analyses. Thus, a large subcritical margin currently exists that more than accounts for errors or uncertainties associated with the use of the REFFE. Consequently, the findings presented here do not represent a significant safety concern unless/until the subcritical margin associated with the soluble boron (that is not currently explicitly credited) is offset by the uncertainties associated with burnup credit and/or the expanded allowance of credit for the soluble boron.

Wagner, J.C.; Parks, C.V.

2000-09-01T23:59:59.000Z

415

Red River Biodiesel Ltd | Open Energy Information  

Open Energy Info (EERE)

AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home5b9fcbce19 No revisionEnvReviewNonInvasiveExplorationUT-g Grant of Access Permit5-ID-aRECRaton,RFPs Home NameRecurrentRedRedLtd

416

SOURCE OF BURNUP VALUES FOR COMMERCIAL SPENT NUCLEAR FUEL ASSEMBLIES  

SciTech Connect (OSTI)

Waste packages are loaded with commercial spent nuclear fuel (SNF) that satisfies the minimum burnup requirements of a criticality loading curve. The burnup value assigned by the originating nuclear utility to each SNF assembly (assigned burnup) is used to load waste packages in compliance with a criticality loading curve. The burnup provided by a nuclear utility has uncertainties, so conservative calculation methods are used to characterize those uncertainties for incorporation into the criticality loading curves. Procedural safety controls ensure that the correct assembly is loaded into each waste package to prevent a misload that could create a condition affecting the safety margins. Probabilistic analyses show that procedural safety controls can minimize the chance of a misload but can not completely eliminate the possibility. Physical measurements of burnup with instrumentation in the surface facility are not necessary due to the conservative calculation methods used to produce the criticality loading curves. The reactor records assigned burnup of a commercial SNF assembly contains about two percent uncertainty, which is increased to five-percent to ensure conservatism. This five-percent uncertainty is accommodated by adjusting the criticality loading curve. Also, the record keeping methods of nuclear utilities are not uniform and the level of detail required by the NRC has varied over the last several decades. Thus, some SNF assemblies may have assigned burnups that are averages for a batch of assemblies with similar characteristics. Utilities typically have access to more detailed core-follow records that allow the batch average burnup to be changed to an assembly specific burnup. Alternatively, an additional safety margin is incorporated into the criticality loading curve to accommodate SNF assemblies with batch average burnups or greater uncertainties due to the methodology used by the nuclear utility. The utility records provide the assembly identifier, initial {sup 235}U enrichment, and time of discharge from the reactor as well as the assigned burnup, but the distribution. of burnup axially along the assembly length is not provided. The axial burnup profile is maintained within acceptable bounds by the operating conditions of the nuclear reactor and is calculated during preparations to reload a reactor, but the actual burnup profile is not measured. The axial burnup profile is important to the determination of the reactivity of a waste package, so a conservative evaluation of the calculated axial profiles for a large database of SNF has been performed. The product of the axial profile evaluation is a profile that is conservative. Thus, there is no need for physical measurement of the axial profile. The assembly identifier is legible on each SNF assembly and the utility records provide the associated characteristics of the assembly. The conservative methodologies used to determine the criticality loading curve for a waste package provide sufficient margin so that criticality safety is assured for preclosure operations even in the event of a misload. Consideration of misload effects for postclosure time periods is provided by the criticality Features, Events, and Processes (FEPs) analysis. The conservative approaches used to develop and apply the criticality loading curve are thus sufficiently robust that the utility assigned burnup is an adequate source of burnup values, and additional means of verification of assigned burnup through physical measurements are not needed.

BSC

2004-12-01T23:59:59.000Z

417

Fresh and Spent Nuclear Fuel Repatriation from the IRT-2000 Research Reactor Facility, Sofia, Bulgaria  

SciTech Connect (OSTI)

The IRT 2000 research reactor, operated by the Bulgarian Institute for Nuclear Research and Nuclear Energy (INRNE), safely shipped all of their Russian-origin nuclear fuel from the Republic of Bulgaria to the Russian Federation beginning in 2003 and completing in 2008. These fresh and spent fuel shipments removed all highly enriched uranium (HEU) from Bulgaria. The fresh fuel was shipped by air in December 2003 using trucks and a commercial cargo aircraft. One combined spent fuel shipment of HEU and low enriched uranium (LEU) was completed in July 2008 using high capacity VPVR/M casks transported by truck, barge, and rail. The HEU shipments were assisted by the Russian Research Reactor Fuel Return Program (RRRFR) and the LEU spent fuel shipment was funded by Bulgaria. This report describes the work, approvals, organizations, equipment, and agreements required to complete these shipments and concludes with several major lessons learned.

K. J. Allen; T. G. Apostolov; I. S. Dimitrov

2009-03-01T23:59:59.000Z

418

The Universal Canister Strategy in Spent Fuel Reprocessing: UC-C a Real Industrial Improvement  

SciTech Connect (OSTI)

In commercial nuclear activities, spent fuel back end management is a key issue for nuclear countries as spent fuel represent most of national civil nuclear waste legacy. Ensuring public safety and protection of the environment, now and in the future has been and still remains a major commitment, it is still the subject of thorough development efforts and active public debates. Considerable benefits can be obtained from the Universal Canister strategy as implemented in France in spent fuel treatment and waste conditioning based on reprocessing. COGEMA developed sophisticated waste conditioning processes to simplify High Level and Long Lived Intermediate Level Waste storage and final disposal. Main benefits are: waste stabilization by immobilization and encapsulation; ultimate waste toxicity reduction; drastic ultimate waste volume reduction; and ultimate waste packages standardization.

Thomasson, J.; Barithel, S.; Cocaud, A.; Derycke, P.; Pierre, P.

2003-02-25T23:59:59.000Z

419

Criticality safety considerations in the geologic disposal of spent nuclear fuel assemblies  

SciTech Connect (OSTI)

Features of geologic disposal which hamper the demonstration that criticality cannot occur therein include possible changes of shape and form, intrusion of water as a neutron moderator, and selective leaching of spent fuel constituents. If the criticality safety of spent fuel disposal depends on burnup, independent measurements verifying the burnup should be performed prior to disposal. The status of nondestructive analysis method which might provide such verification is discussed. Calculations were performed to assess the potential for increasing the allowed size of a spent fuel disposal canister if potential water intrusion were limited by close-packing the enclosed rods. Several factors were identified which severely limited the potential of this application. The theoretical limit of hexagonal close-packing cannot be achieved due to fuel rod bowing. It is concluded that disposal canisters should be sized on the basis of assumed optimum moderation. Several topics for additional research were identified during this limited study.

Gore, B.F.; McNair, G.W.; Heaberlin, S.W.

1980-05-01T23:59:59.000Z

420

RUSSIAN-ORIGIN HIGHLY ENRICHED URANIUM SPENT NUCLEAR FUEL SHIPMENT FROM BULGARIA  

SciTech Connect (OSTI)

In July 2008, the Global Threat Reduction Initiative and the IRT 2000 research reactor in Sofia, Bulgaria, operated by the Institute for Nuclear Research and Nuclear Energy (INRNE), safely shipped 6.4 kilograms of Russian origin highly enriched uranium (HEU) spent nuclear fuel (SNF) to the Russian Federation. The shipment, which resulted in the removal of all HEU from Bulgaria, was conducted by truck, barge, and rail modes of transport across two transit countries before reaching the final destination at the Production Association Mayak facility in Chelyabinsk, Russia. This paper describes the work, equipment, organizations, and approvals that were required to complete the spent fuel shipment and provides lessons learned that might assist other research reactor operators with their own spent nuclear fuel shipments.

Kelly Cummins; Igor Bolshinsky; Ken Allen; Tihomir Apostolov; Ivaylo Dimitrov

2009-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "red liquor spent" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Determining Reactor Flux from Xenon-136 and Cesium-135 in Spent Fuel  

E-Print Network [OSTI]

The ability to infer the reactor flux from spent fuel or seized fissile material would enhance the tools of nuclear forensics and nuclear nonproliferation significantly. We show that reactor flux can be inferred from the ratios of xenon-136 to xenon-134 and cesium-135 to cesium-137. If the average flux of a reactor is known, the flux inferred from measurements of spent fuel could help determine whether that spent fuel was loaded as a blanket or close to the mid-plane of the reactor. The cesium ratio also provides information on reactor shutdowns during the irradiation of fuel, which could prove valuable for identifying the reactor in question through comparisons with satellite reactor heat monitoring data. We derive analytic expressions for these correlations and compare them to experimental data and to detailed reactor burn simulations. The enrichment of the original uranium fuel affects the correlations by up to 3 percent, but only at high flux.

A. C. Hayes; Gerard Jungman

2012-05-30T23:59:59.000Z

422

Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term-Disposal Criticality Safety  

SciTech Connect (OSTI)

Utilization of burnup credit in criticality safety analysis for long-term disposal of spent nuclear fuel allows improved design efficiency and reduced cost due to the large mass of fissile material that will be present in the repository. Burnup-credit calculations are based on depletion calculations that provide a conservative estimate of spent fuel contents (in terms of criticality potential), followed by criticality calculations to assess the value of the effective neutron multiplication factor (k(sub)eff) for the a spent fuel cask or a fuel configuration under a variety of probabilistically derived events. In order to ensure that the depletion calculation is conservative, it is necessary to both qualify and quantify assumptions that can be made in depletion models.

DeHart, M.D.

1999-08-01T23:59:59.000Z

423

Threat of Hydride Re-orientation to Spent Fuel Integrity During Transportation Accidents: Myth or Reality?  

SciTech Connect (OSTI)

The source-term study conducted by Sandia National Laboratories nearly two decades ago for the spent fuel inventory known at the time, which was in the low-to-medium burnup range ({approx}35 GWd/MTU), showed that the effects of transportation accidents on spent fuel failures, and consequential radioactivity release to the environment, were relatively benign. However, with today's discharged fuel burnups routinely greater than 45 GWd/MTU, potential hydride reorientation during interim dry storage, and its effects on cladding properties, has become one of the primary concerns for spent fuel transportation. Laboratory tests of un-irradiated cladding specimens subjected to heat treatments promoting hydride dissolution followed by re-precipitation in the radial direction have shown that relatively moderate concentrations ({approx}70 ppm) of radial hydrides can significantly degrade cladding ductility, at least at room temperature. The absence of specific data that are relevant to high-burnup spent fuel under dry storage conditions have led to the conjecture, deduced from those tests, that massive cladding failures, possibly resulting in fuel reconfiguration, can be expected during cask drop events. Such conclusions are not borne out by the findings in this paper. The analysis results indicate that cladding failure is bi-modal: a state of failure initiation at the cladding ID remaining as part-wall damage with less than 2% probability of occurrence, and a through-wall failure at a probability of 1 E-5. These results indicate that spent fuel conditions that could promote the formation of radial hydrides during dry storage are not sufficient to produce radial hydrides concentrations of significant levels to cause major threat to spent fuel integrity. It is important to note in this regard that the through-wall cladding failure probability of 1 E-5 is of the same order of magnitude as calculated in the cited Sandia study for low burnup fuel. (authors)

Rashid, Joe [ANATECH, 5435 Oberlin Drive, San Diego, CA 92121 (United States); Machiels, Albert [EPRI, 3420 Hillview Avenue, Palo Alto, CA 94304 (United States)

2007-07-01T23:59:59.000Z

424

The FIRST-2MASS Red Quasar Survey  

SciTech Connect (OSTI)

Combining radio observations with optical and infrared color selection--demonstrated in our pilot study to be an efficient selection algorithm for finding red quasars--we have obtained optical and infrared spectroscopy for 120 objects in a complete sample of 156 candidates from a sky area of 2716 square degrees. Consistent with our initial results, we find our selection criteria--J-K > 1.7,R-K > 4.0--yield a {approx} 50% success rate for discovering quasars substantially redder than those found in optical surveys. Comparison with UVX- and optical color-selected samples shows that {approx}> 10% of the quasars are missed in a magnitude-limited survey. Simultaneous two-frequency radio observations for part of the sample indicate that a synchrotron continuum component is ruled out as a significant contributor to reddening the quasars spectra. We go on to estimate extinctions for our objects assuming their red colors are caused by dust. Continuum fits and Balmer decrements suggest E(B-V) values ranging from near zero to 2.5 magnitudes. Correcting the K-band magnitudes for these extinctions, we