Sample records for wood spent sulfite

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

    SciTech Connect (OSTI)

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

    1996-12-31T23:59:59.000Z

    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.

  2. Nitrogen Dioxide Absorption and Sulfite Oxidation in Aqueous Sulfite

    E-Print Network [OSTI]

    Rochelle, Gary T.

    Nitrogen Dioxide Absorption and Sulfite Oxidation in Aqueous Sulfite C H E N H . S H E N A N D G by absorption in sulfite solution in existing scrubbers for desulfurization. Rates of NO2 absorption and sulfite absorption initiates sulfite oxidation in the presence of oxygen, and this study quantified the effect

  3. Alternatives for balanced production of fibers, chemicals, and energy from wood

    SciTech Connect (OSTI)

    Sjoestroem, E.

    1983-01-01T23:59:59.000Z

    Increased oil prices and shortage of fossil materials have recently focused interest on the possibilities of conversion of wood to various forms of fuels and chemicals. It is to be expected that new approaches are emerging from the totality of the research effort now in progress. However, irrespective of this, the function of wood as a construction material and a source for fibers presumably remains unchanged or even becomes more important in the future. In regard to the principal pulping methods for production of fibers, no abrupt changes in current practices are probable, apart from important progress in energy saving. In a very favorable situation of the kraft process, when surplus energy generated from the burning of black liquor is availiable, a partial recovery of dissolved organic solids, such as lignin and carbohydrates and their degradation products, becomes more attractive. Quite different is the case of the conventional sulfite process when evaporation and burning of the spent liquor result in severe air pollution. Successful recovery, conversion, and marketing of the dissolved solids can then be the only way to compensate for the expense of using external fuel. Alternatives for production of organic chemicals from kraft and sulfite spent liquors are discussed by taking into consideration the fiber production, composition of dissolved solids, energy requirements, pollution problems, and recovery of inorganic pulping chemicals. 11 references, 10 figures, 5 tables

  4. Value-Added Products From FGD Sulfite-Rich Scrubber Materials

    SciTech Connect (OSTI)

    Vivak M. Malhotra

    2006-09-30T23:59:59.000Z

    Massive quantities of sulfite-rich flue gas desulfurization (FGD) scrubber materials are produced every year in the USA. In fact, at present, the production of wet sulfite-rich scrubber cake outstrips the production of wet sulfate-rich scrubber cake by about 6 million tons per year. However, most of the utilization focus has centered on FGD gypsum. Therefore, we have recently initiated research on developing new strategies for the economical, but environmentally-sound, utilization of sulfite-rich scrubber material. In this exploratory project (Phase I), we attempted to ascertain whether it is feasible to develop reconstituted wood replacement products from sulfite-rich scrubber material. In pursuit of this goal, we characterized two different wet sulfite-rich scrubber materials, obtained from two power plants burning Midwestern coal, for their suitability for the development of value-added products. The overall strategy adopted was to fabricate composites where the largest ingredient was scrubber material with additional crop materials as additives. Our results suggested that it may be feasible to develop composites with flexural strength as high as 40 MPa (5800 psi) without the addition of external polymers. We also attempted to develop load-bearing composites from scrubber material, natural fibers, and phenolic polymer. The polymer-to-solid ratio was limited to {le} 0.4. The formulated composites showed flexural strengths as high as 73 MPa (10,585 psi). We plan to harness the research outcomes from Phase I to develop parameters required to upscale our value-added products in Phase II.

  5. Oxidation kinetics of by-product calcium sulfite 

    E-Print Network [OSTI]

    Othman, Hasliza

    1992-01-01T23:59:59.000Z

    by hydration to dihydrate. Another low energy technique under study is to develop a sulfate resistant cement which does not react with dihydrate to form deleterious expansive compounds. One of the paramount requirements necessary for utilizing... calcium sulfite hemihydrate. Ca + SO2 + 2H20 ? -& CaSO2. 2H20 (s) 2+ 2- 1 Due to the presence of excess air in the system, some sulfite is oxidized to sulfate and precipitates as calcium sulfate dihydrate (gypsum). SO2 + &O2 ? &804 2 1 2- Ca + SO4...

  6. Oxidation kinetics of by-product calcium sulfite

    E-Print Network [OSTI]

    Othman, Hasliza

    1992-01-01T23:59:59.000Z

    of Department) May 1992 ABSTRACT Oxidation Kinetics of By-product Calcium Sulfite. (May 1992) Hasliza Othman, B. S. , Texas A&M University Chair of Advisory Committee: Dr. Ahmed M. Gadalla The by-products obtained from the flue gas desulfurization (FGD..., suggestions and encouragement. TABLE OF CONTENTS CHAPTER Page I INTRODUCTION I I LITERATURE REVIEW A. Limestone Flue Gas Desulfurization Process . . . . . . . . . . . . B. Scaling Problem in the FGD Process...

  7. The effect of cooking preparations on the residual sulfite concentrations in shrimp

    E-Print Network [OSTI]

    Lally, Audrey Ann

    1987-01-01T23:59:59.000Z

    of this study was, therefore, to determine the effect of various types of cook- ing preparations on the residual sulfite in shrimp. The specific obgectives were: 1. To determine the residual sulfite when shrimp were boiled in water shell-on and shell-off. 2.... (1978). This may be due to the difference in brine concentrations and a possible increase of diffusion rate in shrimp versus beans. The Effect of Processing Procedures on Residual Sulfites in ~Shrim The different cooking procedures affected the rate...

  8. Value-Added Products from FGD Sulfite-Rich Scrubber Materials

    SciTech Connect (OSTI)

    Vivak Malhotra

    2010-01-31T23:59:59.000Z

    According to the American Coal Ash Association, about 29.25 million tons of flue gas desulfurization (FGD) byproducts were produced in the USA in 2003. Out of 29.25 million tons, 17.35 million tons were sulfite-rich scrubber materials. At present, unlike its cousin FGD gypsum, the prospect for effective utilization of sulfite-rich scrubber materials is not bright. In fact, almost 16.9 million tons are leftover every year. In our pursuit to mitigate the liability of sulfite-rich FGD scrubber materials' disposal, we are attempting to develop value-added products that can commercially compete. More specifically, for this Innovative Concept Phase I project, we have the following objectives: to characterize the sulfite-rich scrubber material for toxic metals; to optimize the co-blending and processing of scrubber material and natural byproducts; to formulate and develop structural composites from sulfite-rich scrubber material; and to evaluate the composites' mechanical properties and compare them with current products on the market. After successfully demonstrating the viability of our research, a more comprehensive approach will be proposed to take these value-added materials to fruition.

  9. Oxidation and characterization of FGD byproduct calcium sulfite and oxidized product

    E-Print Network [OSTI]

    Gupta, Anurag

    1993-01-01T23:59:59.000Z

    with absorbed sulfur dioxide, sulfite oxidation and CaSOs/CaSO4 crystallization. Calcium ion is formed during dissolution of calcium carbonate in water. z CaCO3 (s) ? -& CaCO3 (aq) (2-1) CaCO3 + H20 ? -& Ca~ + HCO3 + OH (2-2) Sulfur dioxide is absorbed... in the water and forms SO3= ion. SO2 (g) ? -& SO2 (aq) (2-3) SO2 (aq) + H20 ? -& H2SO3 ? -& HSO3- + H+ (2-4) HSO3- ? -& H+ + SO3= (2-5) The sulfite ions react with calcium ions to form calcium sulfite hemihydrate. Ca++ + SO3= + ? HpO ? -& CaSO3. ? HZO (s...

  10. Residential Wood Residential wood combustion (RWC) is

    E-Print Network [OSTI]

    Residential Wood Combustion Residential wood combustion (RWC) is increasing in Europe because PM2.5. Furthermore, other combustion- related sources of OA in Europe may need to be reassessed. Will it affect global OA emission estimates? Combustion of biofuels is globally one of the major OA sources

  11. Oxidation and characterization of FGD byproduct calcium sulfite and oxidized product 

    E-Print Network [OSTI]

    Gupta, Anurag

    1993-01-01T23:59:59.000Z

    and infrared spectroscopy. It was found to consist mainly of a solid solution of calcium sulfate and calcium sulfite hemihydrate, calcium sulfate dihydrate and unreacted calcium carbonate. 1 Pure CaSO3. ? H20 was synthesized as a model and was used... in slurries containing I to 12 % of solids in the temperature range 40 to 70 'C, using sulfuric acid to control the pH and to convert calcium carbonate to calcium sulfate dihydrate. Air and hydrogen peroxide were used as the oxidizing agents. When air...

  12. Redox states of Desulfovibrio vulgaris DsrC, a key protein in dissimilatory sulfite reduction

    SciTech Connect (OSTI)

    Venceslau, Sofia S. [Instituto de Tecnologia Química e Biológica António Xavier, Universidade Nova de Lisboa, Oeiras (Portugal)] [Instituto de Tecnologia Química e Biológica António Xavier, Universidade Nova de Lisboa, Oeiras (Portugal); Cort, John R.; Baker, Erin S. [Fundamental and Computational Sciences Directorate, Pacific Northwest National Laboratory, Richland, WA 99352 (United States)] [Fundamental and Computational Sciences Directorate, Pacific Northwest National Laboratory, Richland, WA 99352 (United States); Chu, Rosalie K.; Robinson, Errol W. [Environmental Molecular Sciences Laboratory, Pacific Northwest National Laboratory, Richland, WA 99352 (United States)] [Environmental Molecular Sciences Laboratory, Pacific Northwest National Laboratory, Richland, WA 99352 (United States); Dahl, Christiane [Institut für Mikrobiologie and Biotechnologie, Rheinische Friedrich-Wilhelms-Universität Bonn, Meckenheimer Allee 168, D-53115 Bonn (Germany)] [Institut für Mikrobiologie and Biotechnologie, Rheinische Friedrich-Wilhelms-Universität Bonn, Meckenheimer Allee 168, D-53115 Bonn (Germany); Saraiva, Lígia M. [Instituto de Tecnologia Química e Biológica António Xavier, Universidade Nova de Lisboa, Oeiras (Portugal)] [Instituto de Tecnologia Química e Biológica António Xavier, Universidade Nova de Lisboa, Oeiras (Portugal); Pereira, Inês A.C., E-mail: ipereira@itqb.unl.pt [Instituto de Tecnologia Química e Biológica António Xavier, Universidade Nova de Lisboa, Oeiras (Portugal)

    2013-11-29T23:59:59.000Z

    Highlights: •DsrC is known to interact with the dissimilatory sulfite reductase enzyme (DsrAB). •We show that, however, most cellular DsrC is not associated with DsrAB. •A gel-shift assay was developed that allows monitoring of the DsrC redox state. •The DsrC intramolecularly oxidized state could only be produced by arginine treatment. -- Abstract: Dissimilatory reduction of sulfite is carried out by the siroheme enzyme DsrAB, with the involvement of the protein DsrC, which has two conserved redox-active cysteines. DsrC was initially believed to be a third subunit of DsrAB. Here, we report a study of the distribution of DsrC in cell extracts to show that, in the model sulfate reducer Desulfovibrio vulgaris, the majority of DsrC is not associated with DsrAB and is thus free to interact with other proteins. In addition, we developed a cysteine-labelling gel-shift assay to monitor the DsrC redox state and behaviour, and procedures to produce the different redox forms. The oxidized state of DsrC with an intramolecular disulfide bond, which is proposed to be a key metabolic intermediate, could be successfully produced for the first time by treatment with arginine.

  13. Wood Resources International

    E-Print Network [OSTI]

    .3% Sweden 5.3% Finland 4.1% Russia 13.8% US 37.3% Germany 3.3% France 2.8% Poland 2.1% Other Europe 14 International Wood Fuel Removals in Europe 2002 Turkey 12.2% Poland 3.6% Romania 5.3% Hungary 4.1% Germany 7;Wood Resources International Production of energy from wood fuels in 2000 Source: EUBIONET 0 50 100 150

  14. Redox states of Desulfovibrio vulgaris DsrC, a key protein in dissimilatory sulfite reduction

    SciTech Connect (OSTI)

    Venceslau, Sofia S.; Cort, John R.; Baker, Erin Shammel; Chu, Rosalie K.; Robinson, Errol W.; Dahl, Christiane; Saraiva, Ligia M.; Pereira, Ines Ac

    2013-11-29T23:59:59.000Z

    Dissimilatory reduction of sulfite is carried out by the siroheme enzyme DsrAB, with the involvement of the protein DsrC having two conserved cysteine residues. Here, we report a study of the distribution of DsrC in cell extracts, a cysteine-labelling gel-shift assay to monitor its redox state and behaviour, and procedures to produce the different redox forms. We show that, in the model sulfate reducer Desulfovibrio vulgaris, the majority of DsrC is not associated with DsrAB and is thus free to interact with other proteins. In addition, we successfully produced DsrC with an intramolecular disulfide bond (oxidized state) by treatment with arginine.

  15. Scintillator spent fuel monitor

    SciTech Connect (OSTI)

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

    1980-01-01T23:59:59.000Z

    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%.

  16. James F. Wood

    Broader source: Energy.gov [DOE]

    James F. Wood is currently Deputy Assistant Secretary for Clean Coal in the Office of Fossil Energy (FE). In this position, he is responsible for the management and direction of the Office's...

  17. Release of U(VI) from spent biosorbent immobilized in cement concrete blocks

    SciTech Connect (OSTI)

    Venkobachar, C.; Iyengar, L.; Mishra, U.K.; Chauhan, M.S. [Indian Inst. of Tech., Kanpur (India)] [Indian Inst. of Tech., Kanpur (India)

    1995-12-01T23:59:59.000Z

    This paper deals with cementation as the method for the disposal of spent biosorbent, Ganoderma lucidum (a wood rotting macrofungi) after it is used for the removal of Uranium. Results on the uranium release during the curing of cement-concrete (CC) blocks indicated that placing the spent sorbent at the center of the blocks during their casting yields better immobilization of uranium as compared to the homogeneous mixing of the spent sorbent with the cement. Short term leach tests indicated that the uranium release was negligible in simulated seawater, 1.8% in 0.2 N sodium carbonate and 6.0% in 0.2 N HCl. The latter two leachates were used to represent the extreme environmental conditions. It was observed that the presence of the spent biosorbent up to 5% by weight did not affect the compressive strength of CC blocks. Thus cementation technique is suitable for the immobilization of uranium loaded biosorbent for its ultimate disposal.

  18. Precision wood particle feedstocks

    DOE Patents [OSTI]

    Dooley, James H; Lanning, David N

    2013-07-30T23:59:59.000Z

    Wood particles having fibers aligned in a grain, wherein: the wood particles are characterized by a length dimension (L) aligned substantially parallel to the grain, a width dimension (W) normal to L and aligned cross grain, and a height dimension (H) normal to W and L; the L.times.H dimensions define two side surfaces characterized by substantially intact longitudinally arrayed fibers; the W.times.H dimensions define two cross-grain end surfaces characterized individually as aligned either normal to the grain or oblique to the grain; the L.times.W dimensions define two substantially parallel top and bottom surfaces; and, a majority of the W.times.H surfaces in the mixture of wood particles have end checking.

  19. Intermodal transportation of spent fuel

    SciTech Connect (OSTI)

    Elder, H.K.

    1983-09-01T23:59:59.000Z

    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.

  20. HFIR spent fuel management alternatives

    SciTech Connect (OSTI)

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

    1992-10-15T23:59:59.000Z

    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.

  1. HFIR spent fuel management alternatives

    SciTech Connect (OSTI)

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

    1992-10-15T23:59:59.000Z

    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.

  2. Spent Nuclear Fuel project, project management plan

    SciTech Connect (OSTI)

    Fuquay, B.J.

    1995-10-25T23:59:59.000Z

    The Hanford Spent Nuclear Fuel Project has been established to safely store spent nuclear fuel at the Hanford Site. This Project Management Plan sets forth the management basis for the Spent Nuclear Fuel Project. The plan applies to all fabrication and construction projects, operation of the Spent Nuclear Fuel Project facilities, and necessary engineering and management functions within the scope of the project

  3. WOOD PRODUCTS AND UTILIZATION

    E-Print Network [OSTI]

    Standiford, Richard B.

    not require extensive cultivation and extraction methods, and it uses less manmade energy to manufacture, these trees are a vital component of wildlife and plant ecosystems, water quality, recreation, and esthetic and firewood harvesting are two activities that consume large quantities of wood from oak woodlands. Finding

  4. Rheological Model for Wood

    E-Print Network [OSTI]

    Mohammad Masoud Hassani; Falk K. Wittel; Stefan Hering; Hans J. Herrmann

    2014-10-15T23:59:59.000Z

    Wood as the most important natural and renewable building material plays an important role in the construction sector. Nevertheless, its hygroscopic character basically affects all related mechanical properties leading to degradation of material stiffness and strength over the service life. Accordingly, to attain reliable design of the timber structures, the influence of moisture evolution and the role of time- and moisture-dependent behaviors have to be taken into account. For this purpose, in the current study a 3D orthotropic elasto-plastic, visco-elastic, mechano-sorptive constitutive model for wood, with all material constants being defined as a function of moisture content, is presented. The corresponding numerical integration approach, with additive decomposition of the total strain is developed and implemented within the framework of the finite element method (FEM). Moreover to preserve a quadratic rate of asymptotic convergence the consistent tangent operator for the whole model is derived. Functionality and capability of the presented material model are evaluated by performing several numerical verification simulations of wood components under different combinations of mechanical loading and moisture variation. Additionally, the flexibility and universality of the introduced model to predict the mechanical behavior of different species are demonstrated by the analysis of a hybrid wood element. Furthermore, the proposed numerical approach is validated by comparisons of computational evaluations with experimental results.

  5. Spent-fuel-storage alternatives

    SciTech Connect (OSTI)

    Not Available

    1980-01-01T23:59:59.000Z

    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)

  6. Spent graphite fuel element processing

    SciTech Connect (OSTI)

    Holder, N.D.; Olsen, C.W.

    1981-07-01T23:59:59.000Z

    The Department of Energy currently sponsors two programs to demonstrate the processing of spent graphite fuel elements. General Atomic in San Diego operates a cold pilot plant to demonstrate the processing of both US and German high-temperature reactor fuel. Exxon Nuclear Idaho Company is demonstrating the processing of spent graphite fuel elements from Rover reactors operated for the Nuclear Rocket Propulsion Program. This work is done at Idaho National Engineering Laboratory, where a hot facility is being constructed to complete processing of the Rover fuel. This paper focuses on the graphite combustion process common to both programs.

  7. Characteristics of spent nuclear fuel

    SciTech Connect (OSTI)

    Notz, K.J.

    1988-04-01T23:59:59.000Z

    The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the spent fuels and other wastes that will, or may, eventually be disposed of in a geological repository. The two major sources of these materials are commercial light-water reactor (LWR) spent fuel and immobilized high-level waste (HLW). Other wastes that may require long-term isolation include non-LWR spent fuels and miscellaneous sources such as activated metals. This report deals with spent fuels, but for completeness, the other sources are described briefly. Detailed characterizations are required for all of these potential repository wastes. These characteristics include physical, chemical, and radiological properties. The latter must take into account decay as a function of time. In addition, the present inventories and projected quantities of the various wastes are needed. This information has been assembled in a Characteristics Data Base which provides data in four formats: hard copy standard reports, menu-driven personal computer (PC) data bases, program-level PC data bases, and mainframe computer files. 5 refs., 3 figs., 4 tabs.

  8. 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...

  9. FAO Forestry Department Wood Energy WISDOM Slovenia

    E-Print Network [OSTI]

    in developing pellet production and district heating systems; the formulation of a national wood energy strategyFAO ­ Forestry Department ­ Wood Energy WISDOM ­ Slovenia Spatial woodfuel production Rudi Drigo Forestry Specialist - Wood energy planning and forest resources monitoring Zivan Veseli

  10. DIVISION 6 -WOOD AND PLASTICS 06000 GENERAL

    E-Print Network [OSTI]

    DIVISION 6 - WOOD AND PLASTICS ________________________________________________________________________ 06000 GENERAL 1. For both woods and plastics, special attention is called to matters of flame spread-dried. 3. For exterior wood or plastic framed structures, see Division 4 for dimensions of Sample Panel

  11. Solution Structure of Pyrobaculum aerophilum DsrC, an Archaeal Homologue of the Gamma Subunit of Dissimilatory Sulfite Reductase

    SciTech Connect (OSTI)

    Cort, John R.; Mariappan, S.V. S.; Kim, Chang Y.; Park, Min S.; Peat, Thomas S.; Waldo, Geoffrey S.; Terwilliger, Thomas C.; Kennedy, Michael A.

    2001-11-29T23:59:59.000Z

    The solution structure of DsrC, an archaeal homologue of the g subunit of dissimilatory sulfite reductase has been determined by NMR spectroscopy. This 12.7 kDa protein from the hyperthermophilic archaeon Pyrobaculum aerophilum adopts a novel fold consisting of an orthogonal helical bundle with a b-hairpin along one side. A portion of the structure resembles the helix-turn-helix DNA-binding motif common in transcriptional regulator proteins. The protein contains two disulfide bonds but remains folded in the presence of DTT. DsrC proteins from organisms other than Pyrobaculum species do not contain these disulfide bonds. A conserved cysteine next to the C-terminus, which is not involved in the disulfide bonds, is not part of the globular structure of the protein and is located on an unstructured 7-residue C-terminal arm that extends away from the center of the protein.

  12. Beverly Woods | Y-12 National Security Complex

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

    Beverly Woods Beverly Woods Oral History Videos Speakers INTRODUCTION Ed Bailey Jim Bailey Kay Bailey Ken Bernander Willard Brock Wilma Brooks Elmer Brummitt Naomi Brummitt Blake...

  13. Environmental Impacts of Treated Wood

    E-Print Network [OSTI]

    Florida, University of

    Environmental Impacts of Treated Wood 6495_C000.fm Page iii Wednesday, February 1, 2006 5:48 PM #12 through the Florida Center for Environmental Solutions, National Science Foundation Grant No. 0126172. Any of treated-wood research and their efforts in organizing the con- ference entitled Environmental Impacts

  14. The Asian Wood Pellet Markets

    E-Print Network [OSTI]

    The Asian Wood Pellet Markets Joseph A. Roos and Allen M. Brackley United States Department Wood Pellet plant in North Pole, Alaska. Clockwise from upper left: pelleting machine; pellets bagged for home use; a Superior Pellet Fuels bag; inventory of product ready for shipment to retailers. Upper

  15. GLOBAL WOOD SUPPLY Sten Nilsson

    E-Print Network [OSTI]

    GLOBAL WOOD SUPPLY Sten Nilsson Biomass and Resource Efficiency: the need for a supply led approach the wood come from? Western EU Deficit Eastern EU Deficit Rest of Eastern Europe Balanced Russia Rest of Eastern Europe Balanced Russia Is probably at production ceiling under current conditions Japan

  16. Actinide removal from spent salts

    DOE Patents [OSTI]

    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

    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.

  17. Metals removal from spent salts

    DOE Patents [OSTI]

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

    2002-01-01T23:59:59.000Z

    A method and apparatus for removing metal contaminants 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 may be added to precipitate the metal oxide and/or the metal as either metal oxide, metal hydroxide, or as a salt. The precipitated materials are filtered, dried and packaged for disposal as waste or can be immobilized as ceramic pellets. More than about 90% of the metals and mineral residues (ashes) present are removed by filtration. After filtration, salt solutions having a carbonate concentration >20% can be spray-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 1.0 ppm of contaminants.

  18. Spent fuel integrity during transportation

    SciTech Connect (OSTI)

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

    1980-01-01T23:59:59.000Z

    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.

  19. Probability of spent fuel transportation accidents

    SciTech Connect (OSTI)

    McClure, J. D.

    1981-07-01T23:59:59.000Z

    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.

  20. Successful biomass (wood pellets ) implementation in

    E-Print Network [OSTI]

    Successful biomass (wood pellets ) implementation in Estonia Biomass Utilisation of Local of primary energy in Estonia ! Wood fuels production ! Pellet firing projects in Estonia ­ SIDA Demo East Production of wood fuels in Estonia in 2002 Regional Energy Centres in Estonia Wood pellets production

  1. Wood Fuel Task Force Response 2 | Wood Fuel Task Force Response

    E-Print Network [OSTI]

    Wood Fuel Task Force Response #12;2 | Wood Fuel Task Force Response #12;Wood Fuel Task Force Response | 3 Wood Fuel Task Force Response Scottish Government response by Minister for Environment, Michael Russell I am pleased to present on behalf of the Scottish Government our response to the Wood Fuel

  2. Spent nuclear fuel sampling strategy

    SciTech Connect (OSTI)

    Bergmann, D.W.

    1995-02-08T23:59:59.000Z

    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.

  3. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently AskedEnergyIssues DOE's Nuclear EnergySmartOverviewEnergy Spelman GraduateSpent

  4. Textile Drying Via Wood Gasification 

    E-Print Network [OSTI]

    McGowan, T. F.; Jape, A. D.

    1983-01-01T23:59:59.000Z

    This project was carried out to investigate the possibility of using wood gas as a direct replacement for natural gas in textile drying. The Georgia Tech updraft gasifier was used for the experimental program. During preliminary tests, the 1 million...

  5. Textile Drying Via Wood Gasification

    E-Print Network [OSTI]

    McGowan, T. F.; Jape, A. D.

    1983-01-01T23:59:59.000Z

    This project was carried out to investigate the possibility of using wood gas as a direct replacement for natural gas in textile drying. The Georgia Tech updraft gasifier was used for the experimental program. During preliminary tests, the 1 million...

  6. Integrated Industrial Wood Chip Utilization

    E-Print Network [OSTI]

    Owens, E. T.

    1984-01-01T23:59:59.000Z

    The sources of supply of wood residues for energy generation are described and the rationale for exploring the potential available from forest harvesting is developed. Details of three industrial-scale projects are presented and the specific...

  7. HYDRAULIC CEMENT PREPARATION FROM LURGI SPENT SHALE

    E-Print Network [OSTI]

    Mehta, P.K.

    2013-01-01T23:59:59.000Z

    Investigations on hydraulic cement from spent oil shale,"April 16-18, 1980 HYDRAULIC CEMENT PREPARATION FROM LURGIpressi ve b strength, MPa this cement in moist environments.

  8. Spent Nuclear Fuel (SNF) Project Execution Plan

    SciTech Connect (OSTI)

    LEROY, P.G.

    2000-11-03T23:59:59.000Z

    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.

  9. CHEMISTRY AND STOICHIOMETRY OF WOOD LIQUEFACTION

    E-Print Network [OSTI]

    Davis, H.G.

    2012-01-01T23:59:59.000Z

    analysis of the wood-oil product derived from the above2 g It is probable that oil products with oxygen contentscollected with the wood-oil product. The condensate contains

  10. Marin County- Wood Stove Replacement Rebate Program

    Broader source: Energy.gov [DOE]

    The County of Marin has created a rebate program to encourage homeowners to remove or replace non-EPA certified wood-burning heaters (wood stoves and fireplace inserts) with cleaner burning stoves...

  11. Leonard Wood and the American Empire 

    E-Print Network [OSTI]

    Pruitt, James Herman

    2012-07-16T23:59:59.000Z

    During the ten years following the Spanish American War (1898 to 1908), Major General Leonard Wood served as the primary agent of American imperialism. Wood was not only a proconsul of the new American Empire; he was a ...

  12. Structure-Infesting Wood-Boring Beetles

    E-Print Network [OSTI]

    Jackman, John A.

    2006-03-28T23:59:59.000Z

    Several kinds of beetles damage stored wood, structural timbers and other wood products. This publication explains how to detect, identify, prevent and control powderpost beetle, old house borer and others....

  13. Decreasing the leachibility of boron wood preservatives

    E-Print Network [OSTI]

    Gezer, Engin Derya

    1996-01-01T23:59:59.000Z

    The use of boron in wood preservatives has been growing since the 1930s, primarily in various boric acid/borax mixtures. Boron preservatives have several advantages for application as wood preservatives including a broad spectrum of activity...

  14. EIS-0203: Spent Nuclear Fuel Management and Idaho National Engineering...

    Energy Savers [EERE]

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

  15. Determination of Plutonium Content in Spent Fuel with Nondestructive Assay

    E-Print Network [OSTI]

    Tobin, S. J.

    2010-01-01T23:59:59.000Z

    Spent Nuclear Fuel Recycling Facility – 8032,” Waste ManagementSpent Nuclear Fuel by Self-Induced X-ray,” Annual Meeting of the Institute of Nuclear Material Management,

  16. 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...

  17. 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...

  18. Emerging Technologies in Wood Energy Wood can already be used to produce heat and

    E-Print Network [OSTI]

    established technologies of District Energy and Combined Heat and Power plants. Using wood to makeEmerging Technologies in Wood Energy Wood can already be used to produce heat and electricity using such as flooring and siding. In Europe, torrefaction has been explored to produce an improved wood pellet

  19. Creating Value Wood Products Industry

    E-Print Network [OSTI]

    Louisiana Forest Products Development Center #12;2 Louisiana is blessed with quality timberland for the Wood Products Industry The forest industry contributes more than 50 percent of the total value of all for quality information, research and education in forest products in Louisiana, recognized regionally

  20. Optical computing Damien Woods a

    E-Print Network [OSTI]

    Woods, Damien

    Optical computing Damien Woods a aDepartment of Computer Science and Artificial Intelligence Institute, Vierimaantie 5, 84100 Ylivieska, Finland Abstract In this survey we consider optical computers of such optical computing archi- tectures, including descriptions of the type of hardware commonly used in optical

  1. Optical computing Damien Woods a

    E-Print Network [OSTI]

    Woods, Damien

    Optical computing Damien Woods a aDepartment of Computer Science and Artificial Intelligence Institute, Vierimaantie 5, 84100 Ylivieska, Finland Abstract We consider optical computers that encode data using images and compute by transforming such images. We give an overview of a number of such optical

  2. Fluoride removal from water with spent catalyst

    SciTech Connect (OSTI)

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

    1996-12-01T23:59:59.000Z

    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.

  3. Spent fuel storage requirements 1993--2040

    SciTech Connect (OSTI)

    Not Available

    1994-09-01T23:59:59.000Z

    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.

  4. HYDRAULIC CEMENT PREPARATION FROM LURGI SPENT SHALE

    E-Print Network [OSTI]

    Mehta, P.K.

    2013-01-01T23:59:59.000Z

    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

  5. HYDRAULIC CEMENT PREPARATION FROM LURGI SPENT SHALE

    E-Print Network [OSTI]

    Mehta, P.K.

    2013-01-01T23:59:59.000Z

    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

  6. Potential adverse health effects of wood smoke

    SciTech Connect (OSTI)

    Pierson, W.E.; Koenig, J.Q.; Bardana, E.J. Jr.

    1989-09-01T23:59:59.000Z

    The use of wood stoves has increased greatly in the past decade, causing concern in many communities about the health effects of wood smoke. Wood smoke is known to contain such compounds as carbon monoxide, nitrogen oxides, sulfur oxides, aldehydes, polycyclic aromatic hydrocarbons, and fine respirable particulate matter. All of these have been shown to cause deleterious physiologic responses in laboratory studies in humans. Some compounds found in wood smoke--benzo(a)pyrene and formaldehyde--are possible human carcinogens. Fine particulate matter has been associated with decreased pulmonary function in children and with increased chronic lung disease in Nepal, where exposure to very high amounts of wood smoke occurs in residences. Wood smoke fumes, taken from both outdoor and indoor samples, have shown mutagenic activity in short-term bioassay tests. Because of the potential health effects of wood smoke, exposure to this source of air pollution should be minimal.29 references.

  7. Pyrochemical processing of DOE spent nuclear fuel

    SciTech Connect (OSTI)

    Laidler, J.J.

    1995-02-01T23:59:59.000Z

    A compact, efficient method for conditioning spent nuclear fuel is under development. This method, known as pyrochemical processing, or {open_quotes}pyroprocessing,{close_quotes} provides a separation of fission products from the actinide elements present in spent fuel and further separates pure uranium from the transuranic elements. The process can facilitate the timely and environmentally-sound treatment of the highly diverse collection of spent fuel currently in the inventory of the United States Department of Energy (DOE). The pyroprocess utilizes elevated-temperature processes to prepare spent fuel for fission product separation; that separation is accomplished by a molten salt electrorefining step that provides efficient (>99.9%) separation of transuranics. The resultant waste forms from the pyroprocess, are stable under envisioned repository environment conditions and highly leach-resistant. Treatment of any spent fuel type produces a set of common high-level waste forms, one a mineral and the other a metal alloy, that can be readily qualified for repository disposal and avoid the substantial costs that would be associated with the qualification of the numerous spent fuel types included in the DOE inventory.

  8. Spent nuclear fuel reprocessing modeling

    SciTech Connect (OSTI)

    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

    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)

  9. Spent fuel integrity during dry storage

    SciTech Connect (OSTI)

    McKinnon, M.A.

    1995-07-01T23:59:59.000Z

    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.

  10. The conservation of waterlogged wood using sucrose

    E-Print Network [OSTI]

    Parrent, James Michael

    1983-01-01T23:59:59.000Z

    such as resins or creosote, which are 13 volatilized by heating, the standard methods for moisture determination yield false values (Panshin a de Zeeuw 1980:203). This should not be a problem when working with waterlogged wood since only small samples... water. Formation of hydrogen bonds releases energy which can be measured as the "heat of wetting" for dry wood. In turn, energy must be supplied to wet wood to remove any water that is present. 14 "The forces of attraction between dry wood and water...

  11. One on One- Douglas K Woods

    Broader source: Energy.gov [DOE]

    A September 2014 interview with Douglas K Woods, the President of the Association for Manufacturing Technology, on the state of US manufacturing.

  12. WoodPolymer Composites Prepared by the In Situ Polymerization of Monomers Within Wood

    E-Print Network [OSTI]

    Wood­Polymer Composites Prepared by the In Situ Polymerization of Monomers Within Wood Yong-Feng Li in Wiley Online Library (wileyonlinelibrary.com). ABSTRACT: Wood­polymer composites (WPCs) were prepared words: composites; mechanical properties; modifi- cation; monomers; renewable resources INTRODUCTION

  13. Seneca Creek Associates, LLC Wood Resources International, LLC "Illegal" Logging and Global Wood Markets

    E-Print Network [OSTI]

    Seneca Creek Associates, LLC Wood Resources International, LLC "Illegal" Logging and Global Wood@aol.com; hekstrom@wri-ltd.com October, 2004 #12;Page ES - 1 Illegal Logging and Global Wood Markets: The Competitive, LLC Executive Summary Illegal logging has been high on the agenda, if not directly at the center

  14. Seneca Creek Associates, LLC Wood Resources International, LLC "Illegal" Logging and Global Wood Markets

    E-Print Network [OSTI]

    Seneca Creek Associates, LLC Wood Resources International, LLC SUMMARY "Illegal" Logging and Global Resources International, LLC Illegal Logging and Global Wood Markets: The Competitive Impacts on the U.S. Wood Products Industry1 Summary Study Objectives Illegal logging and illegal forest activities, in one

  15. Spent Fuel Background Report Volume I

    SciTech Connect (OSTI)

    Abbott, D.

    1994-03-01T23:59:59.000Z

    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.

  16. Apparatus for shearing spent nuclear fuel assemblies

    DOE Patents [OSTI]

    Weil, Bradley S. (Knoxville, TN); Metz, III, Curtis F. (Knoxville, TN)

    1980-01-01T23:59:59.000Z

    A method and apparatus are described for shearing spent nuclear fuel assemblies of the type comprising an array of fuel pins disposed within an outer metal shell or shroud. A spent fuel assembly is first compacted in a known manner and then incrementally sheared using fixed and movable shear blades having matched laterally projecting teeth which slidably intermesh to provide the desired shearing action. Incremental advancement of the fuel assembly after each shear cycle is limited to a distance corresponding to the lateral projection of the teeth to ensure fuel assembly breakup into small uniform segments which are amenable to remote chemical processing.

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

    E-Print Network [OSTI]

    Amy, Gary L.

    2013-01-01T23:59:59.000Z

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

  18. Daniel Wood | Department of Energy

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625govInstrumentstdmadapInactiveVisitingContract Management Fermi SitePARTOfficeOctoberDaniel Wood About Us Daniel

  19. Spent Nuclear Fuel (SNF) Project Product Specification

    SciTech Connect (OSTI)

    PAJUNEN, A.L.

    2000-01-20T23:59:59.000Z

    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.

  20. Comparison of spent nuclear fuel management alternatives

    SciTech Connect (OSTI)

    Beebe, C.L.; Caldwell, M.A,

    1996-09-01T23:59:59.000Z

    This paper reports the process an results of a trade study of spent nuclear fuel (SNF)management alternatives. The purpose of the trade study was to provide: (1) a summary of various SNF management alternatives, (2) an objective comparison of the various alternatives to facilitate the decision making process, and (3) documentation of trade study rational and the basis for decisions.

  1. automatic wood furnaces: Topics by E-print Network

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

    pressure differences that included standard rating points 11 Wood Products 201213 Student Handbook Environmental Sciences and Ecology Websites Summary: Wood Products 201213 Student...

  2. INVESTIGATIONS ON HYDRAULIC CEMENTS FROM SPENT OIL SHALE

    E-Print Network [OSTI]

    Mehta, P.K.

    2012-01-01T23:59:59.000Z

    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

  3. Autonomy for Aurora's Mars Missions Mark Woods,

    E-Print Network [OSTI]

    Fisher, Michael

    Autonomy for Aurora's Mars Missions Mark Woods, SciSys Ltd., Clothier Road, Bristol, UK BS4 5SS Email: mark.woods@scisys.co.uk Tel: +44 117 9717251 ESA's Aurora programme incorporates a strategy for European involvement in future robotic and human exploration of our Solar System. The Aurora roadmap calls

  4. Wood Burning Combined Cycle Power Plant 

    E-Print Network [OSTI]

    Culley, J. W.; Bourgeois, H. S.

    1984-01-01T23:59:59.000Z

    A combined cycle power plant utilizing wood waste products as a fuel has been designed. This plant will yield a 50% efficiency improvement compared to conventional wood-fueled steam power plants. The power plant features an externally-fired gas...

  5. Leonard Wood and the American Empire

    E-Print Network [OSTI]

    Pruitt, James Herman

    2012-07-16T23:59:59.000Z

    During the ten years following the Spanish American War (1898 to 1908), Major General Leonard Wood served as the primary agent of American imperialism. Wood was not only a proconsul of the new American Empire; he was a symbol of the empire...

  6. Assessment of Nuclear Resonance Fluorescence for Spent Nuclear Fuel Assay

    E-Print Network [OSTI]

    Quiter, Brian

    2012-01-01T23:59:59.000Z

    Spent Fuel Assay Using Nuclear Resonance Fluo- rescence,” Annual Meeting of the Institute of Nuclear Material Management,

  7. EIS-0203F; DOE Programmatic Spent Nuclear Fuel Management and...

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

    Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Final...

  8. Determination of Plutonium Content in Spent Fuel with Nondestructive Assay

    E-Print Network [OSTI]

    Tobin, S. J.

    2010-01-01T23:59:59.000Z

    for safeguards of LEU and MOX spent fuel,” Internationalsystems in use today (Safeguards Mox Python Detector, 1 Fork

  9. Alaska Wood Biomass Energy Project Final Report

    SciTech Connect (OSTI)

    Jonathan Bolling

    2009-03-02T23:59:59.000Z

    The purpose of the Craig Wood Fired Boiler Project is to use waste wood from local sawmilling operations to provide heat to local public buildings, in an effort to reduce the cost of operating those buildings, and put to productive use a byproduct from the wood milling process that otherwise presents an expense to local mills. The scope of the project included the acquisition of a wood boiler and the delivery systems to feed wood fuel to it, the construction of a building to house the boiler and delivery systems, and connection of the boiler facility to three buildings that will benefit from heat generated by the boiler: the Craig Aquatic Center, the Craig Elementary School, and the Craig Middle School buildings.

  10. 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.

  11. Spent nuclear fuel project integrated schedule plan

    SciTech Connect (OSTI)

    Squires, K.G.

    1995-03-06T23:59:59.000Z

    The Spent Nuclear Fuel Integrated Schedule Plan establishes the organizational responsibilities, rules for developing, maintain and status of the SNF integrated schedule, and an implementation plan for the integrated schedule. The mission of the SNFP on the Hanford site is to provide safe, economic, environmentally sound management of Hanford SNF in a manner which stages it to final disposition. This particularly involves K Basin fuel.

  12. Disposal of CCA-treated Wood: An Evaluation of

    E-Print Network [OSTI]

    Florida, University of

    Disposal of CCA-treated Wood: An Evaluation of Existing and Alternative Management Options (FINAL CHARACTERISTICS OF CCA-TREATED WOOD ASH II.1 Sample Preparation 10 II.2 Laboratory Methods 15 II.3 Laboratory Results 24 CHAPTER III, SORTING TECHNOLOGIES FOR SEPARATING TREATED WOOD FROM UNTREATED WOOD III.1

  13. Spent Fuel Working Group Report. Volume 1

    SciTech Connect (OSTI)

    O`Toole, T.

    1993-11-01T23:59:59.000Z

    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.

  14. Spent Nuclear Fuel Alternative Technology Risk Assessment

    SciTech Connect (OSTI)

    Perella, V.F.

    1999-11-29T23:59:59.000Z

    A Research Reactor Spent Nuclear Fuel Task Team (RRTT) was chartered by the Department of Energy (DOE) Office of Spent Fuel Management with the responsibility to recommend a course of action leading to a final technology selection for the interim management and ultimate disposition of the foreign and domestic aluminum-based research reactor spent nuclear fuel (SNF) under DOE''s jurisdiction. The RRTT evaluated eleven potential SNF management technologies and recommended that two technologies, direct co-disposal and an isotopic dilution alternative, either press and dilute or melt and dilute, be developed in parallel. Based upon that recommendation, the Westinghouse Savannah River Company (WSRC) organized the SNF Alternative Technology Program to further develop the direct co-disposal and melt and dilute technologies and provide a WSRC recommendation to DOE for a preferred SNF alternative management technology. A technology risk assessment was conducted as a first step in this recommendation process to determine if either, or both, of the technologies posed significant risks that would make them unsuitable for further development. This report provides the results of that technology risk assessment.

  15. North American wood markets hit by United States housing crash North American wood markets hit by United States housing crash

    E-Print Network [OSTI]

    themes were: 1. softwood market developments, and 2. wood energy and wood mobilization. The main use of wood for energy throughout the UNECE region, driven by policy measures and high oil prices development, which will have to try to balance the needs of the established wood products sector and the bio-energy

  16. From the Woods to the Refinery

    Broader source: Energy.gov [DOE]

    Breakout Session 2D—Building Market Confidence and Understanding II: Carbon Accounting and Woody Biofuels From the Woods to the Refinery Stephen S. Kelley, Principal and Department Head, Department of Forest Biomaterials, North Carolina State University

  17. Residential Wood Heating Fuel Exemption (New York)

    Broader source: Energy.gov [DOE]

    New York exempts retail sales of wood used for residential heating purposes from the state sales tax. The law also permits local governments (municipalities and counties) to grant an exemption from...

  18. Effect of sulfite ions in N{sub 2} and CO{sub 2} purged 0.5 m NaCl solution on stainless steels examined by different electrochemical techniques and by reflectance measurements

    SciTech Connect (OSTI)

    Hemmingsen, T.; Aagotnes, N.O.; Kroeger-Silseth, T.; Kolak, N.; Kaik, M. [Stavanger Coll. (Norway)

    1999-11-01T23:59:59.000Z

    Three steels, 13% Cr-steel, SS 304 steel and duplex steel are examined for corrosion for 48-hours periods in N{sub 2} or CO{sub 2} purged 0.5 M sodium chloride electrolytes with different sulfite concentrations. The results show that 13%Cr-steel is most susceptible to pitting in the presence of sulfite both under N{sub 2} and CO{sub 2} atmospheres. SS 304 steel was more resistant to corrosion than 13%Cr-steel. Duplex steel showed rather good corrosion resistance under these conditions. The corrosion rate, inclusive pitting corrosion, after 24 hours in presence of 0--10 mM sulfite based on LPR-measurements is for duplex steel 0.5--0.9 mm/year under N{sub 2} and 0.1--1.8 mm/year under CO{sub 2}, for SS 304 steel 1.0--1.8 mm/year under N{sub 2} and 0.6--1.4 mm/year under CO{sub 2}, and for 13%Cr-steel 1.3--2.2 mm/year under N{sub 2} and 0.7--1.8 mm/year under CO{sub 2}. The use of AC-impedance measurements is discussed. The method should be used with care when other mechanisms than general corrosion are involved.

  19. Wood Fired Steam Plants in Georgia

    E-Print Network [OSTI]

    Bulpitt, W. S.

    1983-01-01T23:59:59.000Z

    suppliers. Based upon the designs submitted and subsequent negotiations, the Applied Engineering Company (APCO) in Orangeburg, South Carolina, was chosen to do the job. Applied Engineering has been working on wood gasification systems for several years...-20, 1983 company has a large manufacturing plant in Orange burg and is fully capable of fabricating large pressure vessels and heavy industrial equipment. The overall wood gasification system is shown in Figure 1. The fuel for the gasifier is green...

  20. A Wood-Fired Gas Turbine Plant

    E-Print Network [OSTI]

    Powell, S. H.; Hamrick, J. T.

    A WOOD-FIRED GAS TURBINE PLANT Sam H. Powell, Tennessee Valley Authority, Chattanooga, Tennessee Joseph T. Hamrick, Aerospace Research Corporation, RBS Electric, Roanoke, VA Abstract This paper covers the research and development of a wood...-fired gas turbine unit that is used for generating electricity. The system uses one large cyclonic combustor and a cyclone cleaning system in series to provide hot gases to drive an Allison T-56 aircraft engine (the industrial version is the 50l-k). A...

  1. Surrogate Spent Nuclear Fuel Vibration Integrity Investigation

    SciTech Connect (OSTI)

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

    2014-01-01T23:59:59.000Z

    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.

  2. Pyrochemical Treatment of Spent Nuclear Fuel

    SciTech Connect (OSTI)

    K. M. Goff; K. L. Howden; G. M. Teske; T. A. Johnson

    2005-10-01T23:59:59.000Z

    Over the last 10 years, pyrochemical treatment of spent nuclear fuel has progressed from demonstration activities to engineering-scale production operations. As part of the Advanced Fuel Cycle Initiative within the U.S. Department of Energy’s Office of Nuclear Energy, Science and Technology, pyrochemical treatment operations are being performed as part of the treatment of fuel from the Experimental Breeder Reactor II at the Idaho National Laboratory. Integral to these treatment operations are research and development activities that are focused on scaling further the technology, developing and implementing process improvements, qualifying the resulting high-level waste forms, and demonstrating the overall pyrochemical fuel cycle.

  3. TEPP - Spent Nuclear Fuel | 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2Uranium Transferon the PassingRouting TEC Working GroupEnergy- Spent

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

    SciTech Connect (OSTI)

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

    1982-01-01T23:59:59.000Z

    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.

  5. Investigation of the condition of spent-fuel pool components

    SciTech Connect (OSTI)

    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

    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.

  6. European Panel FederationEuropean Panel Federation viewpoint on wood energy policiesviewpoint on wood energy policies

    E-Print Network [OSTI]

    --called "green energy"called "green energy" ·· Simultaneously, the taxes on the use of fossil fuelsSimultaneously, the taxes on the use of fossil fuels increaseincrease ·· This leads to increasing costs for wood productsIncreasing use of wood for energy production ·· Governments in Europe are granting subsidies for

  7. Closed Loop Recycling of PreservativeClosed Loop Recycling of Preservative Treated WoodTreated Wood

    E-Print Network [OSTI]

    Closed Loop Recycling of PreservativeClosed Loop Recycling of Preservative Treated WoodTreated Wood.2 million cubic meters) of lumber treated with CCA are produced annually in the United States (Micklewright 1998). ·In 1997, for example, some 581.4 million cu. ft. was treated with waterborne preservatives

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

    National Nuclear Security Administration (NNSA)

    Reagan Calls for a National Spent Fuel Storage Facility | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile...

  9. Huizenga leads safety of spent fuel management, radioactive waste...

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

    Huizenga leads safety of spent fuel management, radioactive waste management meeting in Vienna | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People...

  10. Transportation capabilities study of DOE-owned spent nuclear fuel

    SciTech Connect (OSTI)

    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

    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.

  11. Nondestructive Spent Fuel Assay Using Nuclear Resonance Fluorescence

    E-Print Network [OSTI]

    Quiter, Brian

    2010-01-01T23:59:59.000Z

    Spent Fuel Library for Assessing Varied Nondestructive Assay Techniques for Nuclear Safeguards," LA-UR 09-01188, ANS Advances in Nuclear Fuel Management

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

    SciTech Connect (OSTI)

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

    2012-07-01T23:59:59.000Z

    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)

  13. Regeneration of field-spent activated carbon catalysts for low...

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

    The spent carbon catalysts were regenerated by washing with a surfactant followed by drying and calcination. The physicochemical properties before and after the regeneration were...

  14. Spent Nuclear Fuel project integrated safety management plan

    SciTech Connect (OSTI)

    Daschke, K.D.

    1996-09-17T23:59:59.000Z

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

  15. Pyroprocess for processing spent nuclear fuel

    DOE Patents [OSTI]

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

    2002-01-01T23:59:59.000Z

    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.

  16. Systems impacts of spent fuel disassembly alternatives

    SciTech Connect (OSTI)

    Not Available

    1984-07-01T23:59:59.000Z

    Three studies were completed to evaluate four alternatives to the disposal of intact spent fuel assemblies in a geologic repository. A preferred spent fuel waste form for disposal was recommended on consideration of (1) package design and fuel/package interaction, (2) long-term, in-repository performance of the waste form, and (3) overall process performance and costs for packaging, handling, and emplacement. The four basic alternative waste forms considered were (1) end fitting removal, (2) fission gas venting, (3) disassembly and close packing, and (4) shearing/immobilization. None of the findings ruled out any alternative on the basis of waste package considerations or long-term performance of the waste form. The third alternative offers flexibility in loading that may prove attractive in the various geologic media under consideration, greatly reduces the number of packages, and has the lowest unit cost. These studies were completed in October, 1981. Since then Westinghouse Electric Corporation and the Office of Nuclear Waste Isolation have completed studies in related fields. This report is now being published to provide publicly the background material that is contained within. 47 references, 28 figures, 31 tables.

  17. Department of Forest and Wood Science Academic Programmes for 2014

    E-Print Network [OSTI]

    Geldenhuys, Jaco

    ; harvesting and supply; biomass conversion; energy production; marketing of bio-energy; economicsDepartment of Forest and Wood Science Academic Programmes for 2014 Postgraduate Diploma Enquiries: Head of Department Contact details: Department of Forest and Wood Science Stellenbosch University

  18. Trends and Market Effects of Wood Energy Policies

    E-Print Network [OSTI]

    Trends and Market Effects of Wood Energy Policies Bengt Hillring SLU SWEDEN http://www.unece.org/trade/timber/docs/tc-sessions/tc-61/presentations/10-hillring.pdf #12;Introduction · Industrial use of wood fibre has increased · Oil

  19. A study of the molecular mechanics of wood cell walls

    E-Print Network [OSTI]

    Adler, David, S.M. (David C.). Massachusetts Institute of Technology

    2013-01-01T23:59:59.000Z

    Wood is the original structural material, developed by nature to support tall plants. Every advantageous feature of wood as used in artificial structures is rooted in the plant's evolved capability to withstand the conditions ...

  20. Method of predicting mechanical properties of decayed wood

    DOE Patents [OSTI]

    Kelley, Stephen S.

    2003-07-15T23:59:59.000Z

    A method for determining the mechanical properties of decayed wood that has been exposed to wood decay microorganisms, comprising: a) illuminating a surface of decayed wood that has been exposed to wood decay microorganisms with wavelengths from visible and near infrared (VIS-NIR) spectra; b) analyzing the surface of the decayed wood using a spectrometric method, the method generating a first spectral data of wavelengths in VIS-NIR spectra region; and c) using a multivariate analysis to predict mechanical properties of decayed wood by comparing the first spectral data with a calibration model, the calibration model comprising a second spectrometric method of spectral data of wavelengths in VIS-NIR spectra obtained from a reference decay wood, the second spectral data being correlated with a known mechanical property analytical result obtained from the reference decayed wood.

  1. Assembly history dictates ecosystem functioning: evidence from wood decomposer communities

    E-Print Network [OSTI]

    Bruns, Tom

    ForReview Only Assembly history dictates ecosystem functioning: evidence from wood decomposer change, community assembly, ecosystem functioning, New Zealand Nothofagus (beech) forests, priority dictates ecosystem functioning: evidence from wood decomposer communities Tadashi Fukami1,2,3 , Ian A

  2. Clean-Burning Wood Stove Grant Program (Maryland)

    Broader source: Energy.gov [DOE]

    The Maryland Energy Administration (MEA) now offers the Clean Burning Wood Stove Grant program as part of its Residential Clean Energy Grant Program. The Clean Burning Wood Stove Grant program...

  3. Guide to Using Wood Ash as an Agricultural Soil Amendment

    E-Print Network [OSTI]

    New Hampshire, University of

    from larger commercial sources such as wood-burning biomass plants which produce heat or electricity in the soil. Wood ash is more soluble and reactive than ground limestone, and brings about a Benefits Recycles

  4. RADIATION ANALYSIS OF A SPENT-FUEL STORAGE CASK

    E-Print Network [OSTI]

    Shultis, J. Kenneth

    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 a single Transnuclear spent-fuel storage cask holding 68 design-basis fuel assemblies (a TN-68 cask

  5. Characterization plan for Hanford spent nuclear fuel

    SciTech Connect (OSTI)

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

    1994-12-01T23:59:59.000Z

    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.

  6. International Trade of Wood Pellets (Brochure)

    SciTech Connect (OSTI)

    Not Available

    2013-05-01T23:59:59.000Z

    The production of wood pellets has increased dramatically in recent years due in large part to aggressive emissions policy in the European Union; the main markets that currently supply the European market are North America and Russia. However, current market circumstances and trade dynamics could change depending on the development of emerging markets, foreign exchange rates, and the evolution of carbon policies. This fact sheet outlines the existing and potential participants in the wood pellets market, along with historical data on production, trade, and prices.

  7. The Storage and Seasoning of Pecan Bud Wood.

    E-Print Network [OSTI]

    Brison, Fred R. (Fred Robert)

    1933-01-01T23:59:59.000Z

    be returned to cold storage and will remain ready for use at a later date. It has been found that bud wood cut late in the dormant period seasons in a shorter time than that cut early. Bud wood of the Delmas variety seasons more readiIy than that of Stuart... _._-_._.--__..__------~-..._..--_...._.--_.....-. Relation of Time of Cutting Bud Wood to Seasoning ._.__....._._-___._------------ ., Relative Response of Stuart and Delmas in Seasoning _---..__._.__....._.---....-....--.- 10 Number of Days for Seasoning Bud Wood During Different Months .... 12 Storage...

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

    SciTech Connect (OSTI)

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

    1982-11-01T23:59:59.000Z

    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.

  9. APPLIED ISSUES Effects of agriculture on wood breakdown and microbial

    E-Print Network [OSTI]

    Webster, Jackson R.

    creating the potential for recovery of ecosystem processes. 2. We examined wood breakdown and microbial breakdown. Wood may not be desirable as a tool for Correspondence: M. E. McTammany, Biology DepartmentAPPLIED ISSUES Effects of agriculture on wood breakdown and microbial biofilm respiration

  10. Landfill Disposal of CCA-Treated Wood with Construction and

    E-Print Network [OSTI]

    Florida, University of

    Landfill Disposal of CCA-Treated Wood with Construction and Demolition (C&D) Debris: Arsenic phased out of many residential uses in the United States, the disposal of CCA-treated wood remains. Catastrophic events have also led to the concentrated disposal of CCA-treated wood, often in unlined landfills

  11. Wood Fuel Future: The Potential Web Text December 2010

    E-Print Network [OSTI]

    Wood Fuel Future: The Potential Web Text 31st December 2010 Wood Fuel Future: The Potential Wood Fuel Future : The Potential Renewable Energy is a key part of our Energy Policy. This UK Government by 2020. This should reduce carbon emissions from fossil fuel by 60% by the year 2050. The Welsh Assembly

  12. Center for Wood Utilization Progress Report for Fiscal Year 2010

    E-Print Network [OSTI]

    Tullos, Desiree

    , Asia, and Latin America. A business plan was developed to capture 1% of the $2.5 billion h manufacturing; and (c) lead to more efficient use of renewable wood-based materials for the benefit of Americans. Renewable wood is essential to human existence. Wood utilization research is critical to national needs

  13. Sulfur X-Ray Absorption And Vibrational Spectroscopic Study of Sulfur Dioxide, Sulfite, And Sulfonate Solutions And of the Substituted Sulfonate Ions X(3)CSO(3-)(X = H, Cl, F)

    SciTech Connect (OSTI)

    Risberg, E.Damian; Eriksson, L.; Mink, J.; Pettersson, L.G.M.; Skripkin, M.Yu.; Sandstrom, M.

    2009-06-02T23:59:59.000Z

    Sulfur K-edge X-ray absorption near-edge structure (XANES) spectra have been recorded and the S(1s) electron excitations evaluated by means of density functional theory-transition potential (DFT-TP) calculations to provide insight into the coordination, bonding, and electronic structure. The XANES spectra for the various species in sulfur dioxide and aqueous sodium sulfite solutions show considerable differences at different pH values in the environmentally important sulfite(IV) system. In strongly acidic (pH < {approx}1) aqueous sulfite solution the XANES spectra confirm that the hydrated sulfur dioxide molecule, SO{sub 2}(aq), dominates. The theoretical spectra are consistent with an OSO angle of {approx}119{sup o} in gas phase and acetonitrile solution, while in aqueous solution hydrogen bonding reduces the angle to {approx}116{sup o}. The hydration affects the XANES spectra also for the sulfite ion, SO{sub 3}{sup 2-}. At intermediate pH (4) the two coordination isomers, the sulfonate (HSO{sub 3{sup -}}) and hydrogen sulfite (SO{sub 3}H{sup -}) ions with the hydrogen atom coordinated to sulfur and oxygen, respectively, could be distinguished with the ratio HSO{sub 3{sup -}}:SO{sub 3}H{sup -} about 0.28:0.72 at 298 K. The relative amount of HSO{sub 3{sup -}} increased with increasing temperature in the investigated range from 275 to 343 K. XANES spectra of sulfonate, methanesulfonate, trichloromethanesulfonate, and trifluoromethanesulfonate compounds, all with closely similar S-O bond distances in tetrahedral configuration around the sulfur atom, were interpreted by DFT-TP computations. The energy of their main electronic transition from the sulfur K-shell is about 2478 eV. The additional absorption features are similar when a hydrogen atom or an electron-donating methyl group is bonded to the -SO{sub 3} group. Significant changes occur for the electronegative trichloromethyl (Cl{sub 3}C-) and trifluoromethyl (F{sub 3}C-) groups, which strongly affect the distribution especially of the {pi} electrons around the sulfur atom. The S-D bond distance 1.38(2) {angstrom} was obtained for the deuterated sulfonate (DSO{sub 3{sup -}}) ion by Rietveld analysis of neutron powder diffraction data of CsDSO{sub 3}. Raman and infrared absorption spectra of the CsHSO{sub 3}, CsDSO{sub 3}, H{sub 3}CSO{sub 3}Na, and Cl{sub 3}CSO{sub 3}Na{center_dot}H{sub 2}O compounds and Raman spectra of the sulfite solutions have been interpreted by normal coordinate calculations. The C-S stretching force constant for the trichloromethanesulfonate ion obtains an anomalously low value due to steric repulsion between the Cl{sub 3}C- and -SO{sub 3} groups. The S-O stretching force constants were correlated with corresponding S-O bond distances for several oxosulfur species.

  14. Storage of LWR spent fuel in air: Volume 1: Design and operation of a spent fuel oxidation test facility

    SciTech Connect (OSTI)

    Thornhill, C.K.; Campbell, T.K.; Thornhill, R.E.

    1988-12-01T23:59:59.000Z

    This report describes the design and operation and technical accomplishments of a spent-fuel oxidation test facility at the Pacific Northwest Laboratory. The objective of the experiments conducted in this facility was to develop a data base for determining spent-fuel dry storage temperature limits by characterizing the oxidation behavior of light-water reactor (LWR) spent fuels in air. These data are needed to support licensing of dry storage in air as an alternative to spent-fuel storage in water pools. They are to be used to develop and validate predictive models of spent-fuel behavior during dry air storage in an Independent Spent Fuel Storage Installation (ISFSI). The present licensed alternative to pool storage of spent fuel is dry storage in an inert gas environment, which is called inerted dry storage (IDS). Licensed air storage, however, would not require monitoring for maintenance of an inert-gas environment (which IDS requires) but does require the development of allowable temperature limits below which UO/sub 2/ oxidation in breached fuel rods would not become a problem. Scoping tests at PNL with nonirradiated UO/sub 2/ pellets and spent-fuel fragment specimens identified the need for a statistically designed test matrix with test temperatures bounding anticipated maximum acceptable air-storage temperatures. This facility was designed and operated to satisfy that need. 7 refs.

  15. Wood Fired Steam Plants in Georgia 

    E-Print Network [OSTI]

    Bulpitt, W. S.

    1983-01-01T23:59:59.000Z

    . Shortly after that time, Georgia Tech and the Georgia Forestry Commission embarked on a number of projects directed toward providing the use of wood as an industrial energy source. This paper will present an overview of these programs with an emphasis...

  16. Woods Safety SFRC UF 7/09

    E-Print Network [OSTI]

    Watson, Craig A.

    Woods Safety SFRC UF 7/09 #12;Working alone #12;Poison Plants Poison ivy (Toxicodendron radicans) Poison oak (Toxicodendron pubescens) #12;Commonly Mistaken Plants Virginia creeper (Parthenocissus quinquefolia) Blackberry (Rubus spp.) Three leaflets let it be! #12;Poison Ivy/Oak Prevention: · Wear long

  17. Updated 1-12 Bryan H. Wood

    E-Print Network [OSTI]

    as an attorney with the Department of the Navy's Office of the General Counsel (OGC). Initially appointed as ONR Counsel in 2007, he was the first Navy OGC attorney to deploy to a combat zone in his civilian OGC Force-Horn of Africa (CJTF-HOA) in Djibouti, Africa. Mr. Wood began his career with Navy OGC

  18. A Wood-Fired Gas Turbine Plant 

    E-Print Network [OSTI]

    Powell, S. H.; Hamrick, J. T.

    1986-01-01T23:59:59.000Z

    This paper covers the research and development of a wood-fired gas turbine unit that is used for generating electricity. The system uses one large cyclonic combustor and a cyclone cleaning system in series to provide hot gases to drive an Allison T...

  19. CORRUPTION AND ILLEGAL LOGGING IN THE WOOD

    E-Print Network [OSTI]

    Pettenella, Davide

    CORRUPTION AND ILLEGAL LOGGING IN THE WOOD PRODUCTS MARKET: the Italian experience in controlling Science 7 May 2004 Paper organization 1. State of the problem 2. Are Italian companies involved in deforestation and trade of illegal logging? 3. Which are the most affected countries? 4. Why do we need

  20. PASSION FOR WOOD THE DLH GROUP 2006

    E-Print Network [OSTI]

    countries on 5 continents · 19 timber merchant companies in Denmark, 10 of which have do-it-yourself stores Division consists of 19 timber merchant companies in Denmark, just over half of which have an adjacent doPASSION FOR WOOD THE DLH GROUP 2006 #12;54% 21% 25% ONE OF THE WORLD'S MAJOR TIMBER WHOLESALERS

  1. Energie-Cits 2001 BIOMASS -WOOD

    E-Print Network [OSTI]

    Energie-Cités 2001 BIOMASS - WOOD Gasification / Cogeneration ARMAGH United Kingdom Gasification is transferring the combustible matters in organic waste or biomass into gas and pure char by burning the fuel via it allows biomass in small-scaled engines and co-generation units ­ which with conventional technologies

  2. Harvested Wood Products -an Incentive for Deforestation?

    E-Print Network [OSTI]

    Fischlin, Andreas

    1 Harvested Wood Products - an Incentive for Deforestation? Andreas Fischlin1 Abstract Mitigation for deforestation is real. To curb the disadvantages of HWP, some debiting of non-sustainable forest management activities are implemented that provide true disincentives to deforestation, HWP may continue to create some

  3. Fast Curing of Composite Wood Products

    SciTech Connect (OSTI)

    Dr. Arthur J. Ragauskas

    2006-04-26T23:59:59.000Z

    The overall objective of this program is to develop low temperature curing technologies for UF and PF resins. This will be accomplished by: • Identifying the rate limiting UF and PF curing reactions for current market resins; • Developing new catalysts to accelerate curing reactions at reduced press temperatures and times. In summary, these new curing technologies will improve the strength properties of the composite wood products and minimize the detrimental effects of wood extractives on the final product while significantly reducing energy costs for wood composites. This study is related to the accelerated curing of resins for wood composites such as medium density fiberboard (MDF), particle board (PB) and oriented strandboard (OSB). The latter is frequently manufactured with a phenol-formaldehyde resin whereas ureaformaldehyde (UF) resins are usually used in for the former two grades of composite wood products. One of the reasons that hinder wider use of these resins in the manufacturing of wood composites is the slow curing speed as well as inferior bondability of UF resin. The fast curing of UP and PF resins has been identified as an attractive process development that would allow wood to be bonded at higher moisture contents and at lower press temperatures that currently employed. Several differing additives have been developed to enhance cure rates of PF resins including the use of organic esters, lactones and organic carbonates. A model compound study by Conner, Lorenz and Hirth (2002) employed 2- and 4-hydroxymethylphenol with organic esters to examine the chemical basis for the reported enhanced reactivity. Their studies suggested that the enhance curing in the presence of esters could be due to enhanced quinone methide formation or enhanced intermolecular SN2 reactions. In either case the esters do not function as true catalysts as they are consumed in the reaction and were not found to be incorporated in the polymerized resin product. An alternative approach to accelerated PF curing can be accomplished with the addition amines or amides. The later functionality undergoes base catalyzed hydrolysis yielding the corresponding carboxyl ate and free amine which rapidly reacts with the phenolic methylol groups facilitating polymerization and curing of the PF resin (Pizzi, 1997).

  4. Wye Wood Project Tackling rural social deprivation

    E-Print Network [OSTI]

    , and unemployment, the project seeks to overcome these problems through the power of nature. By putting trees opportunities, skills training, and conservation work, and given people quality time spent in the natural the unemployed, ex-offenders, ethnic minorities, disabled, and people with no access to the countryside

  5. Spent Fuel Transportation Package Performance Study - Experimental Design Challenges

    SciTech Connect (OSTI)

    Snyder, A. M.; Murphy, A. J.; Sprung, J. L.; Ammerman, D. J.; Lopez, C.

    2003-02-25T23:59:59.000Z

    Numerous studies of spent nuclear fuel transportation accident risks have been performed since the late seventies that considered shipping container design and performance. Based in part on these studies, NRC has concluded that the level of protection provided by spent nuclear fuel transportation package designs under accident conditions is adequate. [1] Furthermore, actual spent nuclear fuel transport experience showcase a safety record that is exceptional and unparalleled when compared to other hazardous materials transportation shipments. There has never been a known or suspected release of the radioactive contents from an NRC-certified spent nuclear fuel cask as a result of a transportation accident. In 1999 the United States Nuclear Regulatory Commission (NRC) initiated a study, the Package Performance Study, to demonstrate the performance of spent fuel and spent fuel packages during severe transportation accidents. NRC is not studying or testing its current regulations, a s the rigorous regulatory accident conditions specified in 10 CFR Part 71 are adequate to ensure safe packaging and use. As part of this study, NRC currently plans on using detailed modeling followed by experimental testing to increase public confidence in the safety of spent nuclear fuel shipments. One of the aspects of this confirmatory research study is the commitment to solicit and consider public comment during the scoping phase and experimental design planning phase of this research.

  6. Spent fuel dry storage technology development: thermal evaluation of sealed storage cask containing spent fuel

    SciTech Connect (OSTI)

    Schmitten, P.F.; Wright, J.B.

    1980-08-01T23:59:59.000Z

    A PWR spent fuel assembly was encapsulated inside the E-MAD Hot Bay and placed in a instrumented above surface storage cell during December 1978 for thermal testing. Instrumentation provided to measure canister, liner and concrete temperatures consisted of thermocouples which were inserted into tubes on the outside of the canister and liner and in three radial positions in the concrete. Temperatures from the SSC test assembly have been recorded throughout the past 16 months. Canister and liner temperatures have reached their peak values of 200{sup 0}F and 140{sup 0}F, respectively. Computer predictions of the transient and steady-state temperatures show good agreement with the test data.

  7. Development of Technical Nuclear Forensics for Spent Research Reactor Fuel

    E-Print Network [OSTI]

    Sternat, Matthew Ryan 1982-

    2012-11-20T23:59:59.000Z

    , an inverse analysis was developed to re-construct the burnup, initial uranium isotopic compositions, and cooling time of a research reactor spent fuel sample. A convergence acceleration technique was used that consisted of an analytical calculation to predict...

  8. Effect of Helium Accumulation on the Spent Fuel Microstructure

    SciTech Connect (OSTI)

    Ferry, Cecile [Department of Physico-chemistry, Commissariat a l'Energie Atomique, CEA-Saclay, Gif-sur-Yvette, 91191 (France); Piron, Jean-Paul [Commisariat a l'Energie Atomique, CEA - Cadarache, Saint-Paul Lez Durance, 13108 (France); Stout, Ray [Rho Beta Sigma Affaires, Livermore, CA, CA 94550 (United States)

    2007-07-01T23:59:59.000Z

    In a nuclear spent fuel repository, the aqueous rapid release of radio-activity from exposed spent fuel surfaces will depend on the pellet microstructure at the arrival time of water into the disposal container. Research performed on spent fuel evolution in a closed system has shown that the evolution of microstructure under disposal conditions should be governed by the cumulated {alpha}-decay damage and the subsequent helium behavior. The evolution of fission gas bubble characteristics under repository conditions has to be assessed. In UO{sub 2} fuels with a burnup of 47.5 GWd/t, the pressure in fission gas bubbles, including the pressure increase from {alpha}-decay helium atoms, is not expected to reach the critical bubble pressure that will cause failure, thus micro-cracking in UO{sub 2} spent fuel grains is not expected. (authors)

  9. area spent fuel: Topics by E-print Network

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

    2009-05-15 8 Nuclear Waste Imaging and Spent Fuel Verification by Muon Tomography CERN Preprints Summary: This paper explores the use of cosmic ray muons to image the...

  10. atucha spent fuel: Topics by E-print Network

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

    2009-05-15 8 Nuclear Waste Imaging and Spent Fuel Verification by Muon Tomography CERN Preprints Summary: This paper explores the use of cosmic ray muons to image the...

  11. ahwr spent fuel: Topics by E-print Network

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

    2009-05-15 8 Nuclear Waste Imaging and Spent Fuel Verification by Muon Tomography CERN Preprints Summary: This paper explores the use of cosmic ray muons to image the...

  12. Risk and Responsibility Sharing in Nuclear Spent Fuel Management

    E-Print Network [OSTI]

    De Roo, Guillaume

    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 ...

  13. Inventory of LWR spent nuclear fuel in the 324 Building

    SciTech Connect (OSTI)

    Jenquin, U.P.

    1996-09-01T23:59:59.000Z

    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.

  14. Application of ALARA principles to shipment of spent nuclear fuel

    SciTech Connect (OSTI)

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

    1980-05-01T23:59:59.000Z

    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.

  15. INVESTIGATIONS ON HYDRAULIC CEMENTS FROM SPENT OIL SHALE

    E-Print Network [OSTI]

    Mehta, P.K.

    2012-01-01T23:59:59.000Z

    ON HYDRAULIC CEMENTS FROM SPENT OIL SHALE P.K. Mehta and P.Cement Manufacture from Oil Shale, U.S. Patent 2,904,445,203 (1974), E. D. York, Amoco Oil Co. , letter to J, P. Fox,

  16. INVESTIGATIONS ON HYDRAULIC CEMENTS FROM SPENT OIL SHALE

    E-Print Network [OSTI]

    Mehta, P.K.

    2012-01-01T23:59:59.000Z

    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,

  17. Thermal Cooling Limits of Sbotaged Spent Fuel Pools

    SciTech Connect (OSTI)

    Dr. Thomas G. Hughes; Dr. Thomas F. Lin

    2010-09-10T23:59:59.000Z

    To develop the understanding and predictive measures of the post “loss of water inventory” hazardous conditions as a result of the natural and/or terrorist acts to the spent fuel pool of a nuclear plant. This includes the thermal cooling limits to the spent fuel assembly (before the onset of the zircaloy ignition and combustion), and the ignition, combustion, and the subsequent propagation of zircaloy fire from one fuel assembly to others

  18. Spent nuclear fuel Canister Storage Building CDR Review Committee report

    SciTech Connect (OSTI)

    Dana, W.P.

    1995-12-01T23:59:59.000Z

    The Canister Storage Building (CSB) is a subproject under the Spent Nuclear Fuels Major System Acquisition. This subproject is necessary to design and construct a facility capable of providing dry storage of repackaged spent fuels received from K Basins. The CSB project completed a Conceptual Design Report (CDR) implementing current project requirements. A Design Review Committee was established to review the CDR. This document is the final report summarizing that review

  19. Spent nuclear fuel discharges from U.S. reactors 1994

    SciTech Connect (OSTI)

    NONE

    1996-02-01T23:59:59.000Z

    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.

  20. Conditioning of spent nuclear fuel for permanent disposal

    SciTech Connect (OSTI)

    Laidler, J.J.

    1994-10-01T23:59:59.000Z

    A compact, efficient method for conditioning spent nuclear fuel is under development This method, known as pyrochemical processing, or {open_quotes}pyroprocessing,{close_quotes} provides a separation of fission products from the actinide elements present in spent fuel and further separates pure uranium from the transuranic elements. The process can facilitate the timely and environmentally-sound treatment of the highly diverse collection of spent fuel currently in the inventory of the United States Department of Energy (DOE). The pyroprocess utilizes elevated-temperature processes to prepare spent fuel for fission product separation; that separation is accomplished by a molten salt electrorefining step that provides efficient (99.9%) separation of transuranics. The resultant waste forms from the pyroprocess are stable under envisioned repository environment conditions and highly leach-resistant. Treatment of any spent fuel type produces a set of common high-level waste forms, one a mineral and the other a metal alloy, that can be readily qualified for repository disposal and preclude the substantial costs that would be associated with the qualification of the numerous spent fuel types included in the DOE inventory.

  1. Reactor-specific spent fuel discharge projections, 1987-2020

    SciTech Connect (OSTI)

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

    1988-03-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    Bailey, W.J.

    1990-11-01T23:59:59.000Z

    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.

  3. The united kingdom's changing requirements for spent fuel storage

    SciTech Connect (OSTI)

    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

    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.

  4. Reactor-specific spent fuel discharge projections: 1985 to 2020

    SciTech Connect (OSTI)

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

    1986-09-01T23:59:59.000Z

    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.

  5. Neutron Generators for Spent Fuel Assay

    SciTech Connect (OSTI)

    Ludewigt, Bernhard A

    2010-12-30T23:59:59.000Z

    The Next Generation Safeguards Initiative (NGSI) of the U.S. DOE has initiated a multi-lab/university collaboration to quantify the plutonium (Pu) mass in, and detect the diversion of pins from, spent nuclear fuel (SNF) assemblies with non-destructive assay (NDA). The 14 NDA techniques being studied include several that require an external neutron source: Delayed Neutrons (DN), Differential Die-Away (DDA), Delayed Gammas (DG), and Lead Slowing-Down Spectroscopy (LSDS). This report provides a survey of currently available neutron sources and their underlying technology that may be suitable for NDA of SNF assemblies. The neutron sources considered here fall into two broad categories. The term 'neutron generator' is commonly used for sealed devices that operate at relatively low acceleration voltages of less than 150 kV. Systems that employ an acceleration structure to produce ion beam energies from hundreds of keV to several MeV, and that are pumped down to vacuum during operation, rather than being sealed units, are usually referred to as 'accelerator-driven neutron sources.' Currently available neutron sources and future options are evaluated within the parameter space of the neutron generator/source requirements as currently understood and summarized in section 2. Applicable neutron source technologies are described in section 3. Commercially available neutron generators and other source options that could be made available in the near future with some further development and customization are discussed in sections 4 and 5, respectively. The pros and cons of the various options and possible ways forward are discussed in section 6. Selection of the best approach must take a number of parameters into account including cost, size, lifetime, and power consumption, as well as neutron flux, neutron energy spectrum, and pulse structure that satisfy the requirements of the NDA instrument to be built.

  6. Shippingport Spent Fuel Canister System Description

    SciTech Connect (OSTI)

    JOHNSON, D.M.

    2000-03-27T23:59:59.000Z

    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.

  7. Generation, Use, Disposal, and Management Options for CCA-Treated Wood

    E-Print Network [OSTI]

    Florida, University of

    Generation, Use, Disposal, and Management Options for CCA-Treated Wood May 1998 Helena Solo, INVENTORY OF CCA-TREATED WOOD IN FLORIDA II.1 Characteristics of the Florida Wood Treatment Industry in 1996 10 II.2 Generation and Disposal of Cca-treated Wood 14 II.3 Disposal Reservoirs for Cca-treated Wood

  8. Society of Wood Science and Technology State-of-the-Art Review

    E-Print Network [OSTI]

    Society of Wood Science and Technology State-of-the-Art Review CHEMICAL COUPLING IN WOOD FIBER. In this paper, we review coupling agents, pretreatment, and mixing technology for wood fiber and polymer and adhesion Wood ond trhc,r S c r r ~ ~ Society of Wood Sclencc

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

    DOE Patents [OSTI]

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

    2010-04-20T23:59:59.000Z

    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.

  10. Spent Nuclear Fuel (SNF) Project Product Specification

    SciTech Connect (OSTI)

    PAJUNEN, A.L.

    2000-12-07T23:59:59.000Z

    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.

  11. Wood-boring Insects of Trees and Shrubs

    E-Print Network [OSTI]

    Drees, Bastiaan M.; Jackman, John A.; Merchant, Michael E.

    2008-06-17T23:59:59.000Z

    This publication explains how to identify and control wood-boring insects that invade shrubs and shade trees in Texas. 12 pages, 9 figures, 6 photographs, 1 table...

  12. From: FERGAS To: Wood, Natalie (CONTR); Moore, Larine Subject...

    Energy Savers [EERE]

    Wood, Natalie (CONTR); Moore, Larine Subject: FW: FE Docket No. 14-96-LNG Date: Friday, October 24, 2014 3:17:49 PM Attachments: image001.png ---...

  13. arsenate cca wood: Topics by E-print Network

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

    in Renewable Energy Websites Summary: of primary energy in Estonia Wood fuels production Pellet firing projects in Estonia - SIDA Demo East firing projects in...

  14. anisotropic olivier wood: Topics by E-print Network

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

    in Renewable Energy Websites Summary: of primary energy in Estonia Wood fuels production Pellet firing projects in Estonia - SIDA Demo East firing projects in Estonia:...

  15. Microsoft Word - CX-Murray-CusterWoodPoles_WEB.doc

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

    Covington SUBJECT: Environmental Clearance Memorandum Steve Scott Line Foreman III - TFNF-Snohomish Proposed Action: Wood pole replacement at selected locations along the...

  16. FIEA Advancing Wood Technology Forest Industry Engineering Scholarship

    E-Print Network [OSTI]

    Hickman, Mark

    year. Forestry and wood products companies, key product suppliers, researchers and technology qualification. This FIEA Scholarship has also been set up to encourage and support an outstanding student

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

    SciTech Connect (OSTI)

    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

    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)

  18. Modeling of Spent Fuel Oxidation at Low Temperature

    SciTech Connect (OSTI)

    Poulesquen, Arnaud; Ferry, Cecile [Department of Physico Chemistry, CEA, Gif sur Yvette, 91191 (France); Desgranges, Lionel [Department of Spent Fuel Studies, CEA, St Paul lez Durance, 13108 (France)

    2007-07-01T23:59:59.000Z

    During dry storage, the oxidation of the spent fuel in case of cladding and container failure (accidental scenario) could be detrimental for further handling of the spent fuel rod and for the safety of the facilities. Depending on whether the uranium dioxide is under the form of powder or pellet, irradiated or unirradiated, the weight gain curves do not present the same shape. To account for these different behaviours, two models have been developed. Firstly, the oxidation of unirradiated powders has been modelled based on the coexistence, during the oxidation, of two intermediate products, U{sub 4}O{sub 9} and U{sub 3}O{sub 7}. The comparison between the calculation and the literature data is good in terms of weight gain curves and chemical diffusion coefficient of oxygen within the two phases. Secondly, the oxidation of spent fuel fragments is approached by a convolution procedure between a grain oxidation model and an empirical parameter which represents the linear oxidation speed of grain boundary or an average distance able to cover the entire spent fuel fragment. This procedure of calculation allows in one hand to account for the incubation period noticed on unirradiated pellets or spent fuel and in another hand to link the empirical parameter to physical as porosity, cracks or linear power, or operational parameters such as fission gas release (FGR) respectively. A comparison of this new modelling with experimental data will be proposed. (authors)

  19. Home Page > Business > Industrial > Global Trade Of Wood Chips Down 26% In 2009 As Pulpmills Reduce Production Worldwide, Reports Wood Resources International

    E-Print Network [OSTI]

    in Europe searching for additional sources of woody biomass, it is likely that trade with wood chips On March 16-17, 2010, the 4th Global Wood Fiber Conference: Trade in Wood chips and Biomass worldwide, European demand for pellets and biomass chips, outlook for plantation wood chip supply, ocean

  20. Life in the woods : production and consumption of the urban forest

    E-Print Network [OSTI]

    Volicer, Nadine (Nadine M.)

    2012-01-01T23:59:59.000Z

    The use of wood is fraught with paradox. Wood as a building material is embraced for its naturalness, while the cutting of trees is indicted as a destruction of nature. Wood is lauded for its structural properties and ...

  1. How Wood Chip Size Affects Pretreatment Effectiveness of Woody Biomass for Biological Processing

    E-Print Network [OSTI]

    Tam, Jerry

    2013-01-01T23:59:59.000Z

    temperature treatment of aspen. Wood Sci Technol 40:371-391size- reduction of Poplar and Aspen wood. Biotechnology andHydrothermal Pretreatment of Aspen Wood Chips 5.1. Abstract

  2. Volatile constituents in a wood pyrolysis oil

    E-Print Network [OSTI]

    Lin, Shih-Chien

    1978-01-01T23:59:59.000Z

    , 1958]. . . . . . . . . . . . 4 Pyrolysis products of cellulose and treated cellulose at 600oC f Chin, 1973]. . . . . . . . . . . . . . . 6 3. Pyrolysis products of lignin at 450-550 C [Allen and Nattil a, 1971] Properties of wood pyrolysis oil. 12... and decom- 0 poses at 225-325 C. Cellulose decompos s at higher temp- eratures within a narrow range of 320-375 C. In other 0 words, the cell wall polysaccharides provide most of the vol ati) e products, while lignin predominantly forms a charred...

  3. Wood, Wisconsin: Energy Resources | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells, Wisconsin: Energy Resources JumpWood, Wisconsin: Energy Resources Jump

  4. Wood3 Resources | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to:Ezfeedflag JumpID-fTriWildcat 1 Wind Project JumpWisconsin: Energy ResourcesWolverineWood3

  5. Wood Energy 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnualProperty Edit withTianlinPapers Home Kyoung's pictureWindManitoba,WisconsinWonder SourceWood

  6. Wood To Fuel LLC | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directedAnnualProperty Edit withTianlinPapers Home Kyoung's pictureWindManitoba,WisconsinWonderWood To Fuel

  7. Mission Need Statement: Idaho Spent Fuel Facility Project

    SciTech Connect (OSTI)

    Barbara Beller

    2007-09-01T23:59:59.000Z

    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.

  8. Spent nuclear fuel discharges from US reactors 1993

    SciTech Connect (OSTI)

    Not Available

    1995-02-01T23:59:59.000Z

    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.

  9. Information handbook on independent spent fuel storage installations

    SciTech Connect (OSTI)

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

    1996-12-01T23:59:59.000Z

    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.

  10. Elements present in leach solutions from unsaturated spent fuel tests

    SciTech Connect (OSTI)

    Finn, P.A.; Bates, J.K.; Hoh, J.C.; Emery, J.W.; Hafenrichter, L.D.; Buck, E.C.; Gong, M.

    1993-10-01T23:59:59.000Z

    Preliminary results for the composition of the leachate from unsaturated tests at 90{degrees}C with spent fuel for 55--134 days with J-13 groundwater are reported. The pH of the leachate solutions was found to be acidic, ranging from 4 to 7. The actinide concentrations were 10{sup 5} greater than those reported for saturated spent fuel tests in which the leachate pH was 8. We also found that most species in the leachate were present as colloids containing both americium and curium. The presence of actinides in a form not currently included in repository radionuclide transport models provides information that can be used in spent fuel reaction modeling, the performance assessment of the repository and the design of the engineering barrier system. This report was prepared as part of the Yucca Mountain Site Characterization Project

  11. NUHOMS modular spent-fuel storage system: Performance testing

    SciTech Connect (OSTI)

    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

    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.

  12. Method for the regeneration of spent molten zinc chloride

    DOE Patents [OSTI]

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

    1981-01-01T23:59:59.000Z

    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.

  13. Wood-Fiber/High-Density-Polyethylene Composites: Compounding Process

    E-Print Network [OSTI]

    Wood-Fiber/High-Density-Polyethylene Composites: Compounding Process J. Z. Lu,1 Q. Wu,1 I. I strength and flexural modulus of the resultant composites. With 50 wt % wood fiber, the optimum compounding of the modified blends and the dynamic mechanical properties of the resultant composites. The melt torque

  14. Wood for energy at Bedgebury Forest Bedgebury visitor centre's

    E-Print Network [OSTI]

    Wood for energy at Bedgebury Forest Bedgebury visitor centre's woodfuel boiler provides a renewable source of energy and demonstrates that locally- produced wood has economic and sustainable value is stored outside but stacked off the ground to allow air to circulate. It is essential that the chips

  15. SECO - Dow Corning's Wood Fueled Industrial Cogeneration Project

    E-Print Network [OSTI]

    Betts, W. D.

    1982-01-01T23:59:59.000Z

    In 1979, Dow Corning Corporation decided to build a wood fueled steam and electric cogeneration (SECO) power plant at Midland, Michigan. This decision was prompted by the high cost of oil and natural gas, an abundant supply of wood in mid Michigan...

  16. Wood, energy and households: Perspectives on rural Kenya

    SciTech Connect (OSTI)

    Barnes, C.; Ensminger, J.; O'Keefe, P.

    1984-01-01T23:59:59.000Z

    This book presents papers on the use of wood fuels in Kenya. Topics considered include domestic energy consumption, historical aspects, the Kenyan economy, ecology, supply and demand, forests, aspects of energy consumption in a pastoral ecosystem, estimation of present and future demand for wood fuels, and energy source development.

  17. Emerging Markets for Wood Energy Richard Vlosky, Director

    E-Print Network [OSTI]

    ) are Woody Biomass Utilization Grants (Woody BUG) and Biomass Crop Assistance Program (BCAP) Renewable Fuel · The Louisiana Forest Products Development Center · Wood-to-Energy · Wood Biomass · Energy Options · Current Forest Products Development Center School of Renewable Natural Resources, LSU AgCenter & School

  18. SECO - Dow Corning's Wood Fueled Industrial Cogeneration Project 

    E-Print Network [OSTI]

    Betts, W. D.

    1982-01-01T23:59:59.000Z

    In 1979, Dow Corning Corporation decided to build a wood fueled steam and electric cogeneration (SECO) power plant at Midland, Michigan. This decision was prompted by the high cost of oil and natural gas, an abundant supply of wood in mid Michigan...

  19. Wood-based Energy Technologies Michigan offers some significant advantages

    E-Print Network [OSTI]

    quality stan- dards. Wood pellets are an attractive alternative for home heating or for larger individual--ground wood. Pellet storage area. #12;distributed through a District Energy grid. Efficiencies are high on municipal solid waste. Both district heating and CHP plants can also pro- duce pellets for local housing

  20. Relative Leaching and Aquatic Toxicity of Pressure-Treated Wood

    E-Print Network [OSTI]

    Florida, University of

    Relative Leaching and Aquatic Toxicity of Pressure-Treated Wood Products Using Batch Leaching Tests treated with one of five different waterborne chemical preservatives, were leached using 18-h batch- treated wood at concentrations above the U.S. federal toxicity characteristic limit (5 mg/L). All

  1. A Chemical Stain for Identifying Arsenic-Treated Wood

    E-Print Network [OSTI]

    Florida, University of

    A Chemical Stain for Identifying Arsenic-Treated Wood (FINAL) Submitted June 23, 2006 Amy Omae.2 Motivation 4 I.3 Objectives 5 CHAPTER II, DEVELOPMENT OF A CHEMICAL STAIN FOR IDENTIFYING ARSENIC-TREATED Applications 22 II.5 Resulting Stain to Identify Arsenic-Treated Wood and Methods of Testing 25 CHAPTER III

  2. FAO Forestry Department Wood Energy WISDOM East Africa

    E-Print Network [OSTI]

    FAO ­ Forestry Department ­ Wood Energy WISDOM ­ East Africa Woodfuel Integrated Supply and Tropical Southern Africa woodfuels, mainly fuelwood, contribute from 75 to 86 percent of total primary African countries Rudi Drigo Consultant - Wood energy planning and forest resources monitoring August 2005

  3. SURFACE CHARACTERIZATION OF CHEMICALLY MODIFIED WOOD: DYNAMIC WETTABILITY1

    E-Print Network [OSTI]

    wetting slope and K value) were used to illustrate the dynamic wetting process. Dynamic contact angle the dynamic wettability of wood surfaces modified with different coupling agents. Keywords: Chemical articles on dynamic wetting process for wood adhesion have been published (Scheikl and Dunky 1998

  4. Modelling piloted ignition of wood and plastics

    SciTech Connect (OSTI)

    Blijderveen, Maarten van [TNO, Schoemakerstraat 97, 2628 VK Delft (Netherlands); University of Twente, Department of Thermal Engineering, Drienerlolaan 5, 7522 NB Enschede (Netherlands); Bramer, Eddy A. [University of Twente, Department of Thermal Engineering, Drienerlolaan 5, 7522 NB Enschede (Netherlands); Brem, Gerrit, E-mail: g.brem@utwente.nl [University of Twente, Department of Thermal Engineering, Drienerlolaan 5, 7522 NB Enschede (Netherlands)

    2012-09-15T23:59:59.000Z

    Highlights: Black-Right-Pointing-Pointer We model piloted ignition times of wood and plastics. Black-Right-Pointing-Pointer The model is applied on a packed bed. Black-Right-Pointing-Pointer When the air flow is above a critical level, no ignition can take place. - Abstract: To gain insight in the startup of an incinerator, this article deals with piloted ignition. A newly developed model is described to predict the piloted ignition times of wood, PMMA and PVC. The model is based on the lower flammability limit and the adiabatic flame temperature at this limit. The incoming radiative heat flux, sample thickness and moisture content are some of the used variables. Not only the ignition time can be calculated with the model, but also the mass flux and surface temperature at ignition. The ignition times for softwoods and PMMA are mainly under-predicted. For hardwoods and PVC the predicted ignition times agree well with experimental results. Due to a significant scatter in the experimental data the mass flux and surface temperature calculated with the model are hard to validate. The model is applied on the startup of a municipal waste incineration plant. For this process a maximum allowable primary air flow is derived. When the primary air flow is above this maximum air flow, no ignition can be obtained.

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

    E-Print Network [OSTI]

    2006-01-01T23:59:59.000Z

    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

  6. Biomass plants face wood supply risks Report warns giant new biomass power plants will be hugely reliant on wood chip

    E-Print Network [OSTI]

    Biomass plants face wood supply risks Report warns giant new biomass power plants will be hugely's biomass energy sector could be undermined unless businesses move to resolve the supply chain issues-scale biomass plants will leave generators largely reliant on biomass from overseas such as wood chips, elephant

  7. Multipass comminution process to produce precision wood particles of uniform size and shape with disrupted grain structure from wood chips

    DOE Patents [OSTI]

    Dooley, James H; Lanning, David N

    2014-05-27T23:59:59.000Z

    A process of comminution of wood chips (C) having a grain direction to produce a mixture of wood particles (P), wherein the wood chips are characterized by an average length dimension (L.sub.C) as measured substantially parallel to the grain, an average width dimension (W.sub.C) as measured normal to L.sub.C and aligned cross grain, and an average height dimension (H.sub.C) as measured normal to W.sub.C and L.sub.C, and wherein the comminution process comprises the step of feeding the wood chips in a direction of travel substantially randomly to the grain direction one or more times through a counter rotating pair of intermeshing arrays of cutting discs (D) arrayed axially perpendicular to the direction of wood chip travel.

  8. Spent nuclear fuel project design basis capacity study

    SciTech Connect (OSTI)

    Cleveland, K.J.

    1996-09-09T23:59:59.000Z

    A parametric study of the Spent Nuclear Fuel Project system capacity is presented. The study was completed using a commercially available software package to develop a summary level model of the major project systems. Alternative configurations, sub-system cycle times, and operating scenarios were tested to identify their impact on total project duration and equipment requirements.

  9. Shippingport Spent Fuel Canister (SSFC) Design Report Project W-518

    SciTech Connect (OSTI)

    JOHNSON, D.M.

    2000-01-27T23:59:59.000Z

    The SSFC Design Report Describes A spent fuel canister for Shippingport Core 2 blanket fuel assemblies. The design of the SSFC is a minor modification of the MCO. The modification is limited to the Shield Plug which remains unchanged with regard to interfaces with the canister shell. The performance characteristics remain those for the MCO, which bounds the payload of the SSFC.

  10. Recycling practices of spent MgO-C refractories

    SciTech Connect (OSTI)

    Kwong, Kyei-Sing; Bennett, James P.

    2002-10-01T23:59:59.000Z

    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.

  11. Review of Drying Methods for Spent Nuclear Fuel

    SciTech Connect (OSTI)

    Large, W.S.

    1999-10-21T23:59:59.000Z

    SRTC is developing technology for direct disposal of aluminum spent nuclear fuel (SNF). The development program includes analyses and tests to support design and safe operation of a facility for ''road ready'' dry storage of SNF-filled canisters. The current technology development plan includes review of available SNF drying methods and recommendation of a drying method for aluminum SNF.

  12. Implementing Strategies for Drying and Pressing Wood Without Emissions Controls

    SciTech Connect (OSTI)

    Sujit Banerjee; Terrance Conners

    2007-09-07T23:59:59.000Z

    Drying and pressing wood for the manufacture of lumber, particleboard, oriented strand board (OSB), veneer and medium density fiberboard (MDF) release volatile organic compounds (VOCs) into the atmosphere. These emissions require control equipment that are capital-intensive and consume significant quantities of natural gas and electricity. The objective of our work was to understand the mechanisms through which volatile organic compounds are generated and released and to develop simple control strategies. Of the several strategies developed, two have been implemented for OSB manufacture over the course of this study. First, it was found that increasing final wood moisture by about 2-4 percentage points reduced the dryer emissions of hazardous air pollutants by over 70%. As wood dries, the escaping water evaporatively cools the wood. This cooling tapers off wood when the wood is nearly dry and the wood temperature rises. Thermal breakdown of the wood tissue occurs and VOCs are released. Raising the final wood moisture by only a few percentage points minimizes the temperature rise and reduces emissions. Evaporative cooling also impacts has implications for VOC release from wood fines. Flaking wood for OSB manufacture inevitable generates fines. Fines dry out rapidly because of their high surface area and evaporative cooling is lost more rapidly than for flakes. As a result, fines emit a disproportionate quantity of VOCs. Fines can be reduced in two ways: through screening of the green furnish and through reducing their generation during flaking. The second approach is preferable because it also increased wood yield. A procedure to do this by matching the sharpness angle of the flaker knife to the ambient temperature was also developed. Other findings of practical interests are as follows: Dielectric heating of wood under low-headspace conditions removes terpenes and other extractives from softwood; The monoterpene content in trees depend upon temperature and seasonal effects; Method 25A emissions from lumber drying can be modeled from a knowledge of the airflow through the kiln; A heat transfer model shows that VOCs released during hot-pressing mainly originate from the surface of the board; and Boiler ash can be used to adsorb formaldehyde from air streams.

  13. A Monte Carlo based spent fuel analysis safeguards strategy assessment

    SciTech Connect (OSTI)

    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

    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.

  14. 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...

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

    E-Print Network [OSTI]

    Lovett, Phyllis Maria

    1991-01-01T23:59:59.000Z

    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 ...

  16. 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...

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

    Office of Environmental Management (EM)

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

  18. Air Shipment of Spent Nuclear Fuel from Romania to Russia

    SciTech Connect (OSTI)

    Igor Bolshinsky; Ken Allen; Lucian Biro; Alexander Buchelnikov

    2010-10-01T23:59:59.000Z

    Romania successfully completed the world’s 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.

  19. Overview of the spent nuclear fuel project at Hanford

    SciTech Connect (OSTI)

    Daily, J.L. [Dept. of Energy, Richland, WA (United States). Richland Operations Office; Fulton, J.C.; Gerber, E.W.; Culley, G.E. [Westinghouse Hanford Co., Richland, WA (United States)

    1995-02-01T23:59:59.000Z

    The Spent Nuclear Fuel Project`s mission at Hanford is to {open_quotes}Provide safe, economic and environmentally sound management of Hanford spent nuclear fuel in a manner which stages it to final disposition.{close_quotes} The inventory of spent nuclear fuel (SNF) at the Hanford Site covers a wide variety of fuel types (production reactor to space reactor) in many facilities (reactor fuel basins to hot cells) at locations all over the Site. The 2,129 metric tons of Hanford SNF represents about 80% of the total US Department of Energy (DOE) inventory. About 98.5% of the Hanford SNF is 2,100 metric tons of metallic uranium production reactor fuel currently stored in the 1950s vintage K Basins in the 100 Area. This fuel has been slowly corroding, generating sludge and contaminating the basin water. This condition, coupled with aging facilities with seismic vulnerabilities, has been identified by several groups, including stakeholders, as being one of the most urgent safety and environmental concerns at the Hanford Site. As a direct result of these concerns, the Spent Nuclear Fuel Project was recently formed to address spent fuel issues at Hanford. The Project has developed the K Basins Path Forward to remove fuel from the basins and place it in dry interim storage. Alternatives that addressed the requirements were developed and analyzed. The result is a two-phased approach allowing the early removal of fuel from the K Basins followed by its stabilization and interim storage consistent with the national program.

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

    SciTech Connect (OSTI)

    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

    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 industry’s 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

  1. Examining 239Pu and 240Pu Nuclear Resonance Fluorescence Measurements on Spent Fuel for Nuclear Safeguards

    E-Print Network [OSTI]

    Quiter, Brian

    2013-01-01T23:59:59.000Z

    Spent Fuel Assay Using Nuclear Resonance Fluo- rescence,” Annual Meeting of the Institute of Nuclear Material Management,

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

    SciTech Connect (OSTI)

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

    1995-06-01T23:59:59.000Z

    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.

  3. Copyright (to be inserted by Humphrey) Thermal and Dynamic-mechanical Properties of Wood-PVC

    E-Print Network [OSTI]

    Citation & Copyright (to be inserted by Humphrey) Thermal and Dynamic-mechanical Properties of Wood-PVC properties, maleation, thermal analysis, wood veneer, wood-PVC composites ABSTRACT The influence of maleation on thermal and dynamic-mechanical properties of wood-PVC composites was investigated in this study

  4. Wood plastic composites based on microfibrillar blends of high density polyethylene/poly(ethylene terephthalate)

    E-Print Network [OSTI]

    Wood plastic composites based on microfibrillar blends of high density polyethylene January 2010 Keywords: Wood plastic composites Poly(ethylene terephthalate) Polyethylene Extrusion a b into wood plastic composites through a two-step reactive extrusion technology. Wood flour was added into pre

  5. Jmtland County Energy Agency Comfortable use of wood pellets in one-family houses in

    E-Print Network [OSTI]

    Jämtland County Energy Agency Sweden 1 Comfortable use of wood pellets in one-family houses-operation with the Swedish Energy Agency, carried through the project "Comfortable use of wood pellets in one-family houses of one-family houses to start using wood pellets and an increase of the use of wood pellets in one

  6. Dynamics of wood recruitment in streams of the northeastern US Dana R. Warren a,

    E-Print Network [OSTI]

    Kraft, Clifford E.

    : Large woody debris LWD Riparian forest Wood recruitment Wood dynamics Stream restoration Debris dam restoration efforts often incorporate large wood. In most cases, however, stream restoration projectsDynamics of wood recruitment in streams of the northeastern US Dana R. Warren a, *, Clifford E

  7. Author's personal copy Evaluation of methods for sorting CCA-treated wood

    E-Print Network [OSTI]

    Florida, University of

    Author's personal copy Evaluation of methods for sorting CCA-treated wood Gary Jacobi a , Helena contains treated wood including wood treated with chromated copper arsenate (CCA). Many recycling options of sorting methods for identifying treated wood. Sorting methods evaluated included visual sorting and visual

  8. PROPERTIES OF HDPE/CLAY/WOOD NANOCOMPOSITES , C. M. Clemons 2

    E-Print Network [OSTI]

    from wood, kenaf, flax, hemp, cotton, Kraft pulp, coconut husk, areca fruit, pineapple leaf, oil palm

  9. An economical and market analysis of Canadian wood pellets.

    SciTech Connect (OSTI)

    Peng, J. [University of British Columbia, Vancouver

    2010-08-01T23:59:59.000Z

    This study systematically examined the current and future wood pellet market, estimated the cost of Canadian torrefied pellets, and compared the torrefied pellets with the conventional pellets based on literature and industrial data. The results showed that the wood pellet industry has been gaining significant momentum due to the European bioenergy incentives and the rising oil and natural gas prices. With the new bioenergy incentives in USA, the future pellets market may shift to North America, and Canada can potentially become the largest pellet production centre, supported by the abundant wood residues and mountain pine beetle (MPB) infested trees.

  10. Method for lowering the VOCS emitted during drying of wood products

    DOE Patents [OSTI]

    Banerjee, Sujit (1832 Jacksons Creek Point, Marietta, GA 30068); Boerner, James Robert (154 Junedale Rd., Cincinnati, OH 45218); Su, Wei (2262 Orleans Ave., Marietta, GA 30062)

    2000-01-01T23:59:59.000Z

    The present invention is directed to a method for removal of VOCs from wood products prior to drying the wood products. The method of the invention includes the steps of providing a chamber having an opening for receiving wood and loading the chamber with green wood. The wood is loaded to an extent sufficient to provide a limited headspace in the chamber. The chamber is then closed and the wood is heated in the chamber for a time and at a temperature sufficient to saturate the headspace with moisture and to substantially transfer VOCs from the wood product to the moisture in the headspace.

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

    SciTech Connect (OSTI)

    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

    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.

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

    SciTech Connect (OSTI)

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

    1993-12-31T23:59:59.000Z

    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.

  13. Wood Gasification: Where It's At, Where It's Going

    E-Print Network [OSTI]

    Murphy, M. L.

    1981-01-01T23:59:59.000Z

    This paper discusses the principles and practice of various designs of biomass/wood gasifiers. In general, the basic principle of gasification is reviewed. A look at existing gasifier schemes, including packed bed updraft, downdraft, and fluidized...

  14. Wood Gasification: Where It's At, Where It's Going 

    E-Print Network [OSTI]

    Murphy, M. L.

    1981-01-01T23:59:59.000Z

    This paper discusses the principles and practice of various designs of biomass/wood gasifiers. In general, the basic principle of gasification is reviewed. A look at existing gasifier schemes, including packed bed updraft, downdraft, and fluidized...

  15. The Honorable John T. 'Gregorio 301 N. Wood Avenue

    Office of Legacy Management (LM)

    Wood Avenue Linden, 'New Jersey 07036 d. Dear Mayor Gregorio: ,' ,' .' , Secretary of Energy Hazel O'Leary has announced a new approach to openness, in the'llepartment' of...

  16. Disentangling Biodiversity and Climatic Determinants of Wood Production

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    an important role in carbon sequestration. Methodology/Principal Findings: We tested whether tree wood incorporating the role of biodiversity in management and policy plans for forest carbon sequestration. Citation

  17. Seismic rehabilitation of wood diaphragms in unreinforced masonary buildings

    E-Print Network [OSTI]

    Grubbs, Amber Jo

    2002-01-01T23:59:59.000Z

    The purpose of this study is to evaluate the seismic performance of existing and rehabilitated wood floor and roof diaphragms in typical pre-1950's, unreinforced masonry (URM) buildings found in the Central and Eastern portions of the United States...

  18. aspen wood chips: Topics by E-print Network

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

    8 COMPARISON OF DIFFERENT APPROACHES FOR THE SIMULATION OF BOILERS USING OIL, GAS, PELLETS OR WOOD CHIPS CiteSeer Summary: A detailed model for the simulation of boilers using...

  19. Kilowatts From Waste Wood In The Furniture Industry

    E-Print Network [OSTI]

    Nailen, R. L.

    1981-01-01T23:59:59.000Z

    recently, the Singer Furniture Co., Lenoir, N. Carolina, purchased a 450 kilowatt steam turbine/induction generator set to use extra steam - produced by 'free' waste wood fuel - in generating 15% of the plant's electrical energy demand. The turbine...

  20. An Overview of the U.S. Wood Preserving Industry

    E-Print Network [OSTI]

    Preservatives · Oilborne Preservatives · Creosote Treatments · Fire Retardants · Additives · Concluding Comments · Waterborne Preservatives · Oilborne Preservatives · Creosote Treatments · Fire Retardants · Additives a baselinewas to develop a baseline profile of the treated woodprofile of the treated wood manufacturing

  1. An Overview of the Louisiana Primary Solid Wood Products Industry

    E-Print Network [OSTI]

    goal of this second study is to profile the primary solid wood products industry. In addition (including pulp and paper) and secondary manufacturing establishments (Jacob et al. 1987). The forest

  2. RFPs Due for Hazardous Fuel Wood to Energy Grant

    Broader source: Energy.gov [DOE]

    The U.S. Forest Service requests proposals for the 2014 Hazardous Fuel Wood to Energy (W2E) Grant.  The outcome anticipated under this funding mechanism will advance the United States Department of...

  3. RFPs Due for Statewide Wood Energy Cooperative Agreement

    Broader source: Energy.gov [DOE]

    The U.S. Forest Service requests proposals for the 2014 Statewide Wood Energy Teams (SWET) Cooperative Agreement. The outcome anticipated under this funding mechanism will advance the United States...

  4. Long-term lime pretreatment of poplar wood 

    E-Print Network [OSTI]

    Sierra Ramirez, Rocio

    2006-04-12T23:59:59.000Z

    Lignocellulosic biomass (e.g., poplar wood) provides a unique and sustainable resource for environmentally safe organic fuels and chemicals. The core of this study is the pretreatment step involved in bioconversion processes. Pretreatment...

  5. Long-term lime pretreatment of poplar wood

    E-Print Network [OSTI]

    Sierra Ramirez, Rocio

    2006-04-12T23:59:59.000Z

    Lignocellulosic biomass (e.g., poplar wood) provides a unique and sustainable resource for environmentally safe organic fuels and chemicals. The core of this study is the pretreatment step involved in bioconversion processes. Pretreatment...

  6. Photo by Helvetas Moambique Architecture, Wood and Civil Engineering

    E-Print Network [OSTI]

    Wehrli, Bernhard

    Photo by Helvetas Moçambique Architecture, Wood and Civil Engineering #12;IWRM in order to maximize the resultant economic and social welfare in an equitable manner without CAS consists of the following units: - Basic knowledge in order to follow the class

  7. Wood Products Marketing And Value-Added Opportunities

    E-Print Network [OSTI]

    Wood Products Marketing And Value-Added Opportunities In Latin America: A Focus on Brazil Richard School of Renewable Natural Resources Louisiana State University Presented at: PANORAMA Curitiba, Brazil

  8. Nuclear Waste Imaging and Spent Fuel Verification by Muon Tomography

    E-Print Network [OSTI]

    Jonkmans, G; Jewett, C; Thompson, M

    2012-01-01T23:59:59.000Z

    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.

  9. Thermomechanical modeling of the Spent Fuel Test-Climax

    SciTech Connect (OSTI)

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

    1986-02-01T23:59:59.000Z

    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.

  10. Test plan for thermogravimetric analyses of BWR spent fuel oxidation

    SciTech Connect (OSTI)

    Einziger, R.E.

    1988-12-01T23:59:59.000Z

    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.

  11. 3DD - Three Dimensional Disposal of Spent Nuclear Fuel - 12449

    SciTech Connect (OSTI)

    Dvorakova, Marketa; Slovak, Jiri [Radioactive Waste Repository Authority (RAWRA), Prague (Czech Republic)

    2012-07-01T23:59:59.000Z

    Three dimensional disposal is being considered as a way in which to store long-term spent nuclear fuel in underground disposal facilities in the Czech Republic. This method involves a combination of the two most common internationally recognised disposal methods in order to practically apply the advantages of both whilst, at the same time, eliminating their weaknesses; the method also allows easy removal in case of potential re-use. The proposed method for the disposal of spent nuclear fuel will reduce the areal requirements of future deep geological repositories by more than 30%. It will also simplify the container handling process by using gravitational forces in order to meet requirements concerning the controllability of processes and ensuring operational and nuclear safety. With regard to the issue of the efficient potential removal of waste containers, this project offers an ingenious solution which does not disrupt the overall stability of the original disposal complex. (authors)

  12. Heat transfer modeling of dry spent nuclear fuel storage facilities

    SciTech Connect (OSTI)

    Lee, S.Y.

    1999-07-01T23:59:59.000Z

    The present work was undertaken to provide heat transfer model that accurately predicts the thermal performance of dry spent nuclear fuel storage facilities. One of the storage configurations being considered for DOE Aluminum-clad Spent Nuclear Fuel (Al-SNF), such as the Material and Testing Reactor (MTR) fuel, is in a dry storage facility. To support design studies of storage options a computational and experimental program has been conducted at the Savannah River Site (SRS). The main objective is to develop heat transfer models including natural convection effects internal to an interim dry storage canister and to geologic codisposal Waste Package (WP). Calculated temperatures will be used to demonstrate engineering viability of a dry storage option in enclosed interim storage and geologic repository WP and to assess the chemical and physical behaviors of the Al-SNF in the dry storage facilities. The current paper describes the modeling approaches and presents the computational results along with the experimental data.

  13. Heat Transfer Modeling of Dry Spent Nuclear Fuel Storage Facilities

    SciTech Connect (OSTI)

    Lee, S.Y.

    1999-01-13T23:59:59.000Z

    The present work was undertaken to provide heat transfer model that accurately predicts the thermal performance of dry spent nuclear fuel storage facilities. One of the storage configurations being considered for DOE Aluminum-clad Spent Nuclear Fuel (Al-SNF), such as the Material and Testing Reactor (MTR) fuel, is in a dry storage facility. To support design studies of storage options a computational and experimental program has been conducted at the Savannah River Site (SRS). The main objective is to develop heat transfer models including natural convection effects internal to an interim dry storage canister and to geological codisposal Waste Package (WP). Calculated temperatures will be used to demonstrate engineering viability of a dry storage option in enclosed interim storage and geological repository WP and to assess the chemical and physical behaviors of the Al-SNF in the dry storage facilities. The current paper describes the modeling approaches and presents the computational results along with the experimental data.

  14. Technical strategy for the management of INEEL spent nuclear fuel

    SciTech Connect (OSTI)

    NONE

    1997-03-01T23:59:59.000Z

    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.

  15. Molten tin reprocessing of spent nuclear fuel elements

    DOE Patents [OSTI]

    Heckman, Richard A. (Castro Valley, CA)

    1983-01-01T23:59:59.000Z

    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.

  16. Habitat selection of the Wood Thrush nesting in east Texas

    E-Print Network [OSTI]

    Carrie, Neil Ross

    1995-01-01T23:59:59.000Z

    HABITAT SELECTION OF THE WOOD THRUSH NESTING IN EAST TEXAS A Thesis by NEIL ROSS CARRIE Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE... December 1995 Major Subject: Wildlife and Fisheries Sciences HABITAT SELECTION OF THE WOOD THRUSH NESTING IN EAST TEXAS A Thesis by NEIL ROSS CARRIE Submitted to Texas A&M University in partial fulfillment of the requirements for the degree...

  17. Kinetic Modeling and Assessment of Lime Pretreatment of Poplar Wood

    E-Print Network [OSTI]

    Sierra Ramirez, Rocio

    2012-02-14T23:59:59.000Z

    biomass is one of the most promising feedstocks for producing biofuels through fermentation processes. Among lignocellulose choices, poplar wood is appealing because of high energy potential, above-average carbon mitigation potential, fast growth... KINETIC MODELING AND ASSESSMENT OF LIME PRETREATMENT OF POPLAR WOOD A Dissertation by ROCIO SIERRA RAMIREZ Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements...

  18. Hanford`s spent nuclear fuel retrieval: an agressive agenda

    SciTech Connect (OSTI)

    Shen, E.J., Westinghouse Hanford

    1996-12-06T23:59:59.000Z

    Starting December 1997, spent nuclear fuel that has been stored in the K Reactor Fuel Storage Basins will be retrieved over a two year period and repackaged for long term dry storage. The aging and sometimes corroding fuel elements will be recovered and processed using log handled tools and teleoperated manipulator technology. The U.S. Department of Energy (DOE) is committed to this urgent schedule because of the environmental threats to the groundwater and nearby the Columbia River.

  19. Spent nuclear fuel project design basis capacity study

    SciTech Connect (OSTI)

    Cleveland, K.J.

    1998-07-22T23:59:59.000Z

    A parametric study of the Spent Nuclear Fuel Project system capacity is presented. The study was completed using a commercially available software package to develop a summary level model of the major project systems. A base case, reflecting the Fiscal Year 1998 process configuration, is evaluated. Parametric evaluations are also considered, investigating the impact of higher fuel retrieval system productivity and reduced shift operations at the canister storage building on total project duration.

  20. Method For Processing Spent (Trn,Zr)N Fuel

    DOE Patents [OSTI]

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

    2004-07-27T23:59:59.000Z

    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.

  1. Spent Nuclear Fuel Project Canister Storage Building Functions and Requirements

    SciTech Connect (OSTI)

    KLEM, M.J.

    2000-10-18T23:59:59.000Z

    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.

  2. Recycling of nuclear spent fuel with AIROX processing

    SciTech Connect (OSTI)

    Majumdar, D. [ed.] [USDOE Idaho Field Office, Idaho Falls, ID (United States); Jahshan, S.N.; Allison, C.M.; Kuan, P. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Thomas, T.R. [Westinghouse Idaho Nuclear Co., Inc., Idaho Falls, ID (United States)

    1992-12-01T23:59:59.000Z

    This report examines the concept of recycling light water reactor (LWR) fuel through use of a dry-processing technique known as the AIROX (Atomics International Reduction Oxidation) process. In this concept, the volatiles and the cladding from spent LWR fuel are separated from the fuel by the AIROX process. The fuel is then reenriched and made into new fuel pins with new cladding. The feasibility of the concept is studied from a technical and high level waste minimization perspective.

  3. Adsorption of phenol from aqueous systems onto spent oil shale

    SciTech Connect (OSTI)

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

    1996-03-01T23:59:59.000Z

    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.

  4. NAC-1 cask dose rate calculations for LWR spent fuel

    SciTech Connect (OSTI)

    CARLSON, A.B.

    1999-02-24T23:59:59.000Z

    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.

  5. Machine Vision Tests for Spent Fuel Scrap Characteristics

    SciTech Connect (OSTI)

    BERGER, W.W.

    2000-04-27T23:59:59.000Z

    The purpose of this work is to perform a feasibility test of a Machine Vision system for potential use at the Hanford K basins during spent nuclear fuel (SNF) operations. This report documents the testing performed to establish functionality of the system including quantitative assessment of results. Fauske and Associates, Inc., which has been intimately involved in development of the SNF safety basis, has teamed with Agris-Schoen Vision Systems, experts in robotics, tele-robotics, and Machine Vision, for this work.

  6. Study on concrete cask storage of spent fuel in Japan

    SciTech Connect (OSTI)

    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

    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.

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

    SciTech Connect (OSTI)

    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

    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.

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

    SciTech Connect (OSTI)

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

    1991-12-01T23:59:59.000Z

    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.

  9. Thermoelectric powered wireless sensors for spent fuel monitoring

    SciTech Connect (OSTI)

    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

    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)

  10. Effects of Burnable Absorbers on PWR Spent Nuclear Fuel

    SciTech Connect (OSTI)

    P.M. O'Leary; Dr. M.L. Pitts

    2000-08-21T23:59:59.000Z

    Burnup credit is an ongoing issue in designing and licensing transportation and storage casks for spent nuclear fuel (SNF). To address this issue, in July 1999, the U.S. Nuclear Regulatory Commission (NRC), Spent Fuel Project Office, issued Interim Staff Guidance-8 (ISG-8), Revision 1 allowing limited burnup credit for pressurized water reactor (PWR) spent nuclear fuel (SNF) to be used in transport and storage casks. However, one of the key limitations for a licensing basis analysis as stipulated in ISG-8, Revision 1 is that ''burnup credit is restricted to intact fuel assemblies that have not used burnable absorbers''. Because many PWR fuel designs have incorporated burnable-absorber rods for more than twenty years, this restriction places an unnecessary burden on the commercial nuclear power industry. This paper summarizes the effects of in-reactor irradiation on the isotopic inventory of PWR fuels containing different types of integral burnable absorbers (BAs). The work presented is illustrative and intended to represent typical magnitudes of the reactivity effects from depleting PWR fuel with different types of burnable absorbers.

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

    SciTech Connect (OSTI)

    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

    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.

  12. An approach to determine a defensible spent fuel ratio.

    SciTech Connect (OSTI)

    Durbin, Samuel G.; Lindgren, Eric Richard

    2014-03-01T23:59:59.000Z

    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.

  13. Feasibility of x ray fluorescence for spent fuel safeguards

    SciTech Connect (OSTI)

    Freeman, Corey Ross [Los Alamos National Laboratory; Mozin, Vladimir [Los Alamos National Laboratory; Tobin, Stephen J [Los Alamos National Laboratory; Fensin, Michael L [Los Alamos National Laboratory; White, Julia M [Los Alamos National Laboratory; Croft, Stephen [Los Alamos National Laboratory; Stafford, Alissa [TAMU; Charlton, William [TAMU

    2010-01-01T23:59:59.000Z

    Quantifying the Pu content in spent nuclear fuel is necessary for many reasons, in particular to verify that diversion or other illicit activities have not occurred. Therefore, safeguarding the world's nuclear fuel is paramount to responsible nuclear regulation and public acceptance, but achieving this goal presents many difficulties from both a technical and economic perspective. The Next Generation Safeguards Initiative (NGSI) of NA-24 is funding a large collaborative effort between multiple laboratories and universities to improve spent nuclear fuel safeguards methods and equipment. This effort involves the current work of modeling several different nondestructive assay (NDA) techniques. Several are being researched, because no single NDA technique, in isolation, has the potential to properly characterize fuel assemblies and offer a robust safeguards measure. The insights gained from this research, will be used to down-select from the original set a few of the most promising techniques that complement each other. The goal is to integrate the selected instruments to create an accurate measurement system for fuel verification that is also robust enough to detect diversions. These instruments will be fabricated and tested under realistic conditions. This work examines one of the NDA techniques; the feasibility of using x ray emission peaks from Pu and U to gather information about their relative quantities in the spent fuel. X Ray Fluorescence (XRF), is unique compared to the investigated techniques in that it is the only one able to give the elemental ratio of Pu to U, allowing the possibility of a Pu gram quantity for the assembly to be calculated. XRF also presents many challenges, mainly its low penetration, since the low energy x rays of interest are effectively shielded by the first few millimeters of a fuel pin. This paper will explore the results of Monte Carlo N-Particle eXtended (MCNPX) transport code calculations of spent fuel x ray peaks. The MCNPX simulations will be benchmarked against measurements taken at Oak Ridge. Analysis of the feasibility of XRFs role in spent nuclear fuel safeguards efforts, particularly in the context of the overall NGSI effort will be discussed.

  14. 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

  15. Moisture Distribution and Flow During Drying of Wood and Fiber

    SciTech Connect (OSTI)

    Zink-Sharp, Audrey; Hanna, Robert B.

    2001-12-28T23:59:59.000Z

    New understanding, theories, and techniques for moisture flow and distribution were developed in this research on wood and wood fiber. Improved understanding of the mechanisms of flake drying has been provided. Observations of flake drying and drying rate curves revealed that rate of moisture loss consisted of two falling rate periods and no constant rate drying period was observed. Convective heat transfer controls the first period, and bound water diffusion controls the second period. Influence of lower drying temperatures on bending properties of wood flakes was investigated. Drying temperature was found to have a significant influence on bending stiffness and strength. A worksheet for calculation of the energy required to dry a single strandboard flake was developed but has not been tested in an industrial setting yet. A more complete understanding of anisotropic transverse shrinkage of wood is proposed based on test results and statistical analysis. A simplified mod el of a wood cell's cross-section was drawn for calculating differential transverse shrinkage. The model utilizes cell wall thickness and microfibrillar packing density and orientation. In spite of some phenomena of cell wall structure not yet understood completely, the results might explain anisotropic transverse shrinkage to a major extent. Boundary layer theory was found useful for evaluating external moisture resistance during drying. Simulated moisture gradients were quire comparable to the actual gradients in dried wood. A mathematical procedure for determining diffusion and surface emission coefficients was also developed. Thermal conductivity models of wood derived from its anatomical structure were created and tested against experimental values. Model estimations provide insights into changes in heat transfer parameters during drying. Two new techniques for measuring moisture gradients created in wood during drying were developed. A new technique that utilizes optical properties of cobalt chloride was developed for nondestructive determination of surface moisture content. Fundamental new understanding of drying characteristics in wood and fiber has been provided that can be used by researchers to improve drying of wood and fiber. The three techniques for measuring moisture content and gradients provided in this study are efficient, practical, and economical - easy to apply by industry and researchers. An energy consumption worksheet is provided as a first step toward reducing energy consumed during drying of lumber and strandboard flakes. However, it will need additional verification and testing.

  16. Decision-maker's guide to wood fuel for small industrial energy users. Final report. [Includes glossary

    SciTech Connect (OSTI)

    Levi, M. P.; O'Grady, M. J.

    1980-02-01T23:59:59.000Z

    The technology and economics of various wood energy systems available to the small industrial and commercial energy user are considered. This book is designed to help a plant manager, engineer, or others in a decision-making role to become more familiar with wood fuel systems and make informed decisions about switching to wood as a fuel. The following subjects are discussed: wood combustion, pelletized wood, fuel storage, fuel handling and preparation, combustion equipment, retrofitting fossil-fueled boilers, cogeneration, pollution abatement, and economic considerations of wood fuel use. (MHR)

  17. Contaminated sediment removal from a spent fuel storage canal

    SciTech Connect (OSTI)

    Geber, K R

    1993-01-01T23:59:59.000Z

    A leaking underground spent fuel transfer canal between a decommissioned reactor and a radiochemical separations building at the Oak Ridge National Laboratory (ORNL) was found to contain RCRA-hazardous and radioactive sediment. Closure of the Part B RCRA permitted facility required the use of an underwater robotic vacuum and a filtration-containment system to separate and stabilize the contaminated sediment. This paper discusses the radiological controls established to maintain contamination and exposures As Low As Reasonably Achievable (ALARA) during the sediment removal.

  18. Method for reprocessing and separating spent nuclear fuels. [Patent application

    DOE Patents [OSTI]

    Krikorian, O.H.; Grens, J.Z.; Parrish, W.H. Sr.

    1982-01-19T23:59:59.000Z

    Spent nuclear fuels, including actinide fuels, volatile and nonvolatile fission products, are reprocessed and separated in a molten metal solvent housed in a separation vessel made of a carbon-containing material. A first catalyst, which promotes the solubility and permeability of carbon in the metal solvent, is included. By increasing the solubility and permeability of the carbon in the solvent, the rate at which actinide oxides are reduced (carbothermic reduction) is greatly increased. A second catalyst, included to increase the affinity for nitrogen in the metal solvent, is added to increase the rate at which actinide nitrides form after carbothermic reduction is complete.

  19. Method for reprocessing and separating spent nuclear fuels

    DOE Patents [OSTI]

    Krikorian, Oscar H. (Danville, CA); Grens, John Z. (Livermore, CA); Parrish, Sr., William H. (Walnut Creek, CA)

    1983-01-01T23:59:59.000Z

    Spent nuclear fuels, including actinide fuels, volatile and non-volatile fission products, are reprocessed and separated in a molten metal solvent housed in a separation vessel made of a carbon-containing material. A first catalyst, which promotes the solubility and permeability of carbon in the metal solvent, is included. By increasing the solubility and permeability of the carbon in the solvent, the rate at which actinide oxides are reduced (carbothermic reduction) is greatly increased. A second catalyst, included to increase the affinity for nitrogen in the metal solvent, is added to increase the rate at which actinide nitrides form after carbothermic reduction is complete.

  20. Corrosion of Spent Nuclear Fuel: The Long-Term Assessment

    SciTech Connect (OSTI)

    Rodney C. Ewing

    2004-10-07T23:59:59.000Z

    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.

  1. Closure mechanism and method for spent nuclear fuel canisters

    DOE Patents [OSTI]

    Doman, Marvin J. (Monroeville, PA)

    2004-11-23T23:59:59.000Z

    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.

  2. Spent nuclear fuel storage -- Performance tests and demonstrations

    SciTech Connect (OSTI)

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

    1993-04-01T23:59:59.000Z

    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.

  3. Extending dry storage of spent LWR fuel for 100 years.

    SciTech Connect (OSTI)

    Einziger, R. E.

    1998-12-16T23:59:59.000Z

    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.

  4. APPLICATIONS OF CURRENT TECHNOLOGY FOR CONTINUOUS MONITORING OF SPENT FUEL

    SciTech Connect (OSTI)

    Drayer, R.

    2013-06-09T23:59:59.000Z

    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.

  5. A novel process for the treatment of spent potlining

    SciTech Connect (OSTI)

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

    1996-12-31T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    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

    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.

  7. Interface agreement for the management of FFTF Spent Nuclear Fuel

    SciTech Connect (OSTI)

    McCormack, R.L.

    1995-02-02T23:59:59.000Z

    The Hanford Site Spent Nuclear Fuel (SNF) Project was formed to manage the SNF at Hanford. The mission of the Fast Flux Test Facility (FFTF) Transition Project is to place the facility in a radiologically and industrially safe shutdown condition for turnover to the Environmental Restoration Contractor (ERC) for subsequent D&D. To satisfy both project missions, FFTF SNF must be removed from the FFTF and subsequently dispositioned. This documented provides the interface agreement between FFTF Transition Project and SNF Project for management of the FFTF SNF.

  8. Smelting Associated with the Advanced Spent Fuel Conditioning Process

    SciTech Connect (OSTI)

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

    2004-10-03T23:59:59.000Z

    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.

  9. Production of metal waste forms from spent fuel treatment

    SciTech Connect (OSTI)

    Westphal, B.R.; Keiser, D.D.; Rigg, R.H.; Laug, D.V.

    1995-02-01T23:59:59.000Z

    Treatment of spent nuclear fuel at Argonne National Laboratory consists of a pyroprocessing scheme in which the development of suitable waste forms is being advanced. Of the two waste forms being proposed, metal and mineral, the production of the metal waste form utilizes induction melting to stabilize the waste product. Alloying of metallic nuclear materials by induction melting has long been an Argonne strength and thus, the transition to metallic waste processing seems compatible. A test program is being initiated to coalesce the production of the metal waste forms with current induction melting capabilities.

  10. Behavior of Spent Nuclear Fuel in Water Pool Storage

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office511041clothAdvanced Materials Advanced Materials Find More Like3.3 PrintVultureBehavior of Spent Nuclear

  11. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645U.S. DOE Office of ScienceandMesa del Sol HomeFacebookScholarship Fund3Biology|SolarSpeakersSpectroscopy|Spent Fuel

  12. 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2Uranium Transfer toSensorSoftware HelpsSouthAgendaSpectrum Policy SeminarSpent

  13. Comminution process to produce precision wood particles of uniform size and shape with disrupted grain structure from wood chips

    DOE Patents [OSTI]

    Dooley, James H; Lanning, David N

    2013-08-13T23:59:59.000Z

    A process of comminution of wood chips (C) having a grain direction to produce a mixture of wood particles (P), wherein the wood chips are characterized by an average length dimension (L.sub.C) as measured substantially parallel to the grain, an average width dimension (W.sub.C) as measured normal to L.sub.C and aligned cross grain, and an average height dimension (H.sub.C) as measured normal to W.sub.C and L.sub.C, and wherein the comminution process comprises the step of feeding the wood chips in a direction of travel substantially randomly to the grain direction through a counter rotating pair of intermeshing arrays of cutting discs (D) arrayed axially perpendicular to the direction of wood chip travel, wherein the cutting discs have a uniform thickness (T.sub.D), and wherein at least one of L.sub.C, W.sub.C, and H.sub.C is greater than T.sub.D.

  14. 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...

  15. Nuclear Resonance Fluorescence to Measure Plutonium Mass in Spent Nuclear Fuel

    E-Print Network [OSTI]

    Ludewigt, Bernhard A

    2011-01-01T23:59:59.000Z

    Spent Fuel Library for Assessing Varied Nondestructive Assay Techniques for Nuclear Safeguards,” LA-UR 09-01188, ANS Advances in Nuclear Fuel Management

  16. EM Prepares Report for Convention on Safety of Spent Fuel and...

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

    agency to produce a report recently for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The Convention was...

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

    Broader source: Energy.gov [DOE]

    DOE prepared a EIS that evaluated the potential environmental impacts of treatment and management of DOE-owned sodium bonded spent nuclear fuel.

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

    SciTech Connect (OSTI)

    Sindelar, R.L.

    1999-10-21T23:59:59.000Z

    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.

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

    E-Print Network [OSTI]

    Fox, J.P.

    2013-01-01T23:59:59.000Z

    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

  20. 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...

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

    SciTech Connect (OSTI)

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

    2001-01-01T23:59:59.000Z

    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.

  2. Properties of concrete containing wood/coal fly ash mixtures

    SciTech Connect (OSTI)

    Boylan, D.M.; Larrimore, C.L.; Fouad, F.

    1999-07-01T23:59:59.000Z

    Utilities are increasingly interested in co-firing wood with coal in existing pulverized coal units. The co-firing technology is a means of developing a relatively low-cost renewable energy resource, as well as of supporting customers and community by making energy with biomass that might otherwise have been land-filled. However, recent changes in the ASTM C618 standard for fly ash as cement replacement restrict the definition of fly ash that includes non-coal sources. As a result, wood co-firing could affect the market for the fly ash, reducing ash sales revenue, increasing ash disposal costs, and overall substantially increasing the cost of the co-firing technology. In order to address concerns about the effect of wood ash/coal ash mixtures on concrete properties, a study was conducted by University of Alabama at Birmingham, Southern Company, EPRI, and the State of Alabama. This study compared the effects on properties of concrete made with fly ash from coal and made with fly ash from co-firing up to 30% wood with coal. Fly ashes from three plants were used, with two of the ashes from actual co-firing experience and the third an artificial blend of wood and coal ash. Concrete test cylinders were made of several cement/fly ash mixes, and enough were made to allow testing periodically over a one year time period. Test measurements included workability, setting time, air content, compressive and flexural strength, rapid chloride permeability and freeze thaw. It was concluded on the basis of these tests that the wood ash content had no detrimental effect on the plastic and hardened properties of the concrete.

  3. Analytical Modeling of Wood Frame Shear Walls Subjected to Vertical Load

    E-Print Network [OSTI]

    Nguyendinh, Hai

    2011-08-08T23:59:59.000Z

    referred to as Analytical Model of wood frame SHEar walls subjected to Vertical load (AMSHEV) is based on the kinematic behavior of wood frame shear walls and captures significant characteristics observed from experimental testing through appropriate...

  4. Metals Concentrations in Soils Below Decks Made of CCA-Treated Wood

    E-Print Network [OSTI]

    Florida, University of

    Metals Concentrations in Soils Below Decks Made of CCA-Treated Wood This report is an excerpt from the report titled: New Lines of CCA-Treated Wood Research, In-Service and Disposal Issues Which was finalized

  5. Simulating the dynamics of flexible wood pulp fibres in suspension John M. Stockie

    E-Print Network [OSTI]

    Stockie, John

    , including wood pulp processing, polymer composites, and formation of fibre-reinforced materials elements to form a surface that re- sists bending and stretching. This is a natural construction for wood

  6. CONTROLLING THE INTERNATIONAL TRADE IN ILLEGALLY LOGGED TIMBER AND WOOD PRODUCTS

    E-Print Network [OSTI]

    CONTROLLING THE INTERNATIONAL TRADE IN ILLEGALLY LOGGED TIMBER AND WOOD PRODUCTS A study prepared@riia.org February 2002 #12;Controlling the international trade in illegally logged timber and wood products Page 2...................................................................................................................... 11 ILLEGAL ACTIVITIES IN THE FOREST SECTOR

  7. Spent nuclear fuel recycling with plasma reduction and etching

    DOE Patents [OSTI]

    Kim, Yong Ho

    2012-06-05T23:59:59.000Z

    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.

  8. Dry oxidation and fracture of LWR spent fuels

    SciTech Connect (OSTI)

    Ahn, T.M.

    1996-11-01T23:59:59.000Z

    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.

  9. Natural convection heat transfer within horizontal spent nuclear fuel assemblies

    SciTech Connect (OSTI)

    Canaan, R.E.

    1995-12-01T23:59:59.000Z

    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.

  10. Delayed Gamma-Ray Spectroscopy for Spent Nuclear Fuel Assay

    SciTech Connect (OSTI)

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

    2012-04-01T23:59:59.000Z

    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.

  11. Wood residuals find big uses in small pieces

    SciTech Connect (OSTI)

    Glenn, J.

    1996-12-01T23:59:59.000Z

    With a history of finding economic uses for leftovers, the wood industry explores sustainable options for creating higher value products. Years ago, companies saw the use - any use - of residues as a sound, economic business practice. Today, many companies are looking to go beyond low value products such as mulch, animal bedding and fuel, and market to higher value end users. Additionally, with so much material from the primary industries already accounted for, consumers of wood residue are in need of additional supply from sources such as secondary mills (furniture manufacturers, etc.), as wells as the C&D and MSW streams. This paper discusses these products and markets.

  12. Rational production of veneer by IR-heating of green wood during peeling: Modeling experiments

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    (0)3 85 59 53 85 E-mail: anna.dupleix@ensam.eu Abstract Heating green wood logs by infrared (IR-line IR heating system installed on the peeling lathe. Keywords: green wood; heating; infrared; modelingRational production of veneer by IR-heating of green wood during peeling: Modeling experiments Anna

  13. SECTION 50 Table of Contents 50 Lake Rufus Woods Management Plan .........................................................2

    E-Print Network [OSTI]

    and formation of the Subbasin Work Teams and the process used to develop and adopt the management plan can50-1 SECTION 50 ­ Table of Contents 50 Lake Rufus Woods Management Plan .........................................................................28 #12;50-2 50 Lake Rufus Woods Management Plan The Lake Rufus Woods Subbasin Management Plan

  14. European Institute for Wood Preservation Congress 4-6 September 2008, Lausanne, Switzerland

    E-Print Network [OSTI]

    developments A. Wood raw materials (roundwood) B. Sawn softwood C. Wood energy V. Conclusions VI" · In 2007, US housing construction continued its sharp decline, severely impacting world markets. · Green building systems are a market driver, but also a constraint. · UNECE region consumption of wood and paper

  15. EFFECTS OF SAMPLE SIZE ON CHARACTERIZATION OF WOOD-PARTICLE LENGTH DISTRIBUTION

    E-Print Network [OSTI]

    EFFECTS OF SAMPLE SIZE ON CHARACTERIZATION OF WOOD-PARTICLE LENGTH DISTRIBUTION Quang V. Cao of sample size on fitting length distribution of wood particles used for manufacturing wood-based composites moments and the ability of the sample distributions to characterize the population represented

  16. Presentation 2.6: Wood waste for energy: lessons learnt from tropical regions Paul Vantomme

    E-Print Network [OSTI]

    Presentation 2.6: Wood waste for energy: lessons learnt from tropical regions Paul Vantomme of forest products with more value adding, and promoting the use of wood waste to increase energy efficiency to promote the use of wood waste for energy production. Not only the financial viability of the process needs

  17. Matrix penetration in the bulk:In uence of humidity: Morphological analysis of wood welding

    E-Print Network [OSTI]

    Dalang, Robert C.

    Matrix penetration in the bulk:In uence of humidity: Morphological analysis of wood welding.pichelin@b .ch Context: Wood can be welded using linear vibration welding tech- niques similar to the ones in plastic and metal industry[1] . Wood welding allows bonding strength similar to glued joints. However, due

  18. Streamlined LCA of Wood Pellets: Export and Possible Utilization in UBC

    E-Print Network [OSTI]

    Streamlined LCA of Wood Pellets: Export and Possible Utilization in UBC Boiler House CHBE 573 Ann Pa May 15, 2009 #12;2 | P a g e INTRODUCTION Wood pellets are a type of biofuels and are often made. Like all biofuels, wood pellets are carbon- neutral and renewable and are very popular in Europe

  19. Net carbon fluxes at stand and landscape scales from wood bioenergy harvests in the US Northeast

    E-Print Network [OSTI]

    Vermont, University of

    gas emissions implications of wood biomass (`bioenergy') harvests are highly uncer- tain yet of great') on long-term green- house gas emissions are uncertain (McKechnie et al., 2011), yet demand for wood (C) emitted from wood bioenergy may eventually be re-sequestered through regeneration and increased

  20. Management of Discarded Treated Wood Products: A Resource Guide for Generators

    E-Print Network [OSTI]

    Florida, University of

    Management of Discarded Treated Wood Products: A Resource Guide for Generators Prepared by have been conducting research on treated wood since 1996. During the course of the research, there have been numerous inquiries about the disposal and management options for treated wood products. There has

  1. Alternative Chemicals and Improved Disposal-End Management Practices for CCA-treated Wood

    E-Print Network [OSTI]

    Florida, University of

    Alternative Chemicals and Improved Disposal-End Management Practices for CCA-treated Wood (FINAL Importation Associated with CCA-Treated Wood Use APPENDIX B: MSDS Sheets for Alternative Chemicals APPENDIX C Members A-1 B-1 C-1 D-1 E-1 F-1 G-1 ATTACHMENT: Treated Wood Resource Book #12;ii This page left

  2. Preservative leaching from weathered CCA-treated wood Timothy Townsenda,*, Brajesh Dubeya

    E-Print Network [OSTI]

    Florida, University of

    Preservative leaching from weathered CCA-treated wood Timothy Townsenda,*, Brajesh Dubeya , Thabet copper arsenate (CCA)-treated wood in landfills raises concerns with respect to leaching of preservative compounds. When unweathered CCA-treated wood is leached using the toxicity characteristic leaching procedure

  3. Implications for the Future of Treated Wood in Four U.S. Demand Sectors

    E-Print Network [OSTI]

    Implications for the Future of Treated Wood in Four U.S. Demand Sectors Todd F. Shupe Associate extends the life span of lumber, but the Environmental Protection Agency says arsenic treated wood might arsenic-treated wood from Florida's public playgrounds failed to pass. "Wave of opponents kills Crow

  4. Attitudes and Awareness about Treated Wood Products: The U.S. South Homeowner Perspective

    E-Print Network [OSTI]

    Wu, Qinglin

    Attitudes and Awareness about Treated Wood Products: The U.S. South Homeowner Perspective is preservative-treated (SFPA 2004). In light of increasing market penetration from non-wood alternatives homeowner attitudes and awareness about using treated wood Strategic decisions can be made to better

  5. U.S. Playground Equipment Manufacturer and Purchaser Perceptions of Treated Wood

    E-Print Network [OSTI]

    U.S. Playground Equipment Manufacturer and Purchaser Perceptions of Treated Wood Todd F. Shupe treated wood might cut life short for our children. "EPA chops down potential killer", 24 Hour News 8, Florida, after his bill to ban arsenic-treated wood from Florida's public playgrounds failed to pass

  6. Quantities of Arsenic-Treated Wood in Demolition Debris Generated by

    E-Print Network [OSTI]

    Florida, University of

    Research Quantities of Arsenic-Treated Wood in Demolition Debris Generated by Hurricane Katrina B R of the demolition debris is wood waste of which a significant proportion is treated with preservatives, including preservatives containing arsenic. As a result of the large scale destruction of treated wood structures

  7. Mechanical characteristics of aged Hinoki (Chamaecyparis obtusa Endl.) wood from Japanese historical buildings

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    historical buildings -Comparative analyses with accelerated aging wood- Misao YOKOYAMA*1 , Joseph GRIL*1 Abstract Wood is present in many cultural heritage objects thanks to its capacity to resist odvantage with mechanical characteristics of aged hinoki (Chamaecyparis obtusa Endl.) wood of Japanese historical buildings

  8. Society of Wood Science and Technology Convention 10-12 November 2008, Concepcin, Chile

    E-Print Network [OSTI]

    Society of Wood Science and Technology Convention 10-12 November 2008, Concepción, Chile Global #12;Society of Wood Science and Technology Convention 10-12 November 2008, Concepción, Chile Subjects;Society of Wood Science and Technology Convention 10-12 November 2008, Concepción, Chile Main sources

  9. Name: Qinglin Wu Title: Roy O Martin Sr. Professor, Composites and Engineered Wood Products

    E-Print Network [OSTI]

    (ASTM), Philadelphia, PA · Forest Products Society, Madison, WI · Society of Wood and Science Technology Organizations · International Research Group in Wood Preservation, Stockholm, Sweden · American Chemical Society (ACS) · American Wood Preservation Association (AWPA) · American Society for Testing and Materials

  10. Final Independent External Peer Review Report Melvin Price Wood River Underseepage

    E-Print Network [OSTI]

    US Army Corps of Engineers

    EXECUTIVE SUMMARY Project Background and Purpose The purpose of the Melvin Price Wood River Underseepage Price Wood River LRR and the overall scope of the project, the final panel members were selectedFinal Independent External Peer Review Report Melvin Price Wood River Underseepage Limited

  11. APPLICATION OF NELSON'S SORPTION ISOTHERM TO WOOD COMPOSITES AND OVERLAYS'

    E-Print Network [OSTI]

    APPLICATION OF NELSON'S SORPTION ISOTHERM TO WOOD COMPOSITES AND OVERLAYS' Qinglin Wu Assistant. It was found that Nelson's model can be used to describe the experimental data from different composite composite materials (Suchsland 1972). These relationships, known as sorption isotherms, greatly affect

  12. Influence of Nanoclay on Properties of HDPE/Wood Composites

    E-Print Network [OSTI]

    Influence of Nanoclay on Properties of HDPE/Wood Composites Yong Lei,1 Qinglin Wu,1 Craig M Agricultural Center, Baton Rouge, Louisiana 70803 2 Performance Engineered Composites, USDA Forest ServiceScience (www.interscience.wiley.com). ABSTRACT: Composites based on high density polyeth- ylene (HDPE), pine

  13. Bryan H. Wood Assistant Deputy Commandant of the Marine Corps

    E-Print Network [OSTI]

    and stations throughout the world and for the operating forces across the U.S. Marine Corps. Mr. Wood advisor to the Commander, Combined Joint Task Force- Horn of Africa (CJTF-HOA) in Djibouti, Africa. Mr as the Environmental Law Section Head and Senior Associate Counsel (Environment/ Safety), Naval Sea Systems Command

  14. AN EXAMINATION OF WOOD RECYCLING PROVISIONS IN NORTH AMERICAN GREEN

    E-Print Network [OSTI]

    American green building standards, with use of such materials awarded or specified. Construction-consumer materials shall be considered as recycled. In addition to reviewing provisions of various green building! ! ! AN EXAMINATION OF WOOD RECYCLING PROVISIONS IN NORTH AMERICAN GREEN BUILDING PROGRAMS DR. JIM

  15. Physiological Insights Towards Improving Fish Culture L. CURRY WOODS III*

    E-Print Network [OSTI]

    Hamza, Iqbal

    Physiological Insights Towards Improving Fish Culture L. CURRY WOODS III* Department of Animal, and American Fisheries Society (AFS) Fish Culture Section, was held February 26 through March 2, 2007, in San Antonio, Texas. At this meeting, the AFS Fish Culture and Fish Physiol- ogy Sections co

  16. Wood Residues as Fuel Source for Lime Kilns

    E-Print Network [OSTI]

    Azarniouch, M. K.; Philp, R. J.

    1984-01-01T23:59:59.000Z

    One of the main obstacles to total energy self sufficiency of kraft mills appears to be the fossil fuel requirements of the lime kilns. If an economical technology can be developed which allows fossil fuel to be replaced in whole or in part by wood...

  17. Measuring Interfacial Stiffness of Adhesively-Bonded Wood

    E-Print Network [OSTI]

    Nairn, John A.

    , the interfaces will fail, the elements will cease to share load, and the composite will have poor properties property. Nearly all methods for characterizing wood adhesive bonds consider only strength of the bonds. Typically a bond line is loaded until failure and the final load at failure is recorded. Some common

  18. Marketing of Tropical Hardwood Wood Products from Ghana

    E-Print Network [OSTI]

    productive · Causes: farming, bush fires, fuel wood, wasteful logging practices, mining and quarrying #12;Fuelwood #12;Current Industry Structure · 8% of GDP · 250 companies involved in primary operations · 180 companies in secondary operations · Over 200 companies involved in tertiary operations · General

  19. 14 November 2010 Wood SA & Timber Times FOREST HEALTH

    E-Print Network [OSTI]

    14 November 2010 Wood SA & Timber Times FOREST HEALTH Aprogramme that begun based on a very small other disciplines within reach of a dynamic forestry industry. Three South African forestry companies was formally launched in 1990.The research directors of these companies Neville Denison (Mondi),Mike Shaw

  20. Pellet Production Wood Pellets are made by compressing

    E-Print Network [OSTI]

    Pellet Production Wood Pellets are made by compressing clean dry sawdust, under very high pressure into a pellet as it cools. The material used for producing pellets usually comes from industries who are already pellets reduces the volume of material they have to treat as waste, reducing landfill. Pellets have

  1. Vertical feed stick wood fuel burning furnace system

    DOE Patents [OSTI]

    Hill, Richard C. (Orono, ME)

    1982-01-01T23:59:59.000Z

    A stove or furnace for efficient combustion of wood fuel includes a vertical feed combustion chamber (15) for receiving and supporting wood fuel in a vertical attitude or stack. A major upper portion of the combustion chamber column comprises a water jacket (14) for coupling to a source of water or heat transfer fluid for convection circulation of the fluid. The locus (31) of wood fuel combustion is thereby confined to the refractory base of the combustion chamber. A flue gas propagation delay channel (34) extending laterally from the base of the chamber affords delayed travel time in a high temperature refractory environment sufficient to assure substantially complete combustion of the gaseous products of wood burning with forced air prior to extraction of heat in heat exchanger (16). Induced draft draws the fuel gas and air mixture laterally through the combustion chamber and refractory high temperature zone to the heat exchanger and flue. Also included are active sources of forced air and induced draft, multiple circuit couplings for the recovered heat, and construction features in the refractory material substructure and metal component superstructure.

  2. Performance of Wood-Frame Structures during Hurricane Katrina

    E-Print Network [OSTI]

    Cox, Dan

    Performance of Wood-Frame Structures during Hurricane Katrina John W. van de Lindt, M.ASCE1 ; Andrew Graettinger, M.ASCE2 ; Rakesh Gupta, M.ASCE3 ; Thomas Skaggs, M.ASCE4 ; Steven Pryor, M.ASCE5 ; and Kenneth J. Fridley, M.ASCE6 Abstract: The costliest natural disaster in U.S. history was Hurricane Katrina

  3. Practical Approach to Designing Wood Roof Truss Assemblies

    E-Print Network [OSTI]

    Gupta, Rakesh

    Practical Approach to Designing Wood Roof Truss Assemblies Rakesh Gupta, M.ASCE1 ; and Pranueng to evaluate "system effects" in light-frame roof truss assemblies. The goal of this study was to develop an improved and practical design method for 3D roof truss assemblies used in residential construction. A truss

  4. U.S. Homeowner of Perceptions of Treated Wood

    E-Print Network [OSTI]

    U.S. Homeowner of Perceptions of Treated Wood Todd F. Shupe Extension Specialist Forest Products% Naturally durable species (cedar, redwood) 19% 56% 25% Treated lumber products 18% 67% 15% Untreated lumber Stating Agree or Strongly Agree Plastic 3.6 55% Steel 3.4 48% Treated Lumber 3.3 38% Concrete 2.8 24

  5. Wood-Coal Fired "Small" Boiler Case Study

    E-Print Network [OSTI]

    Pincelli, R. D.

    1980-01-01T23:59:59.000Z

    Galaxy Carpet Corporation installed a coal and wood waste fired boiler approximately twelve months ago. Its first year net savings were $195,000.00 Total capital investment was paid off in 1.9 years. 20% investment tax credits were granted...

  6. HISTORICAL WOOD COLLECTION AT THE DENDROCHRONOLOGY LABORATORY, VYTAUTAS MAGNUS

    E-Print Network [OSTI]

    investigations. Subfossil oaks from river gravels, pines from peat bogs and wood from archeological excavations.) samples were collected in two peat bogs with pine trunks embedded in oligotrophic peat layers. One more than 300 samples of pine stumps and stems preserved in oligotrophic peat layers were coll

  7. Production of chemical feedstock by the methanolysis of wood

    DOE Patents [OSTI]

    Steinberg, M.; Fallon, P.

    1983-06-01T23:59:59.000Z

    A process is discussed for the production of ethylene, benzene and carbon monoxide from particulated biomass such as wood by reaction with methane at a temperature of from 700/sup 0/C to 1200/sup 0/C, at a pressure of from 20 psi to 100 psi for a period of from 0.2 to 10 seconds.

  8. In-Depth Temperature Profiles in Pyrolyzing Wood 

    E-Print Network [OSTI]

    Reszka, Pedro

    of experimental in-depth temperature measurements were done in wood samples exposed to various intensities of radiant heat fluxes, with clearly defined boundary conditions that allow a proper input for pyrolysis models. The imposed heat fluxes range from 10 k...

  9. Production of chemical feedstock by the methanolysis of wood

    DOE Patents [OSTI]

    Steinberg, Meyer (Melville, NY); Fallon, Peter (East Moriches, NY)

    1984-07-31T23:59:59.000Z

    A process for the production of ethylene, benzene and carbon monoxide from particulated biomass such as wood by reaction with methane at a temperature of from 700.degree. C. to 1200.degree. C., at a pressure of from 20 psi to 100 psi for a period of from 0.2 to 10 seconds.

  10. INFLUENCE OF TORREFACTION TREATMENT ON WOOD POWDER PROPERTIES M. Almendrosa

    E-Print Network [OSTI]

    Boyer, Edmond

    INFLUENCE OF TORREFACTION TREATMENT ON WOOD POWDER PROPERTIES M. Almendrosa , O. Bonnefoyb , A de Saint-Etienne (EMSE), 158, Cours Fauriel, F-42023 Saint-Etienne, France ABSTRACT: Torrefaction and makes the grinding easier. Our project deals with the study of the effects of the combined torrefaction

  11. The Wood-Based Biorefinery in a Petroleum Depleted World

    E-Print Network [OSTI]

    Chatterjee, Avik P.

    3 Year Old Willow #12;14 14 Woody Biomass Feedstocks Sustainably harvested low value wood from, Sustainable Bioproducts: Fuels, Chemicals, Materials Renewable Resources to "Green" Bio-Products Woody Biomass Feedstock #12;5 5 Spindletop at Beaumont, TX Circa late 1890's Birth of the Petroleum Industry in Texas

  12. Page 2 of 4 TREE Cookies Etc. Got Woods -continued

    E-Print Network [OSTI]

    Liskiewicz, Maciej

    of a forester is to help sell timber, though they can and should be used to write management plans, manage tree plantings, implement intermediate tending treatments to improve the woods, design soil stabilization the tree, the rays (the lateral transporting structures for water and nutrients) are blocked. Finally

  13. Spent fuel dry storage technology development: fuel temperature measurements under imposed dry storage conditions (I kW PWR spent fuel assembly)

    SciTech Connect (OSTI)

    Unterzuber, R.; Wright, J.B.

    1980-09-01T23:59:59.000Z

    A spent fuel assembly temperature test under imposed dry storage conditions was conducted at the Engine Maintenance Assembly and Disassembly (E-MAD) facility on the Nevada Test Site in support of spent fuel dry storage technology development. This document presents the test data and results obtained from an approximately 1.0 kW decay heat level PWR spent fuel assembly. A spent fuel test apparatus was designed to utilize a representative stainless steel spent fuel canister, a canister lid containing internal temperature instrumentation to measure fuel cladding temperatures, and a carbon steel liner that encloses the canister and lid. Electrical heaters along the liner length, on the lid, and below the canister are used to impose dry storage canister temperature profiles. Temperature instrumentation is provided on the liner and canister. The liner and canister are supported by a test stand in one of the large hot cells (West Process Cell) inside E-MAD. Fuel temperature measurements have been performed using imposed canister temperature profiles from the electrically heated and spent fuel drywell tests being conducted at E-MAD as well as for four constant canister temperature profiles, each with a vacuum, helium and air backfill. Computer models have been utilized in conjunction with the test to predict the thermal response of the fuel cladding. Computer predictions are presented, and they show good agreement with the test data.

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

    SciTech Connect (OSTI)

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

    1993-01-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    1981-09-01T23:59:59.000Z

    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.

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

    E-Print Network [OSTI]

    DuPont, John N.

    composition for any Gd level. Keywords gadolinium, neutron absorbing material, nuclear criticality safety support, (2) spent nuclear fuel geometry control, and (3) nuclear criticality safety. In additionDevelopment of Gd-Enriched Alloys for Spent Nuclear Fuel Applications--Part 1: Preliminary

  17. Spent Nuclear Fuel Self-Induced XRF to Predict Pu to U Content 

    E-Print Network [OSTI]

    Stafford, Alissa Sarah

    2010-10-12T23:59:59.000Z

    The quantification of plutonium (Pu) in spent nuclear fuel is an increasingly important safeguards issue. There exists an estimated worldwide 980 metric tons of Pu in the nuclear fuel cycle and the majority is in spent nuclear fuel waiting for long...

  18. Utilizing Divers in Support of Spent Fuel Basin Closure Subproject

    SciTech Connect (OSTI)

    Allen Nellesen

    2005-01-01T23:59:59.000Z

    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. ICP’s 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.

  19. Assessment of Nuclear Resonance Fluorescence for Spent Nuclear Fuel Assay

    SciTech Connect (OSTI)

    Quiter, Brian; Ludewigt, Bernhard; Ambers, Scott

    2011-06-30T23:59:59.000Z

    In nuclear resonance fluorescence (NRF) measurements, resonances are excited by an external photon beam leading to the emission of gamma rays with specific energies that are characteristic of the emitting isotope. NRF promises the unique capability of directly quantifying a specific isotope without the need for unfolding the combined responses of several fissile isotopes as is required in other measurement techniques. We have analyzed the potential of NRF as a non-destructive analysis technique for quantitative measurements of Pu isotopes in spent nuclear fuel (SNF). Given the low concentrations of 239Pu in SNF and its small integrated NRF cross sections, the main challenge in achieving precise and accurate measurements lies in accruing sufficient counting statistics in a reasonable measurement time. Using analytical modeling, and simulations with the radiation transport code MCNPX that has been experimentally tested recently, the backscatter and transmission methods were quantitatively studied for differing photon sources and radiation detector types. Resonant photon count rates and measurement times were estimated for a range of photon source and detection parameters, which were used to determine photon source and gamma-ray detector requirements. The results indicate that systems based on a bremsstrahlung source and present detector technology are not practical for high-precision measurements of 239Pu in SNF. Measurements that achieve the desired uncertainties within hour-long measurements will either require stronger resonances, which may be expressed by other Pu isotopes, or require quasi-monoenergetic photon sources with intensities that are approximately two orders of magnitude higher than those currently being designed or proposed.This work is part of a larger effort sponsored by the Next Generation Safeguards Initiative to develop an integrated instrument, comprised of individual NDA techniques with complementary features, that is fully capable of determining Pu mass in spent fuel assemblies.

  20. Managing Spent Nuclear Fuel at the Idaho National Laboratory

    SciTech Connect (OSTI)

    Thomas Hill; Denzel L. Fillmore

    2005-10-01T23:59:59.000Z

    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 forms—from 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.

  1. Fort Calhoun Station disposal of spent fuel pool racks

    SciTech Connect (OSTI)

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

    1995-09-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

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

    2004-12-27T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    N /A

    1998-12-24T23:59:59.000Z

    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).

  4. A Technical Review of Non-Destructive Assay Research for the Characterization of Spent Nuclear Fuel Assemblies Being Conducted Under the US DOE NGSI - 11544

    E-Print Network [OSTI]

    Croft, S.

    2012-01-01T23:59:59.000Z

    for Safeguards of LEU and MOX Spent Fuel,” Internationalfuel rods (including some MOX fuel) followed by confirmatoryfresh and 1-cycle spent MOX fuel from 3- and 4-cycles spent

  5. Determining Plutonium Mass in Spent Fuel with Nondestructive Assay Techniques NGSI Research Overview and Update on NDA Techniques

    E-Print Network [OSTI]

    A., V. Mozin, S.J. Tobin, L.W. Cambell, J.R. Cheatham, C.R. Freeman, C.J. Gesh,

    2012-01-01T23:59:59.000Z

    considered one of the 17x17 PWR assemblies from the NGSIplutonium signal because in a PWR spent fuel its content isspectra for a single PWR fuel pin with fresh and spent UO 2

  6. Woodfuel Usage Update 1 I Wood fuel use in Scotland 2012 I Hudson Consulting I November 2012

    E-Print Network [OSTI]

    furnish of 150k odt/yr in 2012. 9. Including wood going for the production of pellets, usage of wood in progress 3.3. Wood fuel usage by fuel category 3.4. Pellet plants 3.5. Greenhouse gas emissions 4 to 1.073 million odt in 2014. 8. Four wood pellet manufacturing plants in Scotland used in total some

  7. U.S. Home Builder Perceptions about Treated Wood:Summary Richard P. Vlosky, Ph.D.1

    E-Print Network [OSTI]

    U.S. Home Builder Perceptions about Treated Wood:Summary Richard P. Vlosky, Ph.D.1 Professor for wood. In areas subject to a high risk of decay, wood that is preservative treated is often recommended alternatives to treated wood in certain applications, but this may result in higher costs, higher energy

  8. Determining Plutonium Mass in Spent Fuel with Nondestructive Assay Techniques -- Preliminary Modeling Results Emphasizing Integration among Techniques

    E-Print Network [OSTI]

    Tobin, S. J.

    2010-01-01T23:59:59.000Z

    Spent Nuclear Fuel by Self-Induced X- ray,” Annual Meeting of the Institute of Nuclear Material Management,

  9. Determining Plutonium Mass in Spent Fuel with Nondestructive Assay Techniques NGSI Research Overview and Update on NDA Techniques

    E-Print Network [OSTI]

    A., V. Mozin, S.J. Tobin, L.W. Cambell, J.R. Cheatham, C.R. Freeman, C.J. Gesh,

    2012-01-01T23:59:59.000Z

    Spent Fuel Library for Assessing Varied Nondestructive Assay Techniques for Nuclear Safeguards,” Advances in Nuclear Fuel Management

  10. Determining Plutonium Mass in Spent Fuel with Nondestructive Assay Techniques -- Preliminary Modeling Results Emphasizing Integration among Techniques

    E-Print Network [OSTI]

    Tobin, S. J.

    2010-01-01T23:59:59.000Z

    for safeguards of LEU and MOX spent fuel,” Internationalsystems in use today (Safeguards Mox Python Detector, 1 Fork

  11. URBAN WOOD/COAL CO-FIRING IN THE NIOSH BOILER PLANT

    SciTech Connect (OSTI)

    James T. Cobb Jr.

    2005-02-10T23:59:59.000Z

    Phase I of this project began by obtaining R&D variances for permits at the NIOSH boilerplant (NBP), Emery Tree Service (ETS) and the J. A. Rutter Company (JARC) for their portions of the project. Wood for the test burn was obtained from the JARC inventory (pallets), Thompson Properties and Seven D Corporation (construction wood), and the Arlington Heights Housing Project (demolition wood). The wood was ground at ETS and JARC, delivered to the Three Rivers Terminal and blended with coal. Three one-day tests using wood/coal blends of 33% wood by volume (both construction wood and demolition wood) were conducted at the NBP. Blends using hammermilled wood were operationally successful. Emissions of SO{sub 2} and NOx decreased and that of CO increased when compared with combusting coal alone. Mercury emissions were measured and evaluated. During the first year of Phase II the principal work focused upon searching for a replacement boilerplant and developing a commercial supply of demolition wood. The NBP withdrew from the project and a search began for another stoker boilerplant in Pennsylvania to replace it on the project. Three potential commercial demolition wood providers were contacted. Two were not be able to supply wood. At the end of the first year of Phase II, discussions were continuing with the third one, a commercial demolition wood provider from northern New Jersey. During the two-and-a-third years of the contract extension it was determined that the demolition wood from northern New Jersey was impractical for use in Pittsburgh, in another power plant in central New Jersey, and in a new wood gasifier being planned in Philadelphia. However, the project team did identify sufficient wood from other sources for the gasifier project. The Principal Investigator of this project assisted a feasibility study of wood gasification in Clarion County, Pennsylvania. As a result of the study, an independent power producer in the county has initiated a small wood gasification project at its site. Throughout much of this total project the Principal Investigator has counseled two small businesses in developing a waxed cardboard pellet business. A recent test burn of this biofuel appears successful and a purchase contract is anticipated soon. During the past two months a major tree-trimming firm has shown an active interest in entering the wood-chip fuel market in the Pittsburgh area and has contacted the NBP, among others, as potential customers. The NBP superintendent is currently in discussion with the facilities management of the Bruceton Research Center about resuming their interest in cofiring this renewable fuel to the stoker there.

  12. Cost, time, and benefit measures for personal use fuel-wood collection in Colorado. Forest Service research paper

    SciTech Connect (OSTI)

    Betters, D.R.; Markstrom, D.C.; Aukerman, R.

    1990-01-01T23:59:59.000Z

    The average fuel-wood collector is willing to pay, beyond current perceived costs, an additional $21 to $29 per cord in order to continue collecting fuel-wood. The difference between willingness-to-pay estimates for fuel-wood collection and for wood purchased from a commercial vendor is assumed to present recreational value of fuel-wood collection. On that basis, the recreation values for the average collection is estimated to be between $6 and $12 per cord.

  13. Fast Reactor Spent Fuel Processing: Experience and Criticality Safety

    SciTech Connect (OSTI)

    Chad Pope

    2007-05-01T23:59:59.000Z

    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

  14. Dry Storage of Research Reactor Spent Nuclear Fuel - 13321

    SciTech Connect (OSTI)

    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

    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)

  15. Qualitative human reliability analysis for spent fuel handling

    SciTech Connect (OSTI)

    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

    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)

  16. 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)

    Not Available

    1994-06-01T23:59:59.000Z

    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.

  17. Shipper/receiver difference verification of spent fuel by use of PDET

    SciTech Connect (OSTI)

    Ham, Y. S.; Sitaraman, S. [Global Security Directorate, Lawrence Livermore National Laboratory, Livermore, CA 94550 (United States)

    2011-07-01T23:59:59.000Z

    Spent fuel storage pools in most countries are rapidly approaching their design limits with the discharge of over 10,000 metric tons of heavy metal from global reactors. Countries like UK, France or Japan have adopted a closed fuel cycle by reprocessing spent fuel and recycling MOX fuel while many other countries opted for above ground interim dry storage for their spent fuel management strategy. Some countries like Finland and Sweden are already well on the way to setting up a conditioning plant and a deep geological repository for spent fuel. For all these situations, shipments of spent fuel are needed and the number of these shipments is expected to increase significantly. Although shipper/receiver difference (SRD) verification measurements are needed by IAEA when the recipient facility receives spent fuel, these are not being practiced to the level that IAEA has desired due to lack of a credible measurement methodology and instrument that can reliably perform these measurements to verify non-diversion of spent fuel during shipment and confirm facility operator declarations on the spent fuel. In this paper, we describe a new safeguards method and an associated instrument, Partial Defect Tester (PDET), which can detect pin diversion from Pressurized Water Reactor (PWR) Spent Fuel Assemblies in an in-situ condition. The PDET uses multiple tiny neutron and gamma detectors in the form of a cluster and a simple, yet highly precise, gravity-driven system to obtain underwater radiation measurements inside a Pressurized Water Reactor (PWR) spent fuel assembly. The method takes advantage of the PWR fuel design which contains multiple guide tubes which can be accessed from the top. The data obtained in such a manner can provide spatial distribution of neutron and gamma flux within a spent fuel assembly. Our simulation study as well as validation measurements indicated that the ratio of the gamma signal to the thermal neutron signal at each detector location normalized to the peak ratio of all the detector locations gives a unique signature that is sensitive to missing pins. The signature is principally dependent on the geometry of the detector locations, and little sensitive to enrichment or burn-up variations. A small variation in the fuel bundle, such as a few missing pins, changes the shape of the signature to enable detection. After verification of the non-diversion of spent fuel pins, the neutron signal and gamma signal are subsequently used to verify the consistency of the operator declaration on the fuel burn-up and cooling time. (authors)

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

    SciTech Connect (OSTI)

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

    1982-09-01T23:59:59.000Z

    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).

  19. QUALITY OF WOOD PELLETS PRODUCED IN BRITISH COLUMBIA FOR EXPORT

    SciTech Connect (OSTI)

    Tumuluru, J.S. [Idaho National Laboratory (INL); Sokhansanj, Shahabaddine [ORNL; Lim, C. Jim [University of British Columbia, Vancouver; Bi, X.T. [University of British Columbia, Vancouver; Lau, A.K. [University of British Columbia, Vancouver; Melin, Staffan [University of British Columbia, Vancouver; Oveisi, E. [University of British Columbia, Vancouver; Sowlati, T. [University of British Columbia, Vancouver

    2010-11-01T23:59:59.000Z

    Wood pellet production and its use for heat and power production are increasing worldwide. The quality of export pellets has to consistently meet certain specifications as stipulated by the larger buyers, such as power utilities or as specified by the standards used for the non-industrial bag market. No specific data is available regarding the quality of export pellets to Europe. To develop a set of baseline data, wood pellets were sampled at an export terminal in Vancouver, British Columbia, Canada. The sampling period was 18 months in 2007-2008 when pellets were transferred from storage bins to the ocean vessels. The sampling frequency was once every 1.5 to 2 months for a total of 9 loading/shipping events. The physical properties of the wood pellets measured were moisture content in the range of 3.5% to 6.5%, bulk density from 728 to 808 kg/m3, durability from 97% to 99%, fines content from 0.03% to 0.87%, calorific value as is from 17 to almost 18 MJ/kg, and ash content from 0.26% to 0.93%.The diameter and length were in the range of 6.4 to 6.5 mm and 14.0 to 19.0 mm, respectively. All of these values met the published non-industrial European grades (CEN) and the grades specified by the Pellet Fuel Institute for the United States for the bag market. The measured values for wood pellet properties were consistent except the ash content values decreased over the test period.

  20. Quality of Wood Pellets Produced in British Columbia for Export

    SciTech Connect (OSTI)

    J. S. Tumuluru; S. Sokhansanj; C. J. Lim; T. Bi; A. Lau; S. Melin; T. Sowlati; E. Oveisi

    2010-11-01T23:59:59.000Z

    Wood pellet production and its use for heat and power production are increasing worldwide. The quality of export pellets has to consistently meet certain specifications as stipulated by the larger buyers, such as power utilities or as specified by the standards used for the non-industrial bag market. No specific data is available regarding the quality of export pellets to Europe. To develop a set of baseline data, wood pellets were sampled at an export terminal in Vancouver, British Columbia, Canada. The sampling period was 18 months in 2007-2008 when pellets were transferred from storage bins to the ocean vessels. The sampling frequency was once every 1.5 to 2 months for a total of 9 loading/shipping events. The physical properties of the wood pellets measured were moisture content in the range of 3.5% to 6.5%, bulk density from 728 to 808 kg/m3, durability from 97% to 99%, fines content from 0.03% to 0.87%, calorific value as is from 17 to almost 18 MJ/kg, and ash content from 0.26% to 0.93%.The diameter and length were in the range of 6.4 to 6.5 mm and 14.0 to 19.0 mm, respectively. All of these values met the published non-industrial European grades (CEN) and the grades specified by the Pellet Fuel Institute for the United States for the bag market. The measured values for wood pellet properties were consistent except the ash content values decreased over the test period.

  1. Wood-boring Insects of Trees and Shrubs 

    E-Print Network [OSTI]

    Drees, Bastiaan M.; Jackman, John A.; Merchant, Michael E.

    2008-06-17T23:59:59.000Z

    termites, carpenter bees and carpenter ants. Many other insects live in dying or dead trees, including natural enemies (predators and parasites) of the insect borers, sap or fungi feeders, or species which merely use the spaces provided by the tunnels... segments behind the head capsule. While tunneling, larvae continually pack their tunnels with excrement (frass), which looks like compressed wood fibers, or push frass out of the holes they pro- duce. This excrement, along with the sap exuded by the plant...

  2. Performance of bolted wood connections using supplemental confining devices

    E-Print Network [OSTI]

    Stromatt, Rebecca Faye

    1996-01-01T23:59:59.000Z

    (1994) currently restricts the use of 2x dimensioned lumber for sill plates (nominal lumber thickness of The style and format of this thesis follow the Journal of Structural Engineering. 38. 1 mm [1. 5 in]) and requires the use of 3x dimensioned... lumber (nominal lumber thickness of 63. 5 mm [2. 5 in]). While a thicker wood member would increase the strength capacity of the connection according to analytical strength models, the ultimate failure mode under extreme loading conditions can still...

  3. An evaluation of atmospheric evaporation for treating wood preserving wastes

    E-Print Network [OSTI]

    Shack, Pete A

    1976-01-01T23:59:59.000Z

    i. hat a constant rate of total organi carbon and chemical oxygen demand removal occurred as the wastewai. r was evaporated. A procedure for designing atmospheric evaporation ponds was developed and applied to a hypothetical wood preserving plant.... From this example design estimates of equivalent hydrocarbon concentrations in the air downwind of the pond are made. Various other design con- siderations such as the input data, modifications to the design pro- cedure, solids accumulation...

  4. The treatment of wood preserving wastes with activated carbon

    E-Print Network [OSTI]

    Pence, Robert Fuller

    1978-01-01T23:59:59.000Z

    requirement and treatment schemes should be based on these combined requirements. Current treatment schemes employed in the wood preserving industry combine physical, chemical, and biological processes and operations in treating wastewaters. Jones, et al...-five of the plants performed secondary treatment on-site of which 32 used biological methods. Only 6 per- cent discharged their wastewaters directly to the environment without any form of treatment and approximately 40 percent of the plants planned to change...

  5. Cermet Spent Nuclear Fuel Casks and Waste Packages

    SciTech Connect (OSTI)

    Forsberg, Charles W.; Dole, Leslie R. [Nuclear Science and Technology Division, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN, 37831-6165 (United States)

    2007-07-01T23:59:59.000Z

    Multipurpose transport, aging, and disposal casks are needed for the management of spent nuclear fuel (SNF). Self-shielded cermet casks can out-perform current SNF casks because of the superior properties of cermets, which consist of encapsulated hard ceramic particulates dispersed in a continuous ductile metal matrix to produce a strong high-integrity, high-thermal conductivity cask. A multi-year, multinational development and testing program has been developing cermet SNF casks made of steel, depleted uranium dioxide, and other materials. Because cermets are the traditional material of construction for armor, cermet casks can provide superior protection against assault. For disposal, cermet waste packages (WPs) with appropriate metals and ceramics can buffer the local geochemical environment to (1) slow degradation of SNF, (2) reduce water flow though the degraded WP, (3) sorb neptunium and other radionuclides that determine the ultimate radiation dose to the public from the repository, and (4) contribute to long-term nuclear criticality control. Finally, new cermet cask fabrication methods have been partly developed to manufacture the casks with the appropriate properties. The results of this work are summarized with references to the detailed reports. (authors)

  6. Safe Advantage on Dry Interim Spent Nuclear Fuel Storage

    SciTech Connect (OSTI)

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

    2008-07-01T23:59:59.000Z

    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)

  7. Physical and decay characteristics of commercial LWR spent fuel

    SciTech Connect (OSTI)

    Roddy, J.W.; Claiborne, H.C.; Ashline, R.C.; Johnson, P.J.; Rhyne, B.T.

    1986-01-01T23:59:59.000Z

    Information was collected from the literature and from major manufacturers that will be useful in the design and construction of a mined geologic repository for the disposal of light-water-reactor spent fuel. Pertinent data are included on mechanical design characteristics and materials of construction for fuel assemblies and fuel rods and computed values for heat generation rates, radioactivity, and photon and neutron emission rates as a function of time for four reference cases. Calculations were made with the ORIGEN2 computer code for burnups of 27,500 and 40,000 MWd for a typical boiling-water reactor and 33,000 and 60,000 MWd for a typical pressurized-water reactor. The results are presented in figures depicting the individual contributions per metric ton of initial heavy metal for the activation products, fission products, and actinides and their daughters to the radioactivity and thermal power as a function of time. Tables are also presented that list the contribution of each major nuclide to the radioactivity, thermal power, and photons and neutrons emitted for disposal emitted for disposal periods from 1 to 100,000 years.

  8. Radionuclide release rates from spent fuel for performance assessment modeling

    SciTech Connect (OSTI)

    Curtis, D.B.

    1994-11-01T23:59:59.000Z

    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.

  9. Packaging and transportation system for K-Basin spent fuel

    SciTech Connect (OSTI)

    Kee, A.T.

    1998-03-03T23:59:59.000Z

    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.

  10. Spent fuel drying system test results (second dry-run)

    SciTech Connect (OSTI)

    Klinger, G.S.; Oliver, B.M.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J.; Ritter, G.A.

    1998-07-01T23:59:59.000Z

    The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks have been detected in the basins and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 7.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the second dry-run test, which was conducted without a fuel element. With the concurrence of project management, the test protocol for this run, and subsequent drying test runs, was modified. These modifications were made to allow for improved data correlation with drying procedures proposed under the IPS. Details of these modifications are discussed in Section 3.0.

  11. Dose reduction improvements in storage basins of spent nuclear fuel

    SciTech Connect (OSTI)

    Huang, Fan-Hsiung F.

    1997-08-13T23:59:59.000Z

    Spent nuclear fuel in storage basins at the Hanford Site has corroded and contaminated basin water, which has leaked into the soil; the fuel also had deposited a layer of radioactive sludge on basin floors. The SNF is to be removed from the basins to protect the nearby Columbia River. Because the radiation level is high, measures have been taken to reduce the background dose rate to as low as reasonably achievable (ALARA) to prevent radiation doses from becoming the limiting factor for removal of the SW in the basins to long-term dry storage. All activities of the SNF Project require application of ALARA principles for the workers. On the basis of these principles dose reduction improvements have been made by first identifying radiological sources. Principal radiological sources in the basin are basin walls, basin water, recirculation piping and equipment. Dose reduction activities focus on cleaning and coating basin walls to permit raising the water level, hydrolasing piping, and placing lead plates. In addition, the transfer bay floor will be refinished to make decontamination easier and reduce worker exposures in the radiation field. The background dose rates in the basin will be estimated before each task commences and after it is completed; these dose reduction data will provide the basis for cost benefit analysis.

  12. Accelerator-driven transmutation of spent fuel elements

    DOE Patents [OSTI]

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

    2002-01-01T23:59:59.000Z

    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

  13. A NOVEL APPROACH TO SPENT FUEL POOL DECOMMISSIONING

    SciTech Connect (OSTI)

    R. L. Demmer

    2011-04-01T23:59:59.000Z

    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.

  14. Sustainability Considerations in Spent Light-water Nuclear Fuel Retrievability

    SciTech Connect (OSTI)

    Wood, Thomas W.; Rothwell, Geoffrey

    2012-01-10T23:59:59.000Z

    This paper examines long-term cost differences between two competing Light Water Reactor (LWR) fuels: Uranium Oxide (UOX) and Mixed Uranium Oxide-Plutonium Oxide (MOX). Since these costs are calculated on a life-cycle basis, expected savings from lower future MOX fuel prices can be used to value the option of substituting MOX for UOX, including the value of maintaining access to the used UOX fuel that could be reprocessed to make MOX. The two most influential cost drivers are the price of natural uranium and the cost of reprocessing. Significant and sustained reductions in reprocessing costs and/or sustained increases in uranium prices are required to give positive value to the retrievability of Spent Nuclear Fuel. While this option has positive economic value, it might not be exercised for 50 to 200 years. Therefore, there are many years for a program during which reprocessing technology can be researched, developed, demonstrated, and deployed. Further research is required to determine whether the cost of such a program would yield positive net present value and/or increases the sustainability of LWR energy systems.

  15. Seismic Behavior of Spent Fuel Dry Cask Storage Systems

    SciTech Connect (OSTI)

    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

    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)

  16. The effect of fuel type in unsaturated spent fuel tests

    SciTech Connect (OSTI)

    Finn, P.A.; Gong, M.; Bates, J.K.; Emery, J.W.; Hoh, J.C.

    1994-04-01T23:59:59.000Z

    Two well-characterized types of spent nuclear fuel (ATM-103 and ATM-106) were tested under simulated unsaturated conditions with simulated groundwater at 90{degree}C. The actinides present in the leachate were measured after periods of approximately 60, 120, and 275 days. The vessels were acid stripped after 120 and 275 days. Both colloidal and soluble actinide species were detected in the leachates which had pHs ranging from 4 to 7. Alpha spectroscopy studies of filtered and unfiltered leachates showed that large amounts of actinides may be bound in colloids. The uranium phases identified in the colloids were schoepite and soddyite. The actinide release behavior of the two fuels appears to be different. The ATM-106 fuel began to release actinides later than the ATM-103 fuel, but after 275 days, it had released more. The amount of americium released from the two fuels was a higher percentage of the maximum amount of americium present than was the percentage of the simultaneous amount of uranium released.

  17. Method for predicting dry mechanical properties from wet wood and standing trees

    DOE Patents [OSTI]

    Meglen, Robert R.; Kelley, Stephen S.

    2003-08-12T23:59:59.000Z

    A method for determining the dry mechanical strength for a green wood comprising: illuminating a surface of the wood to be determined with light between 350-2,500 nm, the wood having a green moisture content; analyzing the surface using a spectrometric method, the method generating a first spectral data, and using a multivariate analysis to predict the dry mechanical strength of green wood when dry by comparing the first spectral data with a calibration model, the calibration model comprising a second spectrometric method of spectral data obtained from a reference wood having a green moisture content, the second spectral data correlated with a known mechanical strength analytical result obtained from a reference wood when dried and having a dry moisture content.

  18. aluminium-clad spent fuel: Topics by E-print Network

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

    2009-05-15 8 Nuclear Waste Imaging and Spent Fuel Verification by Muon Tomography CERN Preprints Summary: This paper explores the use of cosmic ray muons to image the...

  19. aluminum-based spent nuclear: Topics by E-print Network

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

    1982- 2012-11-20 3 Nuclear Waste Imaging and Spent Fuel Verification by Muon Tomography CERN Preprints Summary: This paper explores the use of cosmic ray muons to image the...

  20. aluminum-clad spent nuclear: Topics by E-print Network

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

    1982- 2012-11-20 3 Nuclear Waste Imaging and Spent Fuel Verification by Muon Tomography CERN Preprints Summary: This paper explores the use of cosmic ray muons to image the...

  1. Assessment of uranium-free nitride fuels for spent fuel transmutation in fast reactor systems 

    E-Print Network [OSTI]

    Szakaly, Frank Joseph

    2004-09-30T23:59:59.000Z

    The purpose of this work is to investigate the implementation of nitride fuels containing little or no uranium in a fast-spectrum nuclear reactor to reduce the amount of plutonium and minor actinides in spent nuclear fuel ...

  2. 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...

  3. Impact of PWR spent fuel variations on TRU-fueled VHTRS

    E-Print Network [OSTI]

    Alajo, Ayodeji Babatunde

    2009-05-15T23:59:59.000Z

    Several alternative strategies are being considered as spent nuclear fuel (SNF) management options. Transuranic nuclides (TRU) are responsible for the SNF long-term radiotoxicity beyond the first 500 years. One of the most viable approaches suggests...

  4. 324 Building spent fuel segments pieces and fragments removal summary report

    SciTech Connect (OSTI)

    SMITH, C L

    2003-01-09T23:59:59.000Z

    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).

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

    SciTech Connect (OSTI)

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

    2014-06-10T23:59:59.000Z

    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.

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

    E-Print Network [OSTI]

    Fox, J.P.

    2013-01-01T23:59:59.000Z

    and inorganic carbon, The solid waste, referred to as spent45 Kg (25 to 100 pounds) of solid waste per barrel of oil,be disposed with other solid wastes in an on-site solid

  7. Effects of Acid Additives on Spent Acid Flowback through Carbonate Cores

    E-Print Network [OSTI]

    Nasir, Ehsaan Ahmad

    2012-07-16T23:59:59.000Z

    these challenges, different chemicals, or additives, are added to the acid solution such as corrosion inhibitors and iron control agents. These additives may change the relative permeability of the spent acid, and formation wettability, and may either hinder...

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

    DOE Patents [OSTI]

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

    2013-11-05T23:59:59.000Z

    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.

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

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2009-01-01T23:59:59.000Z

    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...

  10. Spent Shale Grouting of Abandoned In-Situ Oil Shale Retorts

    E-Print Network [OSTI]

    Fox, J.P.; Persoff, P.

    1980-01-01T23:59:59.000Z

    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

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

    SciTech Connect (OSTI)

    Koji Shirai

    2006-04-01T23:59:59.000Z

    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.

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

    E-Print Network [OSTI]

    Miller, Marvin M.

    1978-01-01T23:59:59.000Z

    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 ...

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

    SciTech Connect (OSTI)

    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

    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.

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

    SciTech Connect (OSTI)

    Bailey, W.J.

    1990-02-01T23:59:59.000Z

    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.

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

    SciTech Connect (OSTI)

    NONE

    1996-07-01T23:59:59.000Z

    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.

  16. Potential importance of water pathways for spent fuel transportation accident risk

    SciTech Connect (OSTI)

    Ostmeyer, R.M.

    1986-01-01T23:59:59.000Z

    This paper analyzes the potential importance of water pathway contamination for spent fuel transportation accident risk using a ''worst-case'' water contamination scenario. The scenario used for the analysis involves an accident release that occurs near a reservoir. Water pathway doses are compared to doses for accident releases in urban or agricultural areas. The results of the analysis indicate that water pathways are not important for assessing the risk of transporting spent reactor fuel by truck or by rail.

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

    SciTech Connect (OSTI)

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

    1993-12-31T23:59:59.000Z

    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.

  18. Colorado School of Mines Nov-12 Cylindrical or mortise lock aluminum, wood or steel door

    E-Print Network [OSTI]

    Colorado School of Mines Nov-12 Cylindrical or mortise lock aluminum, wood or steel door Hinges 4 cylindrical or mortise lock aluminum, wood or steel door Hinges 4.5"x4.5" Ives 5BB1HW El Hinge 4.5"x4 FS18S OR FS444 #12;Colorado School of Mines Nov-12 Aluminum, wood or steel door with panic bar Hinges

  19. Annual report, FY 1979 Spent fuel and fuel pool component integrity.

    SciTech Connect (OSTI)

    Johnson, A.B. Jr.; Bailey, W.J.; Schreiber, R.E.; Kustas, F.M.

    1980-05-01T23:59:59.000Z

    International meetings under the BEFAST program and under INFCE Working Group No. 6 during 1978 and 1979 continue to indicate that no cases of fuel cladding degradation have developed on pool-stored fuel from water reactors. A section from a spent fuel rack stand, exposed for 1.5 y in the Yankee Rowe (PWR) pool had 0.001- to 0.003-in.-deep (25- to 75-..mu..m) intergranular corrosion in weld heat-affected zones but no evidence of stress corrosion cracking. A section of a 304 stainless steel spent fuel storage rack exposed 6.67 y in the Point Beach reactor (PWR) spent fuel pool showed no significant corrosion. A section of 304 stainless steel 8-in.-dia pipe from the Three Mile Island No. 1 (PWR) spent fuel pool heat exchanger plumbing developed a through-wall crack. The crack was intergranular, initiating from the inside surface in a weld heat-affected zone. The zone where the crack occurred was severely sensitized during field welding. The Kraftwerk Union (Erlangen, GFR) disassembled a stainless-steel fuel-handling machine that operated for 12 y in a PWR (boric acid) spent fuel pool. There was no evidence of deterioration, and the fuel-handling machine was reassembled for further use. A spent fuel pool at a Swedish PWR was decontaminated. The procedure is outlined in this report.

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

    SciTech Connect (OSTI)

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

    1998-07-01T23:59:59.000Z

    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.

  1. MANAGING SPENT NUCLEAR FUEL WASTES AT THE IDAHO NATIONAL LABORATORY

    SciTech Connect (OSTI)

    Hill, Thomas J

    2005-09-01T23:59:59.000Z

    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 it’s 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.

  2. Issues in the use of wood as an energy source in the northeastern US

    SciTech Connect (OSTI)

    Munson, J.S. (ed.)

    1980-05-01T23:59:59.000Z

    This report analyzes some of the concerns surrounding the use of wood for energy in the Northeast. It reviews the information on resource availability and ownership patterns in the Northeast, then focuses on New England, to assess the affect of potential resource constraints on the supply of wood available for energy and the effects of wood energy use on land use patterns. Finally, the application of specific technologies in settings that may experience significant wood energy use in the future is considered, including an assessment of the regional employment and income benefits of a major woodfuel installation.

  3. A review of "The Life of Anthony Wood In His Own Words" edited by Nicholas Kiessling

    E-Print Network [OSTI]

    Paleit, Edward

    2011-01-01T23:59:59.000Z

    authors exasperating, it is a vital form of exasperation. And whatever the exasperation, Genre and Women?s Life Writing in Early Modern England is much better reading than most blogs. Nicholas Kiessling, ed. #31;e Life of Anthony Wood In His Own Words...;#30;#21;#31; until retrieved by more recent scholarship, especially in the case of women. Anthony Wood, or as he later called himself, ? Wood, the historian of Oxford University and biographer of its alumni, was more fortunate. Wood wrote two manuscript...

  4. Techno-economic analysis of wood biomass boilers for the greenhouse industry

    SciTech Connect (OSTI)

    Chau, J. [University of British Columbia, Vancouver; Sowlati, T. [University of British Columbia, Vancouver; Sokhansanj, Shahabaddine [ORNL; Bi, X.T. [University of British Columbia, Vancouver; Preto, F. [Natural Resources Canada; Melin, Staffan [University of British Columbia, Vancouver

    2009-01-01T23:59:59.000Z

    The objective of this study is to perform a techno-economic analysis on a typical wood pellet and wood residue boiler for generation of heat to an average-sized greenhouse in British Columbia. The variables analyzed included greenhouse size and structure, boiler efficiency, fuel types, and source of carbon dioxide (CO2) for crop fertilization. The net present value (NPV) show that installing a wood pellet or a wood residue boiler to provide 40% of the annual heat demand is more economical than using a natural gas boiler to provide all the heat at a discount rate of 10%. For an assumed lifespan of 25 years, a wood pellet boiler system could generate NPV of C$259,311 without electrostatic precipitator (ESP) and C$74,695 with ESP, respectively. While, installing a wood residue boiler with or without an ESP could provide NPV of C$919,922 or C$1,104,538, respectively. Using a wood biomass boiler could also eliminate over 3000 tonne CO2 equivalents of greenhouse gases annually. Wood biomass combustion generates more particulate matters than natural gas combustion. However, an advanced emission control system could significantly reduce particulate matters emission from wood biomass combustion which would bring the particulate emission to a relatively similar level as for natural gas.

  5. Microsoft Word - CX-RedmondWoodPoles_multiSub_WEB.doc

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

    5, 2011 REPLY TO ATTN OF: KEP-Celilo SUBJECT: Environmental Clearance Memorandum Darrell Aaby Line Foreman III - TFDF-Redmond Proposed Action: Wood pole replacement at selected...

  6. Microsoft Word - CX-FY11PascoDistrictWoodPoleReplacement_WEB...

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

    1, 2011 REPLY TO ATTN OF: KEPR-PASCO SUBJECT: Environmental Clearance Memorandum Toby Cossairt Lineman Foreman III - TFPF-PASCO Proposed Action: Wood pole replacement and minor...

  7. Microsoft Word - CX-AlveyDistrictWoodPoles-FY14_WEB.doc

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

    8, 2014 REPLY TO ATTN OF: KEP-Alvey SUBJECT: Environmental Clearance Memorandum Stacey Hensley Project Manager - TEP-TPP-4 Proposed Action: 2014 Alvey District Wood Pole...

  8. Microsoft Word - CX-BigEddy-RedmondWoodPoles_WEB.doc

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

    1 REPLY TO ATTN OF: KEP-Celilo SUBJECT: Environmental Clearance Memorandum Darrell Aaby Line Foreman III - TFDF-Redmond Proposed Action: Wood pole replacements at select locations...

  9. Microsoft Word - CX-FY11WenatcheeDistrictWoodPoleReplacement...

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

    4, 2011 REPLY TO ATTN OF: KEPR-PASCO SUBJECT: Environmental Clearance Memorandum Terry Kugler Lineman Foreman III - TFWF-SCHULTZ Proposed Action: Wood pole replacement and minor...

  10. Microsoft Word - CX-CowlitzTaptoChehalis-CovingtonWoodPoles_WEB...

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

    8, 2011 REPLY TO ATTN OF: KEPR-Covington SUBJECT: Environmental Clearance Memorandum Clay Grande Line Foreman III - TFCF-Covington Proposed Action: Wood pole replacement at...

  11. Microsoft Word - CX-RossDistrictWoodPolesFY13_WEB.doc

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

    9, 2013 REPLY TO ATTN OF: KEP-Alvey SUBJECT: Environmental Clearance Memorandum Stacie Hensley Realty Specialist - TEP-TPP-4 Proposed Action: 2013 Ross District Wood Pole...

  12. Microsoft Word - CX-PilotButte-LaPine-WoodPoles-FY13_WEB.doc

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

    3, 2013 REPLY TO ATTN OF: KEPR-4 SUBJECT: Environmental Clearance Memorandum Richard Heredia Project Manager - TEP-TPP-1 Proposed Action: Wood pole replacements on Bonneville Power...

  13. Microsoft Word - CX-Chehalis-CentraliaNo2WoodPolesFY12_WEB.doc

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

    0, 2012 REPLY TO ATTN OF: KEPROlympia SUBJECT: Environmental Clearance Memorandum Ryan Brady Line Foreman III - TFOK-Chehalis Proposed Action: Wood pole structure replacements on...

  14. Microsoft Word - CX-KalispellTLMDistrictFY11WoodPoleReplacement...

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

    Bell-1 SUBJECT: Environmental Cleareance Memorandum Michael Stolfus Lineman Foreman III - TFKF-Kalispell Kurt Marsh Lineman Foreman I - TFKF-Kalispell Proposed Action: Wood pole...

  15. WOODS FOR LEARNING ACTION PLAN 2010-2013 Objective National Indicators Specific actions

    E-Print Network [OSTI]

    WOODS FOR LEARNING ACTION PLAN 2010-2013 Objective National Indicators Specific actions Lead positive inspection reports Develop Forest Kindergarten with nurseries in both private and state sectors

  16. Spent Nuclear Fuel (SNF) Project Design Basis Capacity Study

    SciTech Connect (OSTI)

    CLEVELAND, K.J.

    2000-08-17T23:59:59.000Z

    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.

  17. Distribution of characteristics of LWR [light water reactor] spent fuel

    SciTech Connect (OSTI)

    Reich, W.J.; Notz, K.J. [Oak Ridge National Lab., TN (USA); Moore, R.S. [Automated Sciences Group, Inc., Oak Ridge, TN (USA)

    1991-01-01T23:59:59.000Z

    The purpose of this report is to develop a collective description of the entire spent fuel inventory in terms of various fuel properties relevant to Approved Testing Materials (ATMs) using information available from the Characteristics Data Base (CBD), which is sponsored by the US Department of Energy`s (DOE`s) Office of Civilian Radioactive Waste Management. A number of light-water reactor (LWR) characteristics were analyzed including assembly class representation, fuel burnup, enrichment, fuel fabrication data, defective fuel quantities, and, at PNL`s specific request, linear heat generation rate (LHGR) and the utilization of burnable poisons. A quantitative relationships was developed between burnup and enrichment for BWRs and PWRs. The relationship shows that the existing BWR ATM is near the center of the burnup-enrichment distribution, while the four PWR ATMs bracket the center of the burnup range but are on the low side of the enrichment range. Fuel fabrication data are based on vendor specifications for new fuel. Defective fuel distributions were analyzed in terms of assembly class and vendor design. LHGR values were calculated from utility data on burnup and effective full-power days; these calculations incorporate some unavoidable assumptions which may compromise the value of the results. Only a limited amount of data are available on burnable poisons at this time. Based on this distribution study, suggestions for additional ATMs are made. These are based on the class and design concepts and include BWR/2,3 barrier fuel, and the WE 17 {times} 17 class with integral burnable poison. Both should be at relatively high burnups. 16 refs., 5 figs., 15 tabs.

  18. Laguna Woods, California: Energy Resources | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere I Geothermal Pwer Plant Jump to: navigation,working-groups <LackawannaLago Vista, Texas:Hills,Woods,

  19. Water Sampling At International Geothermal Area, New Zealand (Wood, 2002) |

    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 onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTown ofNationwideWTED Jump to: navigation,Area (Wood, 2002) Jump to: navigation,Open

  20. Wood-Ridge, New Jersey: Energy Resources | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells, Wisconsin: Energy Resources JumpWood, Wisconsin: Energy Resources

  1. Wood County, Ohio: Energy Resources | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to:Ezfeedflag JumpID-fTriWildcat 1 Wind Project JumpWisconsin: Energy ResourcesWolverine JumpWood

  2. Lake of the Woods, California: Energy Resources | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are beingZealand Jump to: navigation, searchOf Kilauea Volcano, Hawaii9969995°,ILEDSGP/joinHavasuPalmdaleLakeWoods,

  3. Woods County, Oklahoma: Energy Resources | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells, Wisconsin: Energy ResourcesWoods County, Oklahoma: Energy Resources Jump

  4. Woods Hole, Massachusetts: Energy Resources | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells, Wisconsin: Energy ResourcesWoods County, Oklahoma: Energy Resources

  5. Wood and Pellet Heating Basics | 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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently20,000 Russian Nuclear Warheads|ofEvents »SSL BasicsKawtarSue CangeWendeWood and Pellet

  6. Hancock-Wood Electric Coop Inc | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov You are8COaBulkTransmissionSitingProcess.pdfGetec AG| Open EnergyGuntersvilleHallandaleHamlinHanauOhio:Hancock-Wood

  7. Meadow Woods, Florida: Energy Resources | 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 onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere I Geothermal Pwer Plant JumpMarysville, Ohio: Energy8429°, -88.864698° ShowMeade County, Kansas:Acres,Woods,

  8. Wood-Composites Industry Benefits from ALS Research

    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: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level:Energy: Grid Integration Redefining What'sis Taking Over OurThe Iron SpinPrincetonUsingWhat is abig worldFélicieTeresaConcernswithWood

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

    SciTech Connect (OSTI)

    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

    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.

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

    SciTech Connect (OSTI)

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

    1997-06-01T23:59:59.000Z

    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.

  11. Spent fuel drying system test results (first dry-run)

    SciTech Connect (OSTI)

    Klinger, G.S.; Oliver, B.M.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J.; Ritter, G.A.

    1998-07-01T23:59:59.000Z

    The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basin have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site. Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 7.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the first dry-run test, which was conducted without a fuel element. The empty test apparatus was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The data from this dry-run test can serve as a baseline for the first two fuel element tests, 1990 (Run 1) and 3128W (Run 2). The purpose of this dry-run was to establish the background levels of hydrogen in the system, and the hydrogen generation and release characteristics attributable to the test system without a fuel element present. This test also serves to establish the background levels of water in the system and the water release characteristics. The system used for the drying test series was the Whole Element Furnace Testing System, described in Section 2.0, which is located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodology are given in section 3.0, and the experimental results provided in Section 4.0. These results are further discussed in Section 5.0.

  12. Journal of Hazardous Materials A135 (2006) 2131 Leaching of chromated copper arsenate (CCA)-treated wood in a

    E-Print Network [OSTI]

    Florida, University of

    2006-01-01T23:59:59.000Z

    . Monofills are a type of landfill designed and operated to dispose a single waste type, such as ash, tires-treated wood is commingled with untreated wood as part of recycling operations, the mulch product produced

  13. Seismic design of a current woodframe structure and study of innovative products and damping systems in wood construction

    E-Print Network [OSTI]

    Mahjoub, Nina A. (Nina Azadeh)

    2007-01-01T23:59:59.000Z

    Wood structures have seen resurgence in popularity over the past several decades, especially in Western States of America, such as California. The industry keeps creating new structural wood products of exceptional strength, ...

  14. International Conference on Wood-based Bioenergy LIGNA+Hannover, Germany, 17-18 May 2007

    E-Print Network [OSTI]

    International Conference on Wood-based Bioenergy LIGNA+Hannover, Germany, 17-18 May 2007 Photo: NTC+Hannover, Germany, 17-18 May 2007 Photo: NTC Photo: Stora Enso Photo: Stora Enso Topics I. Background for bioenergy;International Conference on Wood-based Bioenergy LIGNA+Hannover, Germany, 17-18 May 2007 Photo: NTC Photo: Stora

  15. Mid-infrared absorption properties of green wood Anna Dupleix Domingos De Sousa Meneses

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    ORIGINAL Mid-infrared absorption properties of green wood Anna Dupleix · Domingos De Sousa Meneses and the amount of energy absorbed by green wood under infrared (IR) radiation. This lack of knowledge is a potential barrier to the development of IR heating as an alternative to soaking as a means of warming logs

  16. Influences of Government Interventions on Increasing Value-Added Wood Product Exports from Ghana

    E-Print Network [OSTI]

    Influences of Government Interventions on Increasing Value-Added Wood Product Exports from Ghana exporting raw materials such lumber to exporting processed or value-added wood products. In the mid-1990s on increasing value-added exports. These actions are: 1) the imposition of a levy on air-dried lumber exports, 2

  17. Field Document No.50 REGIONAL WOOD ENERGY DEVELOPMENT PROGRAMME IN ASIA

    E-Print Network [OSTI]

    AND TOMORROW IN ASIA #12;This publication is printed by the FAO Regional Wood Energy Development Programme wood energy data, leading to best estimates of future consumption. It also tries to estimate development in other relevant sectors like agriculture and energy is also strongly recommended. The document

  18. Forestry building a future in the South Southern Wood Council Forest Products Scholarship

    E-Print Network [OSTI]

    Hickman, Mark

    Forestry ­ building a future in the South Southern Wood Council Forest Products Scholarship attached): A written submission (no more than 1 page double sided) on why you are pursuing Forestry APPLICATIONS WILL BE ACCEPTED #12; Forestry ­ building a future in the South SOUTHERN WOOD COUNCIL FOREST

  19. ECOLOGICAL NOTES ON THE SIREX WOOD WASPS AND THEIR By H. S. HANSON.

    E-Print Network [OSTI]

    27 ECOLOGICAL NOTES ON THE SIREX WOOD WASPS AND THEIR PARASITES. By H. S. HANSON. Farnham House on the ecology of the Sirex wood-wasps and their parasites have been collected during a period of several years. The preliminary investigations were carried out by Dr. J. G. Myers, of Farnham House Laboratory, in collaboration

  20. INTRODUCTION Red wood ants play an important role in the ecology of

    E-Print Network [OSTI]

    Thomas, Len

    INTRODUCTION Red wood ants play an important role in the ecology of woodland ecosystems by virtue the ecological impor- tance of red wood ants (Gösswald, 1989) and the conser- vation concern for some species.borkin@clear.net.nz 2 Royal Society for the Protection of Birds, Etive House, Beechwood Park, Inverness, IV2 3BW, UK; e

  1. Ergonomic Solutions for the Secondary Wood Products Industry On October 17th

    E-Print Network [OSTI]

    Gazo, Rado

    Ergonomic Solutions for the Secondary Wood Products Industry On October 17th and 18th , 2001, you are invited to a conference entitled: Ergonomic Solutions for the Secondary Wood Products Industry. This seminar will be held at Executive Inn, in Louisville, Kentucky. Hear the latest developments in ergonomics

  2. Opportunities for UPC Product and Service Suppliers: The Wood Products Industry

    E-Print Network [OSTI]

    Wu, Qinglin

    product and service suppliers. #12;4 UPC Suppliers To The Wood Products Industry Twenty-seven companies.3 percent of all corporate sales for these 27 respondent companies. An additional 15 companies indicated, from the largest timbers to small lengths of wood moulding are complying with customer requirements

  3. Solar energy and multi-storey residential buildings Larry Hughes and Tylor Wood

    E-Print Network [OSTI]

    Hughes, Larry

    ERG/200702 Solar energy and multi-storey residential buildings Larry Hughes and Tylor Wood Energy.hughes@dal.ca 26 March 2007 #12;Hughes and Wood: Solar energy and multi-storey residential buildings 1 Summary This report considers the limitations on solar energy in new, multi-storey residential buildings. In a time

  4. Modern Wood Energy Systems and Markets 16-17 September 2008, Timisoara, Romania

    E-Print Network [OSTI]

    overcoming a rise in European and CIS). · Oil prices soared, stimulating wood-based biofuels and policies 16-17 September 2008, Timisoara, Romania Oil prices 0 20 40 60 80 100 120 140 2004 2005 2006 2007 with countries in the UNECE region continues to increase. · In Europe, wood products prices generally rose

  5. Historical changes in the distribution and functions of large wood in Puget Lowland rivers

    E-Print Network [OSTI]

    Montgomery, David R.

    Historical changes in the distribution and functions of large wood in Puget Lowland rivers Brian D and functions in Puget Lowland rivers from the last ~150 years of land use by comparing field data from an 11-km and with archival data from several Puget Lowland rivers. Current wood abundance is one to two orders of magnitude

  6. Uses and Desirable Properties of Wood in the 21st Century

    E-Print Network [OSTI]

    of social, economic, and environmental factors that influence wood-use trends. This article discusses plantations. Advances in biotechnology will enable tailoring wood properties of plantation trees and short are driven by social, economic, and environmental factors generally beyond the control of forest sector

  7. EFFECTS OF RESIN AND WAX ON THE WATER UPTAKE BEHAVIOR OF WOOD STRANDS

    E-Print Network [OSTI]

    Wang, Siqun

    EFFECTS OF RESIN AND WAX ON THE WATER UPTAKE BEHAVIOR OF WOOD STRANDS Yang2hang1 Post and wax are essential additives in the manufactureof composite panels such as OSB. Resin binds wood elements together while wax acts as a water repellent. The objective of this study was to investigate

  8. Cancer Mortality and Wood Dust Exposure Among Participants in the American Cancer

    E-Print Network [OSTI]

    Salzman, Daniel

    Cancer Mortality and Wood Dust Exposure Among Participants in the American Cancer Society Cancer and Paolo Boffetta, MD, MPH3 In 1994, the International Agency for Research on Cancer (IARC) classified wood dust as a human carcinogen, based on very strong evidence of a carcinogenic risk of sino-nasal cancer

  9. Biomimetic soy protein nanocomposites with calcium carbonate crystalline arrays for use as wood adhesive

    E-Print Network [OSTI]

    Biomimetic soy protein nanocomposites with calcium carbonate crystalline arrays for use as wood 2010 Available online 21 March 2010 Keywords: Wood glue Calcium carbonate Gecko adhesion Soy protein crosslinking of calcium, carbonate, hydroxyl ions in the adhesive greatly improving the water- resistance

  10. Research Article Fibre wall and lumen fractions drive wood density variation

    E-Print Network [OSTI]

    Wright, Ian

    with hydraulic strategies. Denser woods tend to operate at more negative water potentials (Ackerly 2004; Bucci et et al. 2011). Wood density has been studied in relation to hydraulic conductivity but the results.s.zieminska@gmail.com Published by Oxford University Press on behalf of the Annals of Botany Company. This is an Open Access

  11. New Lines of CCA-Treated Wood Research: In-Service and Disposal Issues

    E-Print Network [OSTI]

    Florida, University of

    New Lines of CCA-Treated Wood Research: In-Service and Disposal Issues Submitted March 19, 2001 Objectives 2 I.3 Background 4 CHAPTER II, METALS CONCENTRATIONS IN SOILS BELOW DECKS MADE OF CCA-TREATED WOOD Results from Soil Core Samples 24 II.7 Summary and Conclusions 28 CHAPTER III, INVENTORY OF CCA-TREATED

  12. A pilot study of children's exposure to CCA-treated wood from playground equipment

    E-Print Network [OSTI]

    Florida, University of

    A pilot study of children's exposure to CCA-treated wood from playground equipment S.L. Shalat Arsenic from chromated copper arsenate (CCA)-treated wood, widely used in playgrounds and other outdoor associated with children playing on CCA- treated playgrounds. In a Pilot Study, 11 children (13­71 months

  13. A pilot study of children's exposure to CCA-treated wood from playground equipment

    E-Print Network [OSTI]

    Florida, University of

    A pilot study of children's exposure to CCA-treated wood from playground equipment S.L. Shalat online 17 February 2006 Abstract Arsenic from chromated copper arsenate (CCA)-treated wood, widely used possible health risks associated with children playing on CCA- treated playgrounds. In a Pilot Study, 11

  14. Perception Drivers for Treated Wood by U.S. South Homebuilders and Remodelers

    E-Print Network [OSTI]

    Wu, Qinglin

    Perception Drivers for Treated Wood by U.S. South Homebuilders and Remodelers Sanna M. Kallioranta1 for the use of treated wood products in construction is considerable, especially in the U.S. South for termite protection and to mitigate moisture related decay. This research investigates the perception about treated

  15. Slovak Centre of Biomass Use for Energy Wood Fired Heating Plant in Slovakia

    E-Print Network [OSTI]

    authorities CHP Planning issues Transport companies District Heating Sustainable communities Utilities Solar the object of interest of municipalities and management of companies, is the issue of how to reconstruct out. Wood exploitation is well developed: many forestry and wood processing companies are represented

  16. DNA Extraction From Processed Wood: A Case Study for the Identification of an Endangered

    E-Print Network [OSTI]

    Protocols DNA Extraction From Processed Wood: A Case Study for the Identification of an Endangered to the extraction of whole genomic DNA from processed wood samples to explore the possibility of identifying an endangered trop- ical timber species by using DNA sequencing technology. High-yield and high-quality DNA

  17. WPMT (Fall 2009) Page 1 June 8, 2009 Wood Products Manufacturing Technology

    E-Print Network [OSTI]

    positions in wood products manufacturing, particularly for the hardwood cabinet and furniture industries to Lean Manufacturing (3) MET 14100 Materials I (4) Physics elective3 (3) STAT 30100 Elementary Sixth Semester (3) ECON 21000 Principles of Economics (3) FNR 31100 Wood Structure, Identification

  18. Determination of VOC emissions from French wood products Christophe YRIEIX *, Franois MAUPETIT **, Olivier RAMALHO **

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    wood manufacturers to determine IAQ performances of their products and to confront them with other quality (IAQ). Indeed, building products are significant sources of Volatile Organic Compounds (VOCs. This is particularly important for French wood manufacturers to determine IAQ performances of their products

  19. Illegal loggin and wood energy: UNECE Timber Committee discusses policy issues of the day SEARCH SITEMAP

    E-Print Network [OSTI]

    activities). Wood energy: "Biomass is one of the renewable energies with the greatest potential for expansion, and wood is by far the largest component of biomass energy" says Kit Prins, Chief of the UNECE Timber/FAO Timber Section Trade Development and Timber Division United Nations Economic Commission for Europe Palais

  20. A review of "John Lowin and the English Theatre, 1603-1647" by Barbara Wooding

    E-Print Network [OSTI]

    Bunker, Nancy M.

    2014-01-01T23:59:59.000Z

    assumed a more active role as a citizen with duties and responsibility over apprentices and financial oversight in the rebuilding of the Globe. Wooding’s commentary on the first decade 213 seventeenth-century news of Lowin’s career advocates for his...

  1. Wood Pellets for UBC Boilers Replacing Natural Gas Based on LCA

    E-Print Network [OSTI]

    Wood Pellets for UBC Boilers Replacing Natural Gas Based on LCA Submitted to Dr. Bi By Bernard Chan Pellets for UBC Boilers Replacing Natural Gas" By Bernard Chan, Brian Chan, and Christopher Young Abstract This report studies the feasibility of replacing natural gas with wood pellets for UBC boilers. A gasification

  2. CONTROLLING THE INTERNATIONAL TRADE IN ILLEGALLY LOGGED TIMBER AND WOOD PRODUCTS

    E-Print Network [OSTI]

    CONTROLLING THE INTERNATIONAL TRADE IN ILLEGALLY LOGGED TIMBER AND WOOD PRODUCTS A study prepared@riia.org February 2002 http://www.illegal-logging.info/uploads/1_ControllingTrade.pdf #12;Controlling the international trade in illegally logged timber and wood products Page 2 Contents EXECUTIVE SUMMARY

  3. Seismic Screening, Evaluation, Rehabilitation, and Design Provisions for Wood-Framed Structures

    E-Print Network [OSTI]

    Gupta, Rakesh

    Seismic Screening, Evaluation, Rehabilitation, and Design Provisions for Wood-Framed Structures Preston Baxter, M.ASCE1 ; Thomas H. Miller, M.ASCE2 ; and Rakesh Gupta, M.ASCE3 Abstract: Seismic Database subject headings: Seismic analysis; Seismic design; Wood structures; Shear walls; Diaphragms

  4. Production development and utilization of Zimmer Station wet FGD by-products. Final report. Volume 4, A laboratory study conducted in fulfillment of Phase 2, Objective 1 titled: Inhibition of acid production in coal refuse amended with calcium sulfite and calcium sulfate - containing FGD solids

    SciTech Connect (OSTI)

    none,

    1998-06-30T23:59:59.000Z

    Control of S02 emission from coal combustion requires desulfurization of coal before its combustion to produce coal refuse. Alternatively, gaseous emissions from coal combustion may be scrubbed to yield flue gas desulfurization (FGD) by-products that include calcium sulfite (CaSO3?0.5H2O or simply CaS03). Acid production in coal refuse due to pyrite oxidation and disposal of large amounts of FGD can cause environmental degradation. Addition of CaS03 and CaS03-containing FGD to coal refuse may reduce the amounts of oxygen and ferric ion available to oxidize pyrite because the sulfite moiety in CaS03 is a strong reductant and thus may mitigate acid production in coal refuse. In Chapter 1, it was shown that CaS03 efficiently scavenged dissolved oxygen and ferric ion in water under the conditions commonly encountered in a coal refuse disposal environment. In the presence ofCaS03, the concentration of dissolved oxygen in water exposed to the atmosphere declined to below 0.01 mg L"1 at pH <8.0. In Chapter 2, it was demonstrated that CaS03 prevented a pH drop in coal refuse slurry when 0.2 gCaS03 was added to a 2% fresh coal refuse slurry every three days. Calcium sulfite also inhibited acid leaching from fresh coal refuse in bench-scale columns under controlled conditions. During the initial 13 weeks of leaching, the total amounts of titratable acidity, soluble H\\ Fe, and Al from CaS03-treated refuse (6.4 gin 50 g fresh coal refuse) were only 26%,10%, 32%, and 39% of those of the control columns, respectively. A combination of CaS03 with CaC03 or fly ash enhanced the inhibitory effect of CaS03 on acid leaching. Calcium sulfite-containing FGD which combined CaS03, CaC03, fly ash, and gypsum showed a much stronger inhibitory effect on acid leaching than CaS03 alone. This combination effect was partially due to the positive interaction of CaS03 with CaC03 and fly ash on inhibition of acid leaching. In Chapter 3, CaS03-containing FGD was found to inhibit acid leaching from both fresh and aged coal refuse in large scale columns under simulated field conditions. During 39 weeks of leaching, the reduction of leachate acidity and Fe concentration and the increase ofleachate pH were significant (p <0.05) for the 22% FGD treatment with a linear response to increasing FGD rates (0%, 5.5%, 11%, and 22%). I conclude that CaS03 and CaS03-containing FGD have the ability to inhibit acid production in coal refuse and the inhibitory effect shown in this experiment is likely to occur under field conditions. Thus, the research results present a potential new method for mitigation of acid production in coal refuse and another beneficial utilization of FGD by-products.

  5. Provenance study and environments of deposition of the Pennslyvanian-Permian Wood River Formation, south-central Idaho, and the paleotectonic character of the Wood River basin

    E-Print Network [OSTI]

    Dean, Christopher William

    1982-01-01T23:59:59.000Z

    and provenance of the conglomerates in the Big Wood River and Fish Creek Reservoir regions of south-central Idaho is needed. Distinguishing between marine and non-marine strata and determining source terranes will aid in reconstructing Wood River basin... paleogeography and paleo- tectonics. Three source areas have been postulated in recent years: 1, The Antler highland to the west, containing volcanics and low grade metamorphic rocks (Bissell, 1960; Churkin, 1962; Roberts and Thomasson, 1964). 2. The stable...

  6. The EU Approach for Responsible and Safe Management of Spent Fuel and Radioactive Waste - 12118

    SciTech Connect (OSTI)

    Blohm-Hieber, Ute; Necheva, Christina [European Commission, Directorate-General for Energy, Luxembourg L-2920 (Luxembourg)

    2012-07-01T23:59:59.000Z

    In July 2011 legislation on responsible and safe management of spent fuel and radioactive waste was adopted in the European Union (EU). It aims at ensuring a high level of safety, avoiding undue burdens on future generations and enhancing transparency. EU Member States are responsible for the management of their spent fuel and/or radioactive waste. Each Member State remains free to define its fuel cycle policy. The spent fuel can be regarded either as a valuable resource that may be reprocessed or as radioactive waste that is destined for direct disposal. Whatever option is chosen, the disposal of high level waste, separated at reprocessing, or of spent fuel regarded as waste should be considered. The storage of radioactive waste, including long-term storage, is an interim solution, but not an alternative to disposal. To this end, each Member State has to establish, maintain and implement national policy, framework and programme for management of spent fuel and/or radioactive waste in the long term. Member States will invite international peer reviews to ensure that high safety standards are achieved. The EU approach is anchored in internationally endorsed principles and requirements of the IAEA safety standards and the Joint Convention and in this context makes them legally binding and enforceable in the EU. The EU approach of regulating the management of spent fuel and radioactive waste is anchored in the competence of the national regulatory authorities and in the internationally endorsed principles and requirements of the IAEA Safety Standards and the Joint Convention. Member States have to report to the Commission on the implementation of Directive 2011/70/Euratom for the first time by 23 August 2015, and every 3 years thereafter, taking advantage of the review and reporting under the Joint Convention. On the basis of the Member States' reports, the Commission will submit to the European Parliament and the Council a report on progress made and an inventory of radioactive waste and spent fuel present in the EU territory and the future prospects. Directive 2011/70/Euratom is a logical next step after the Council Directive 2009/71/Euratom on the nuclear safety of nuclear installations. The EU is the first major regional actor providing a binding legal framework on nuclear safety and on responsible and safe management of spent fuel and radioactive waste, and thus is a real model to progress spent fuel and waste management in a safe and responsible manner. (authors)

  7. Hygrothermal Performance of West Coast Wood Deck Roofing System

    SciTech Connect (OSTI)

    Pallin, Simon B [ORNL; Kehrer, Manfred [ORNL; Desjarlais, Andre Omer [ORNL

    2014-02-01T23:59:59.000Z

    Simulations of roofing assemblies are necessary in order to understand and adequately predict actual the hygrothermal performance. At the request of GAF, simulations have been setup to verify the difference in performance between white and black roofing membrane colors in relation to critical moisture accumulation for traditional low slope wood deck roofing systems typically deployed in various western U.S. Climate Zones. The performance of these roof assemblies has been simulated in the hygrothermal calculation tool of WUFI, from which the result was evaluated based on a defined criterion for moisture safety. The criterion was defined as the maximum accepted water content for wood materials and the highest acceptable moisture accumulation rate in relation to the risk of rot. Based on the criterion, the roof assemblies were certified as being either safe, risky or assumed to fail. The roof assemblies were simulated in different western climates, with varying insulation thicknesses, two different types of wooden decking, applied with varying interior moisture load and with either a high or low solar absorptivity at the roof surface (black or white surface color). The results show that the performance of the studied roof assemblies differs with regard to all of the varying parameters, especially the climate and the indoor moisture load.

  8. A source-term method for determining spent-fuel transport cask containment requirements: Executive summary

    SciTech Connect (OSTI)

    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

    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.

  9. MANAGEMENT OF RESEARCH AND TEST REACTOR ALUMINUM SPENT NUCLEAR FUEL - A TECHNOLOGY ASSESSMENT

    SciTech Connect (OSTI)

    Vinson, D.

    2010-07-11T23:59:59.000Z

    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.

  10. Comparison of selected foreign plans and practices for spent fuel and high-level waste management

    SciTech Connect (OSTI)

    Schneider, K.J.; Mitchell, S.J.; Lakey, L.T.; Johnson, A.B. Jr.; Hazelton, R.F.; Bradley, D.J.

    1990-04-01T23:59:59.000Z

    This report describes the major parameters for management of spent nuclear fuel and high-level radioactive wastes in selected foreign countries as of December 1989 and compares them with those in the United States. The foreign countries included in this study are Belgium, Canada, France, the Federal Republic of Germany, Japan, Sweden, Switzerland, and the United Kingdom. All the countries are planning for disposal of spent fuel and/or high-level wastes in deep geologic repositories. Most countries (except Canada and Sweden) plan to reprocess their spent fuel and vitrify the resultant high-level liquid wastes; in comparison, the US plans direct disposal of spent fuel. The US is planning to use a container for spent fuel as the primary engineered barrier. The US has the most developed repository concept and has one of the earliest scheduled repository startup dates. The repository environment presently being considered in the US is unique, being located in tuff above the water table. The US also has the most prescriptive regulations and performance requirements for the repository system and its components. 135 refs., 8 tabs.

  11. Savannah River Site Spent Nuclear Fuel Management Final Environmental Impact Statement

    SciTech Connect (OSTI)

    N /A

    2000-04-14T23:59:59.000Z

    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.

  12. Carbon-14 in waste packages for spent fuel in a tuff repository

    SciTech Connect (OSTI)

    Van Konynenburg, R.A.; Smith, C.F.; Culham, H.W.; Smith, H.D.

    1986-10-14T23:59:59.000Z

    Carbon-14 is produced naturally by cosmic ray neutrons in the upper atmosphere. It is also produced in nuclear reactors, in amounts much smaller than the global inventory. About one-third of this is released directly to the atmosphere, and the other two-thirds remains in the spent fuel. Both the Environmental Protection Agency and the Nuclear Regulatory Commission have established limits on release of the {sup 14}C in spent fuel. This is of particular concern for the proposed repository in tuff, because of the unsaturated conditions and the consequent possibility of gaseous transport of {sup 14}C as CO{sub 2}. Existing measurements and calculations of the {sup 14}C inventory in spent fuel are reviewed. The physical distribution and chemical forms of the {sup 14}C are discussed. Available data on the release of {sup 14}C from spent fuel in aqueous solutions and in gaseous environments of air, nitrogen, and helium are reviewed. Projected {sup 14}C behavior in a tuff repository is described. It is concluded that {sup 14}C release measurements from spent fuel into moist air at temperatures both above and below the in situ boiling point of water as well as detailed transport calculations for the tuff geological environment will be needed to determine whether the 10CFR60 and 40CFR191 requirements can be met. 56 refs., 1 tab.

  13. Environmental Assessment of Urgent-Relief Acceptance of Foreign Research Reactor Spent Nuclear Fuel

    SciTech Connect (OSTI)

    Not Available

    1994-04-01T23:59:59.000Z

    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.

  14. The Evolution of Dry Spent Fuel Storage in the United States

    SciTech Connect (OSTI)

    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

    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)

  15. State of Nevada comments on the OCRWM from-reactor spent fuel shipping cask preliminary design reports

    SciTech Connect (OSTI)

    Halstead, R.J.; Audin, L.; Hoskins, R.E.; Snedeker, D.F.

    1990-12-01T23:59:59.000Z

    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)

  16. 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)

    Wagner, J.C.; Parks, C.V.

    2000-09-01T23:59:59.000Z

    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.

  17. Journal of Hazardous Materials B114 (2004) 7591 Leaching of CCA-treated wood: implications for waste disposal

    E-Print Network [OSTI]

    Florida, University of

    Journal of Hazardous Materials B114 (2004) 75­91 Leaching of CCA-treated wood: implications, and copper from chromated copper arsenate (CCA)-treated wood poses possible environmental risk when disposed. Samples of un-weathered CCA-treated wood were tested using a variety of the US regulatory leaching

  18. UBC Social Ecological Economic Development Studies (SEEDS) Student Report An Investigation into the Red Listed Material: Pressure Treated Wood

    E-Print Network [OSTI]

    into the Red Listed Material: Pressure Treated Wood (Preservative Infused) and Possible Alternatives Abby Yuen of a project/report". #12;APSC 261 An Investigation into the Red Listed Material: Pressure Treated Wood. Pressure treated wood, a commonly used building material in British Columbia, is a red-listed material

  19. Metal Bioavailability and Speciation in a Wetland Tailings Repository Amended with Biosolids Compost, Wood Ash, and Sulfate

    E-Print Network [OSTI]

    Brown, Sally

    Compost, Wood Ash, and Sulfate Pam S. DeVolder, Sally L. Brown,* Dean Hesterberg, and Kumi Pandya ABSTRACT tundra swans surface amendments: (i) biosolids compost plus wood ash, (ii) and other animals found in the area have tested positive compost wood ash a low SO2 4 addition as K2SO4, and (iii) for Pb poisoning

  20. Fresh and Spent Nuclear Fuel Repatriation from the IRT-2000 Research Reactor Facility, Sofia, Bulgaria

    SciTech Connect (OSTI)

    K. J. Allen; T. G. Apostolov; I. S. Dimitrov

    2009-03-01T23:59:59.000Z

    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.