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1

Mixed-Oxide (MOX) Fuel Performance Benchmarks  

Science Conference Proceedings (OSTI)

Within the framework of the OECD/NEA Expert Group on Reactor-based Plutonium disposition (TFRPD), a fuel modeling code benchmarks for MOX fuel was initiated. This paper summarizes the calculation results provided by the contributors for the first two fuel performance benchmark problems. A limited sensitivity study of the effect of the rod power uncertainty on code predictions of fuel centerline temperature and fuel pin pressure also was performed and is included in the paper.

Ott, Larry J [ORNL; Tverberg, Terje [OECD Halden Reactor Project; Sartori, Enrico [ORNL

2009-01-01T23:59:59.000Z

2

An integrated approach for the verification of fresh mixed oxide fuel (MOX) assemblies at light water reactor MOX recycle reactors  

Science Conference Proceedings (OSTI)

This paper presents an integrated approach for the verification of mixed oxide (MOX) fuel assemblies prior to their being loaded into the reactor. There is a coupling of the verification approach that starts at the fuel fabrication plant and stops with the transfer of the assemblies into the thermal reactor. The key measurement points are at the output of the fuel fabrication plant, the receipt at the reactor site, and the storage in the water pool as fresh fuel. The IAEA currently has the capability to measure the MOX fuel assemblies at the output of the fuel fabrication plants using a passive neutron coincidence counting systems of the passive neutron collar (PNCL) type. Also. at the MOX reactor pool, the underwater coincidence counter (UWCC) has been developed to measure the MOX assemblies in the water. The UWCC measurement requires that the fuel assembly be lifted about two meters up in the storage rack to avoid interference from the fuel that is stored in the rack. This paper presents a new method to verify the MOX fuel assemblies that are in the storage rack without the necessity of moving the fuel. The detector system is called the Underwater MOX Verification System (UMVS). The integration and relationship of the three measurements systems is described.

Menlove, Howard O [Los Alamos National Laboratory; Lee, Sang - Yoon [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

3

CONVERSION OF RUSSIAN WEAPON-GRADE PLUTONIUM INTO OXIDE FOR MIXED OXIDE (MOX) FUEL FABRICATION.  

SciTech Connect

Progress has been made in the Russian Federation towards the conversion of weapons-grade plutonium (w-Pu) into plutonium oxide (PuO{sub 2}) suitable for further manufacture into mixed oxide (MOX) fuels. This program is funded both by French Commissariat x 1'Energie Atomique (CEA) and the US National Nuclear Security Administration (NNSA). The French program was started as a way to make available their expertise gained from manufacturing MOX fuel. The US program was started in 1998 in response to US proliferation concerns and the acknowledged international need to decrease available w-Pu. Russia has selected both the conversion process and the manufacturing site. This paper discusses the present state of development towards fulfilling this mission: the demonstration plant designed to process small amounts of Pu and validate all process stages and the industrial plant that will process up to 5 metric tons of Pu per year.

Glagovski, E.; Kolotilov, Y.; Glagolenko, Y.; Zygmunt, Stanley J.; Mason, C. F. V. (Caroline F. V.); Hahn, W. K. (Wendy K.); Durrer, R. E. (Russell E.); Thomas, S.; Sicard, B.; Herlet, N.; Fraize, G.; Villa, A.

2001-01-01T23:59:59.000Z

4

Program on Technology Innovation: Readiness of Existing and New U.S. Reactors for Mixed-Oxide (MOX) Fuel  

Science Conference Proceedings (OSTI)

Expanding interest in nuclear power and advanced fuel cycles indicate that use of mixed-oxide (MOX) fuel in the current and new U.S. reactor fleet could become an option for utilities in the coming decades. In light of this renewed interest, EPRI has reviewed the substantial knowledge base on MOX fuel irradiation in light water reactors (LWRs). The goal was to evaluate the technical feasibility of MOX fuel use in the U.S. reactor fleet for both existing and advanced LWR designs (Generation III/III+).

2009-05-29T23:59:59.000Z

5

Actual Scale MOX Powder Mixing Test for MOX Fuel Fabrication Plant in Japan  

Science Conference Proceedings (OSTI)

Japan Nuclear Fuel Ltd. (hereafter, JNFL) promotes a program of constructing a MOX fuel fabrication plant (hereafter, J-MOX) to fabricate MOX fuels to be loaded in domestic light water reactors. Since Japanese fiscal year (hereafter, JFY) 1999, JNFL, to establish the technology for a smooth start-up and the stable operation of J-MOX, has executed an evaluation test for technology to be adopted at J-MOX. JNFL, based on a consideration that J-MOX fuel fabrication comes commercial scale production, decided an introduction of MIMAS technology into J-MOX main process, from powder mixing through pellet sintering, well recognized as mostly important to achieve good quality product of MOX fuel, since it achieves good results in both fuel production and actual reactor irradiation in Europe, but there is one difference that JNFL is going to use Japanese typical plutonium and uranium mixed oxide powder converted with the micro-wave heating direct de-nitration technology (hereafter, MH-MOX) but normal PuO{sub 2} of European MOX fuel fabricators. Therefore, in order to evaluate the suitability of the MH-MOX powder for the MIMAS process, JNFL manufactured small scale test equipment, and implemented a powder mixing evaluation test up until JFY 2003. As a result, the suitability of the MH-MOX powder for the MIMAS process was positively evaluated and confirmed It was followed by a five-years test named an 'actual test' from JFY 2003 to JFY 2007, which aims at demonstrating good operation and maintenance of process equipment as well as obtaining good quality of MOX fuel pellets. (authors)

Osaka, Shuichi; Kurita, Ichiro; Deguchi, Morimoto [Japan Nuclear Fuel Ltd., 4-108, Aza okitsuke, oaza obuchi rokkasyo-mura, kamikita-gun, Aomori 039-3212 (Japan); Ito, Masanori [Japan Atomic Energy Agency, 4-33 Muramatu, Tokai-mura, Ibaraki 319-1194 (Japan); Goto, Masakazu [Nuclear Fuel Industries, Ltd., 14-10, Mita 3-chome, Minato-ku, Tokyo 108-0073 (Japan)

2007-07-01T23:59:59.000Z

6

Mixed Oxide (MOX) Fuel Fabrication Facility Construction Authorization Request Change Pages and Revised Response to AP-03 References:  

E-Print Network (OSTI)

Enclosed are change pages for Duke Cogema Stone & Webster's (DCS) request for authorization of construction of the Mixed Oxide (MOX) Fuel Fabrication Facility. The enclosed change pages replace pages in the Construction Authorization Request as updated through Reference 1. The enclosed change pages do not contain information which is considered to be proprietary to DCS. Enclosure 1 provides twenty-five copies of the change pages, which may be disclosed to the public. Enclosure 2 provides the page replacement instructions. The changed pages are the result of additional clarifications to Draft Safety Evaluation Report (DSER) Open Items. Also included as Enclosure 3 is the revised response for open item AP-3. IUmsso(1

Duke Cogema; Stone Webster; Duke Cogema Stone; Duke Cogema Stone; Andrew Persinko Usnrc/hq

2003-01-01T23:59:59.000Z

7

Irradiation behavior of High-Burnup LWR-MOX (mixed-oxide) Fuels  

Science Conference Proceedings (OSTI)

About this Abstract. Meeting, 2014 TMS Annual Meeting & Exhibition. Symposium , Radiation Effects in Oxide Ceramics and Novel LWR Fuels. Presentation Title ...

8

An improved characterization method for international accountancy measurements of fresh and irradiated mixed oxide (MOX) fuel: helping achieve continual monitoring and safeguards through the fuel cycle  

SciTech Connect

Nuclear fuel accountancy measurements are conducted at several points through the nuclear fuel cycle to ensure continuity of knowledge (CofK) of special nuclear material (SNM). Non-destructive assay (NDA) measurements are performed on fresh fuel (prior to irradiation in a reactor) and spent nuclear fuel (SNF) post-irradiation. We have developed a fuel assembly characterization system, based on the novel concept of 'neutron fingerprinting' with multiplicity signatures to ensure detailed CofK of nuclear fuel through the entire fuel cycle. The neutron fingerprint in this case is determined by the measurement of the various correlated neutron signatures, specific to fuel isotopic composition, and therefore offers greater sensitivity to variations in fissile content among fuel assemblies than other techniques such as gross neutron counting. This neutron fingerprint could be measured at the point of fuel dispatch (e.g. from a fuel fabrication plant prior to irradiation, or from a reactor site post-irradiation), monitored during transportation of the fuel assembly, and measured at a subsequent receiving site (e.g. at the reactor site prior to irradiation, or reprocessing facility post-irradiation); this would confirm that no unexpected changes to the fuel composition or amount have taken place during transportation and/or reactor operations. Changes may indicate an attempt to divert material for example. Here, we present the current state of the practice of fuel measurements for both fresh mixed oxide (MOX) fuel and SNF (both MOX and uranium dioxide). This is presented in the framework of international safeguards perspectives from the US and UK. We also postulate as to how the neutron fingerprinting concept could lead to improved fuel characterization (both fresh MOX and SNF) resulting in: (a) assured CofK of fuel across the nuclear fuel cycle, (b) improved detection of SNM diversion, and (c) greater confidence in safeguards of SNF transportation.

Evans, Louise G [Los Alamos National Laboratory; Croft, Stephen [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Tobin, S. J. [Los Alamos National Laboratory; Boyer, B. D. [Los Alamos National Laboratory; Menlove, H. O. [Los Alamos National Laboratory; Schear, M. A. [Los Alamos National Laboratory; Worrall, Andrew [U.K., NNL

2010-11-24T23:59:59.000Z

9

An improved characterization method for international accountancy measurements of fresh and irradiated mixed oxide (MOX) fuel: helping achieve continual monitoring and safeguards through the fuel cycle  

SciTech Connect

Nuclear fuel accountancy measurements are conducted at several points through the nuclear fuel cycle to ensure continuity of knowledge (CofK) of special nuclear material (SNM). Non-destructive assay (NDA) measurements are performed on fresh fuel (prior to irradiation in a reactor) and spent nuclear fuel (SNF) post-irradiation. We have developed a fuel assembly characterization system, based on the novel concept of 'neutron fingerprinting' with multiplicity signatures to ensure detailed CofK of nuclear fuel through the entire fuel cycle. The neutron fingerprint in this case is determined by the measurement of the various correlated neutron signatures, specific to fuel isotopic composition, and therefore offers greater sensitivity to variations in fissile content among fuel assemblies than other techniques such as gross neutron counting. This neutron fingerprint could be measured at the point of fuel dispatch (e.g. from a fuel fabrication plant prior to irradiation, or from a reactor site post-irradiation), monitored during transportation of the fuel assembly, and measured at a subsequent receiving site (e.g. at the reactor site prior to irradiation, or reprocessing facility post-irradiation); this would confirm that no unexpected changes to the fuel composition or amount have taken place during transportation and/ or reactor operations. Changes may indicate an attempt to divert material for example. Here, we present the current state of the practice of fuel measurements for both fresh mixed oxide (MOX) fuel and SNF (both MOX and uranium dioxide). This is presented in the framework of international safeguards perspectives from the US and UK. We also postulate as to how the neutron fingerprinting concept could lead to improved fuel characterization (both fresh MOX and SNF) resulting in: (a) assured CofK of fuel across the nuclear fuel cycle, (b) improved detection of SNM diversion, and (c) greater confidence in safeguards of SNF transportation.

Evans, Louise G [Los Alamos National Laboratory; Croft, Stephen [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Tobin, S. J. [Los Alamos National Laboratory; Menlove, H. O. [Los Alamos National Laboratory; Schear, M. A. [Los Alamos National Laboratory; Worrall, Andrew [U.K. NNL

2011-01-13T23:59:59.000Z

10

Economics of nuclear fuel cycles : option valuation and neutronics simulation of mixed oxide fuels  

E-Print Network (OSTI)

In most studies aiming at the economic assessment of nuclear fuel cycles, a primary concern is to keep scenarios economically comparable. For Uranium Oxide (UOX) and Mixed Oxide (MOX) fuels, a traditional way to achieve ...

De Roo, Guillaume

2009-01-01T23:59:59.000Z

11

Plutonium isotopic analysis of highly enriched mixed oxides  

SciTech Connect

We investigated the analysis method used by the International Atomic Energy Agency (IAEA) to determine the plutonium isotopic composition of highly enriched mixed oxides (MOX). The IAEA currently uses the Cicero multichannel analyzer and the IAEAPU algorithm for its analysis. In our investigation the plutonium isotopic measurements were found to be good for PuO/sub 2/ powder or low-enriched MOX, but acceptable for highly enriched MOX in IAEA special nuclear material (SNM) accountability applications. The gamma-ray interferences from /sup 235/U resulted in underestimation of the isotopic composition of /sup 239/Pu and overestimation of all other plutonium isotopes. Samples with high /sup 240/Pu content were found to have significantly higher error in plutonium isotopic analyses of highly enriched MOX. Code modifications or use of calibration curves are necessary for plutonium isotopic analyses of highly enriched MOX in IAEA SNM accountability applications.

Clement, S.D.; Augustson, R.H.

1986-08-01T23:59:59.000Z

12

Light water reactor mixed-oxide fuel irradiation experiment  

SciTech Connect

The United States Department of Energy Office of Fissile Materials Disposition is sponsoring and Oak Ridge National Laboratory (ORNL) is leading an irradiation experiment to test mixed uranium-plutonium oxide (MOX) fuel made from weapons-grade (WG) plutonium. In this multiyear program, sealed capsules containing MOX fuel pellets fabricated at Los Alamos National Laboratory (LANL) are being irradiated in the Advanced Test Reactor (ATR) at the Idaho National Engineering and Environmental Laboratory (INEEL). The planned experiments will investigate the utilization of dry-processed plutonium, the effects of WG plutonium isotopics on MOX performance, and any material interactions of gallium with Zircaloy cladding.

Hodge, S.A.; Cowell, B.S. [Oak Ridge National Lab., TN (United States); Chang, G.S.; Ryskamp, J.M. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.

1998-06-01T23:59:59.000Z

13

MOX Safety Fuels the Future  

E-Print Network (OSTI)

– Convert 34 metric tons of weapons-grade grade plutonium to mixed oxide (MOX) fuel for use in commercial power reactors • Positive Impact – Removes many warheads from the nuclear arsenal – Eliminates $500 million/year in security costs – Provides clean, carbon free energy that offsets over $21 billion in imported oil costs at $50/barrel

Walt Elliott; Cable Tray; Ap Reference Plant; La Hague

2007-01-01T23:59:59.000Z

14

Survey of Worldwide Light Water Reactor Experience with Mixed Uranium-Plutonium Oxide Fuel  

SciTech Connect

The US and the Former Soviet Union (FSU) have recently declared quantities of weapons materials, including weapons-grade (WG) plutonium, excess to strategic requirements. One of the leading candidates for the disposition of excess WG plutonium is irradiation in light water reactors (LWRs) as mixed uranium-plutonium oxide (MOX) fuel. A description of the MOX fuel fabrication techniques in worldwide use is presented. A comprehensive examination of the domestic MOX experience in US reactors obtained during the 1960s, 1970s, and early 1980s is also presented. This experience is described by manufacturer and is also categorized by the reactor facility that irradiated the MOX fuel. A limited summary of the international experience with MOX fuels is also presented. A review of MOX fuel and its performance is conducted in view of the special considerations associated with the disposition of WG plutonium. Based on the available information, it appears that adoption of foreign commercial MOX technology from one of the successful MOX fuel vendors will minimize the technical risks to the overall mission. The conclusion is made that the existing MOX fuel experience base suggests that disposition of excess weapons plutonium through irradiation in LWRs is a technically attractive option.

Cowell, B.S.; Fisher, S.E.

1999-02-01T23:59:59.000Z

15

MOX and MOX with 237Np/241Am Inert Fission Gas Generation Comparison in ATR  

Science Conference Proceedings (OSTI)

The treatment of spent fuel produced in nuclear power generation is one of the most important issues to both the nuclear community and the general public. One of the viable options to long-term geological disposal of spent fuel is to extract plutonium, minor actinides (MA), and potentially long-lived fission products from the spent fuel and transmute them into short-lived or stable radionuclides in currently operating light-water reactors (LWR), thus reducing the radiological toxicity of the nuclear waste stream. One of the challenges is to demonstrate that the burnup-dependent characteristic differences between Reactor-Grade Mixed Oxide (RG-MOX) fuel and RG-MOX fuel with MA Np-237 and Am 241 are minimal, particularly, the inert gas generation rate, such that the commercial MOX fuel experience base is applicable. Under the Advanced Fuel Cycle Initiative (AFCI), developmental fuel specimens in experimental assembly LWR-2 are being tested in the northwest (NW) I-24 irradiation position of the Advanced Test Reactor (ATR). The experiment uses MOX fuel test hardware, and contains capsules with MOX fuel consisting of mixed oxide manufactured fuel using reactor grade plutonium (RG-Pu) and mixed oxide manufactured fuel using RG-Pu with added Np/Am. This study will compare the fuel neutronics depletion characteristics of Case-1 RG-MOX and Case-2 RG-MOX with Np/Am.

G. S. Chang; M. Robel; W. J. Carmack; D. J. Utterbeck

2006-06-01T23:59:59.000Z

16

Licensing issues associated with the use of mixed-oxide fuel in US commercial nuclear reactors  

Science Conference Proceedings (OSTI)

On January 14, 1997, the Department of Energy, as part of its Record of Decision on the storage and disposition of surplus nuclear weapons materials, committed to pursue the use of excess weapons-usable plutonium in the fabrication of mixed-oxide (MOX) fuel for consumption in existing commercial nuclear power plants. Domestic use of MOX fuel has been deferred since the late 1970s, principally due to nuclear proliferation concerns. This report documents a review of past and present literature (i.e., correspondence, reports, etc.) on the domestic use of MOX fuel and provides discussion on the technical and regulatory issues that must be addressed by DOE (and the utility/consortia selected by DOE to effect the MOX fuel consumption strategy) in obtaining approval from the Nuclear Regulatory Commission to use MOX fuel in one or a group of existing commercial nuclear power plants.

Williams, D.L. Jr.

1997-04-01T23:59:59.000Z

17

Energy Secretary Bodman Commends Key Milestone In MOX Program | Department  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Commends Key Milestone In MOX Program Commends Key Milestone In MOX Program Energy Secretary Bodman Commends Key Milestone In MOX Program April 1, 2005 - 11:28am Addthis WASHINGTON, DC - In response to the Nuclear Regulatory Commission's (NRC) authorization of the construction of a U.S. Mixed-Oxide (MOX) Fuel Fabrication Facility at the Department of Energy's Savannah River Site in South Carolina, Secretary of Energy Samuel W. Bodman today released the following statement: "Issuing the permit for construction of a MOX facility in South Carolina is the crucial next step in the MOX program. It is a key milestone in our efforts to dispose of surplus weapons grade plutonium in the U.S. and Russia," Secretary Bodman said. "We look forward to proceeding with this nonproliferation program that will ultimately eliminate enough

18

Mixed oxide fuels testing in the advanced test reactor to support plutonium disposition  

Science Conference Proceedings (OSTI)

An intense worldwide effort is now under way to find means of reducing the stockpile of weapons-grade plutonium. One of the most attractive solutions would be to use WGPu as fuel in existing light water reactors (LWRs) in the form of mixed oxide (MOX) fuel - i.e., plutonia (PUO{sub 2}) mixed with urania (UO{sub 2}). Before U.S. reactors could be used for this purpose, their operating licenses would have to be amended. Numerous technical issues must be resolved before LWR operating licenses can be amended to allow the use of MOX fuel. These issues include the following: (1) MOX fuel fabrication process verification, (2) Whether and how to use burnable poisons to depress MOX fuel initial reactivity, which is higher than that of urania, (3) The effects of WGPu isotopic composition, (4) The feasibility of loading MOX fuel with plutonia content up to 7% by weight, (5) The effects of americium and gallium in WGPu, (6) Fission gas release from MOX fuel pellets made from WGPu, (7) Fuel/cladding gap closure, (8) The effects of power cycling and off-normal events on fuel integrity, (9) Development of radial distributions of burnup and fission products, (10) Power spiking near the interfaces of MOX and urania fuel assemblies, and (11) Fuel performance code validation. We have performed calculations to show that the use of hafnium shrouds can produce spectrum adjustments that will bring the flux spectrum in ATR test loops into a good approximation to the spectrum anticipated in a commercial LWR containing MOX fuel while allowing operation of the test fuel assemblies near their optimum values of linear heat generation rate. The ATR would be a nearly ideal test bed for developing data needed to support applications to license LWRs for operation with MOX fuel made from weapons-grade plutonium. The requirements for planning and implementing a test program in the ATR have been identified.

Ryskamp, J.M.; Sterbentz, J.W.; Chang, G.S. [and others

1995-09-01T23:59:59.000Z

19

Experience making mixed oxide fuel with plutonium from dismantled weapons  

Science Conference Proceedings (OSTI)

Mixed depleted UO{sub 2} and PuO{sub 2} (MOX) pellets prototypic of fuel proposed for use in commercial power reactors were made with plutonium recovered from dismantled weapons. We characterized plutonium dioxide powders that were produced at the Los Alamos and Lawrence Livermore National Laboratories (LANL and LLNL) using various methods to recover the plutonium from weapons parts and to convert It to oxide. The gallium content of the PUO{sub 2} prepared at LANL was the same as in the weapon alloy while the content of that prepared at LLNL was less. The MOX was prepared with a five weight percent plutonium content. We tested various MOX powders milling methods to improve homogeneity and found vibratory milling superior to ball milling. The sintering behavior of pellets made with the PuO{sub 2} from the two laboratories was similar. We evaluated the effects of gallium and of erbium and gadolinium, that are added to the MOX fuel as deplorable neutron absorbers, on the pellet fabrication process and an the sintered pellets. The gallium content of the sintered pellets was <10 ppm, suggesting that the gallium will not be an issue in the reactor, but that it will be an Issue in the operation of the fuel fabrication processing equipment unless it is removed from the PuO{sub 2} before it is blended with the UO{sub 2}.

Blair, H.T.; Ramsey, K.B.

1995-12-31T23:59:59.000Z

20

Probaability of Criticality for MOX SNF  

Science Conference Proceedings (OSTI)

The purpose of this calculation is to provide a conservative (upper bound) estimate of the probability of criticality for mixed oxide (MOX) spent nuclear fuel (SNF) of the Westinghouse pressurized water reactor (PWR) design that has been proposed for use. with the Plutonium Disposition Program (Ref. 1, p. 2). This calculation uses a Monte Carlo technique similar to that used for ordinary commercial SNF (Ref. 2, Sections 2 and 5.2). Several scenarios, covering a range of parameters, are evaluated for criticality. Parameters specifying the loss of fission products and iron oxide from the waste package are particularly important. This calculation is associated with disposal of MOX SNF.

P. Gottlieb

1999-09-28T23:59:59.000Z

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


21

The manufacture and performance of homogeneous microstructure SBR MOX fuel  

Science Conference Proceedings (OSTI)

In the early 1980's, British experience in the manufacture of mixed-oxide fast reactor fuel was used to develop a new thermal MOX manufacturing route called the Short Binder-less Route (SBR). Laboratory- scale development led to the manufacture of commercial PWR fuel in a small pilot plant, and the construction of the full-scale dual-line Sellafield MOX Plant (SMP). SMP's first MOX assemblies are now under irradiation. SBR MOX is manufactured with 100% co-milled feedstock, leading to a microstructure dominated by a solid solution of (U,Pu)O{sub 2} at the nominal enrichment. A comprehensive fuel performance research programme has demonstrated the benign performance of SBR MOX up to 54 MWd/kgHM. In particular, the homogeneous microstructure is believed to be instrumental in the favourable fission gas retention and PCI resistance properties. (authors)

Barker, Matthew A. [Nexia Solutions Ltd., British Technology Centre, Sellafield, CA20 1PG (United Kingdom); Stephenson, Keith; Weston, Rebecca [Sellafield Ltd., B582, Sellafield, CA20 1PG (United Kingdom)

2007-07-01T23:59:59.000Z

22

Safeguards and security considerations associated with the use of mixed-oxide fuel in U.S. commercial reactors  

Science Conference Proceedings (OSTI)

The US Department of Energy`s overall plutonium disposition strategy includes irradiation of mixed-oxide (MOX) fuel derived from surplus weapons-usable plutonium via domestic, commercial reactors. The storage, handling, and irradiation of weapons-usable plutonium-derived MOX fuel will increase the requirements for safeguards and security at commercial light-water reactor sites, which presently only use low-enriched uranium fuel. Applicable safeguards and security regulations and requirements for the reactor irradiation services portion of the project are discussed in this topical report. Requirements for the MOX fuel fabrication portion of the project are discussed in a separate report.

Ehinger, M.E. [Oak Ridge Y-12 Plant, TN (United States). National Security Program Office

1997-04-01T23:59:59.000Z

23

The Use of Staff Augmentation Subcontracts at the National Nuclear Security Administration's Mixed Oxide Fuel Fabrication Facility, IG-0887  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

The Use of Staff Augmentation The Use of Staff Augmentation Subcontracts at National Nuclear Security Administration's Mixed Oxide Fuel Fabrication Facility DOE/IG-0887 May 2013 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 May 15, 2013 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Audit Report on "The Use of Staff Augmentation Subcontracts at the National Nuclear Security Administration's Mixed Oxide Fuel Fabrication Facility" BACKGROUND Shaw AREVA MOX Services, LLC (MOX Services) is responsible for the design and construction of the National Nuclear Security Administration's (NNSA) nearly $5 billion Mixed

24

Theory of Antineutrino Monitoring of Burning MOX Plutonium Fuels  

E-Print Network (OSTI)

This letter presents the physics and feasibility of reactor antineutrino monitoring to verify the burnup of plutonium loaded in the reactor as a Mixed Oxide (MOX) fuel. It examines the magnitude and temporal variation in the antineutrino signals expected for different MOX fuels, for the purposes of nuclear accountability and safeguards. The antineutrino signals from reactor-grade and weapons-grade MOX are shown to be distinct from those from burning low enriched uranium. Thus, antineutrino monitoring could be used to verify the destruction of plutonium in reactors, though verifying the grade of the plutonium being burned is found to be more challenging.

Hayes, A C; Nieto, Michael Martin; WIlson, W B

2011-01-01T23:59:59.000Z

25

Theory of Antineutrino Monitoring of Burning MOX Plutonium Fuels  

E-Print Network (OSTI)

This letter presents the physics and feasibility of reactor antineutrino monitoring to verify the burnup of plutonium loaded in the reactor as a Mixed Oxide (MOX) fuel. It examines the magnitude and temporal variation in the antineutrino signals expected for different MOX fuels, for the purposes of nuclear accountability and safeguards. The antineutrino signals from reactor-grade and weapons-grade MOX are shown to be distinct from those from burning low enriched uranium. Thus, antineutrino monitoring could be used to verify the destruction of plutonium in reactors, though verifying the grade of the plutonium being burned is found to be more challenging.

A. C. Hayes; H. R. Trellue; Michael Martin Nieto; W. B. WIlson

2011-10-03T23:59:59.000Z

26

MIXED-OXIDE FUEL USE IN COMMERCIAL LIGHT WATER REACTORS  

E-Print Network (OSTI)

In a Commission briefing on high-bumup fuel on March 25, 1997, the staff said that they would prepare a white paper on mixed-oxide (MOX) fuel in anticipation of a DOE program to bum excess weapons plutonium in commercial reactors. This memorandum and its attachment comprise that paper and are provided to inform the Commissioners of technical issues associated with such a program. More recently, on February 5, 1999, I was contacted by the Nuclear Control Institute regarding a paper they have written on this subject. They presented that paper to the staff in a public meeting on April 7, 1999. The Nuclear Control Institute's written paper had been provided to the staff earlier, and we have taken the paper into consideration in preparing this memorandum. Back-ground In January 1997, the U.S. Department of Energy released a record of decision for the storage and disposition of weapons-usable fissile materials. In this record, DOE recommended that excess weapons-grade plutonium be disposed of by two methods: (1) reconstituting the plutonium into mixed-oxide (MOX) fuel rods and burning it in current light water reactors, and (2) immobilizing the plutonium in glass logs with appropriate radioactive isotopes to deter theft prior to geologic disposal. Based on current information, it now appears that, if the MOX fuel method is utilized, fuel fabrication will take place at the Savannah River site in South Carolina with burning in nearby Westinghouse-type PWRs. Although DOE will probably not receive funding in FY 2000 for developing a license application, Congress has already given its approval for NRC licensing authority over a MOX fuel fabrication facility operated under

United States; William D. Travers

1999-01-01T23:59:59.000Z

27

Risk analysis of shipping plutonium pits and mixed oxide fuel  

E-Print Network (OSTI)

With the end of the cold war, there no longer seems to be a credible threat of war between nuclear superpowers, with its possible consequence of billions of fatalities. However, the residue of the cold war, most notably the now excess weapons plutonium, has been identified as the source of a number of potential catastrophes. For example, just a single crude nuclear weapon in the hands of a terrorist organization or rogue state and detonated in even a medium-sized city could lead to hundreds of thousands of deaths. For this reason, the ultimate disposition of this excess plutonium has been identified as a national priority. The process of carrying out this disposition itself carries some risks, and even though any conceivable consequences clearly will be much smaller in magnitude than those cited above, U.S. federal law (the National Environmental Protection Act) mandates that such risks must be analyzed. The ability to carry out one type of such an analysis is demonstrated in this thesis. Specifically, one possible option that has been identified for disposition of excess U.S. weapons plutonium is the transformation into mixed oxide (MOX) fuel, that then would be used as fuel in a commercial nuclear power plant. Any such process will involve the transportation of the MOX fuel from the MOX fuel fabrication facility to the nuclear power plant, and possibly transportation of the plutonium from a storage site to the fuel fabrication facility. This thesis is intended to demonstrate the capability to analyze the risks associated with such transportation campaigns. The primary tool used for these analyses was RADTRAN, a code developed by Sandia National Laboratories for evaluating risk associated with the transportation of radioactive materials. Two sample scenarios were explored relative to the transformation of plutonium pits to MOX fuel. First, the pits would be converted to MOX fuel at a fuel fabrication facility located either at the Pantex Plant or the Savannah River Site (SRS), and then the MOX fuel would be ultimately shipped to a final destination of a commercial power plant, the Palo Verde Generating Station in Arizona. For the scenario of placing the MOX fuel fabrication facility at SRS, pits would need to be shipped from Pantex to SRS and then the MOX fuel would be shipped to Palo Verde. The total number of expected fatalities over a 25 year campaign duration for this scenario would be 1.06, with 0. 1 73 fatalities resulting from latent cancer fatalities due to radiation exposure and 0.89 resulting from traffic accidents. For the placement of the MOX fuel fabrication facility at Pantex, only the MOX fuel would need to be transported from one facility to another, in this case from Pantex to Palo Verde. The total fatalities for this scenario over 25 years would be 0.413, resulting from 5.29 x 10-2 latent cancer fatalities and 0.36 traffic accident fatalities. The maximum exposed individual along any of the three routes would receive 1.0 X 10-5 rem per year or 0.25 mrem over 25 years.

Caldwell, Amy Baker

1997-01-01T23:59:59.000Z

28

Mox fuel arrangement for nuclear core  

DOE Patents (OSTI)

In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion. characteristics of the assembly.

Kantrowitz, Mark L. (Portland, CT); Rosenstein, Richard G. (Windsor, CT)

2001-05-15T23:59:59.000Z

29

MOX fuel arrangement for nuclear core  

DOE Patents (OSTI)

In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly. 38 figs.

Kantrowitz, M.L.; Rosenstein, R.G.

1998-10-13T23:59:59.000Z

30

MOX fuel arrangement for nuclear core  

DOE Patents (OSTI)

In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly.

Kantrowitz, Mark L. (Portland, CT); Rosenstein, Richard G. (Windsor, CT)

1998-01-01T23:59:59.000Z

31

MOX fuel arrangement for nuclear core  

DOE Patents (OSTI)

In order to use up a stockpile of weapons-grade plutonium, the plutonium is converted into a mixed oxide (MOX) fuel form wherein it can be disposed in a plurality of different fuel assembly types. Depending on the equilibrium cycle that is required, a predetermined number of one or more of the fuel assembly types are selected and arranged in the core of the reactor in accordance with a selected loading schedule. Each of the fuel assemblies is designed to produce different combustion characteristics whereby the appropriate selection and disposition in the core enables the resulting equilibrium cycle to closely resemble that which is produced using urania fuel. The arrangement of the MOX rods and burnable absorber rods within each of the fuel assemblies, in combination with a selective control of the amount of plutonium which is contained in each of the MOX rods, is used to tailor the combustion characteristics of the assembly.

Kantrowitz, Mark L. (Portland, CT); Rosenstein, Richard G. (Windsor, CT)

2001-07-17T23:59:59.000Z

32

MOX Cross-Section Libraries for ORIGEN-ARP  

Science Conference Proceedings (OSTI)

The use of mixed-oxide (MOX) fuel in commercial nuclear power reactors operated in Europe has expanded rapidly over the past decade. The predicted characteristics of MOX fuel such as the nuclide inventories, thermal power from decay heat, and radiation sources are required for design and safety evaluations, and can provide valuable information for non-destructive safeguards verification activities. This report describes the development of computational methods and cross-section libraries suitable for the analysis of irradiated MOX fuel with the widely-used and recognized ORIGEN-ARP isotope generation and depletion code of the SCALE (Standardized Computer Analyses for Licensing Evaluation) code system. The MOX libraries are designed to be used with the Automatic Rapid Processing (ARP) module of SCALE that interpolates appropriate values of the cross sections from a database of parameterized cross-section libraries to create a problem-dependent library for the burnup analysis. The methods in ORIGEN-ARP, originally designed for uranium-based fuels only, have been significantly upgraded to handle the larger number of interpolation parameters associated with MOX fuels. The new methods have been incorporated in a new version of the ARP code that can generate libraries for low-enriched uranium (LEU) and MOX fuel types. The MOX data libraries and interpolation algorithms in ORIGEN-ARP have been verified using a database of declared isotopic concentrations for 1042 European MOX fuel assemblies. The methods and data are validated using a numerical MOX fuel benchmark established by the Organization for Economic Cooperation and Development (OECD) Working Group on burnup credit and nuclide assay measurements for irradiated MOX fuel performed as part of the Belgonucleaire ARIANE International Program.

Gauld, I.C.

2003-07-01T23:59:59.000Z

33

Safety issues in fabricating mixed oxide fuel using surplus weapons plutonium  

SciTech Connect

This paper presents an assessment of the safety issues and implications of fabricating mixed oxide (MOX) fuel using surplus weapons plutonium. The basis for this assessment is the research done at Los Alamos National Laboratory (LANL) in identifying and resolving the technical issues surrounding the production of PuO{sub 2} feed, removal of gallium from the PuO{sub 2} feed, the fabrication of test fuel, and the work done at the LANL plutonium processing facility. The use of plutonium in MOX fuel has been successfully demonstrated in Europe, where the experience has been almost exclusively with plutonium separated from commercial spent nuclear fuel. This experience in safely operating MOX fuel fabrication facilities directly applies to the fabrication and irradiation of MOX fuel made from surplus weapons plutonium. Consequently, this paper focuses on the technical difference between plutonium from surplus weapons, and light-water reactor recycled plutonium. Preliminary assessments and research lead to the conclusion that no new process or product safety concerns will arise from using surplus weapons plutonium in MOX fuel.

Buksa, J.; Badwan, F.; Barr, M.; Motley, F.

1998-07-01T23:59:59.000Z

34

Los Alamos National Laboratory summary plan to fabricate mixed oxide lead assemblies for the fissile material disposition program  

Science Conference Proceedings (OSTI)

This report summarizes an approach for using existing Los Alamos National Laboratory (Laboratory) mixed oxide (MOX) fuel-fabrication and plutonium processing capabilities to expedite and assure progress in the MOX/Reactor Plutonium Disposition Program. Lead Assembly MOX fabrication is required to provide prototypic fuel for testing in support of fuel qualification and licensing requirements. It is also required to provide a bridge for the full utilization of the European fabrication experience. In part, this bridge helps establish, for the first time since the early 1980s, a US experience base for meeting the safety, licensing, safeguards, security, and materials control and accountability requirements of the Department of Energy and Nuclear Regulatory Commission. In addition, a link is needed between the current research and development program and the production of disposition mission fuel. This link would also help provide a knowledge base for US regulators. Early MOX fabrication and irradiation testing in commercial nuclear reactors would provide a positive demonstration to Russia (and to potential vendors, designers, fabricators, and utilities) that the US has serious intent to proceed with plutonium disposition. This report summarizes an approach to fabricating lead assembly MOX fuel using the existing MOX fuel-fabrication infrastructure at the Laboratory.

Buksa, J.J.; Eaton, S.L.; Trellue, H.R.; Chidester, K.; Bowidowicz, M.; Morley, R.A.; Barr, M.

1997-12-01T23:59:59.000Z

35

Test plan for the Parallex CANDU-MOX irradiation  

Science Conference Proceedings (OSTI)

One of several options being considered by the United States and the Russian Federation for the disposition of excess plutonium from dismantled weapons is to convert it to mixed-oxide (MOX) fuel for use in Canadian uranium-deuterium (CANDU) reactors. This report describes an irradiation test demonstrating the feasibility of this concept with laboratory quantities of MOX fuel placed in the pressurized loops of the National Research Universal test reactor at the Atomic Energy of Canada, Ltd., Chalk River Laboratories. The objective of the Parallex (for parallel experiment) test is to simultaneously test laboratory-produced quantities of US and R.F. MOX fuel in a test reactor under heat generation rates representing those expected in the CANDU reactors. The MOX fuel will be produced with plutonium from disassembled weapons at the Los Alamos National Laboratory in the United States and at the Bochvar Institute in the Russian Federation. Thus, the test will serve to demonstrate the accomplishment of many parts of the disposition mission: disassembly of weapons, conversion of the plutonium to oxide, fabrication of MOX fuel, assembly of fuel elements and bundles, shipment to a reactor, irradiation, and finally, storage of the spent fuel elements awaiting eventual disposition in a geologic repository in Canada.

Copeland, G.L.

1997-06-01T23:59:59.000Z

36

Issues in the use of Weapons-Grade MOX Fuel in VVER-1000 Nuclear Reactors: Comparison of UO2 and MOX Fuels  

Science Conference Proceedings (OSTI)

The purpose of this report is to quantify the differences between mixed oxide (MOX) and low-enriched uranium (LEU) fuels and to assess in reasonable detail the potential impacts of MOX fuel use in VVER-1000 nuclear power plants in Russia. This report is a generic tool to assist in the identification of plant modifications that may be required to accommodate receiving, storing, handling, irradiating, and disposing of MOX fuel in VVER-1000 reactors. The report is based on information from work performed by Russian and U.S. institutions. The report quantifies each issue, and the differences between LEU and MOX fuels are described as accurately as possible, given the current sources of data.

Carbajo, J.J.

2005-05-27T23:59:59.000Z

37

Plutonium Consumption Program, CANDU Reactor Project: Feasibility of BNFP Site as MOX Fuel Supply Facility. Final report  

SciTech Connect

An evaluation was made of the technical feasibility, cost, and schedule for converting the existing unused Barnwell Nuclear Fuel Facility (BNFP) into a Mixed Oxide (MOX) CANDU fuel fabrication plant for disposition of excess weapons plutonium. This MOX fuel would be transported to Ontario where it would generate electricity in the Bruce CANDU reactors. Because CANDU MOX fuel operates at lower thermal load than natural uranium fuel, the MOX program can be licensed by AECB within 4.5 years, and actual Pu disposition in the Bruce reactors can begin in 2001. Ontario Hydro will have to be involved in the entire program. Cost is compared between BNFP and FMEF at Hanford for converting to a CANDU MOX facility.

1995-06-30T23:59:59.000Z

38

Studies of Flexible MOX/LEU Fuel Cycles  

Science Conference Proceedings (OSTI)

This project was a collaborative effort involving researchers from Oak Ridge National Laboratory and North Carolina State University as well as Texas A and M University. The background, briefly, is that the US is planning to use some of its excess weapons Plutonium (Pu) to make mixed-oxide (MOX) fuel for existing light-water reactors (LWRs). Considerable effort has already gone into designing fuel assemblies and core loading patterns for the transition from full-uranium cores to partial-MOX and full-MOX cores. However, these designs have assumed that any time a reactor needs MOX assemblies, these assemblies will be supplied. In reality there are many possible scenarios under which this supply could be disrupted. It therefore seems prudent to verify that a reactor-based Pu-disposition program could tolerate such interruptions in an acceptable manner. Such verification was the overall aim of this project. The task assigned to the Texas A and M team was to use the HELIOS code to develop libraries of two-group homogenized cross sections for the various assembly designs that might be used in a Westinghouse Pressurized Water Reactor (PWR) that is burning weapons-grade MOX fuel. The NCSU team used these cross sections to develop optimized loading patterns under several assumed scenarios. Their results are documented in a companion report.

Adams, M.L.; Alonso-Vargas, G.

1999-03-01T23:59:59.000Z

39

Hot Cell Examination of Weapons-Grade MOX Fuel  

SciTech Connect

The U.S. Department of Energy has decided to dispose of a portion of the nation s surplus weapons-grade plutonium by reconstituting it into mixed oxide (MOX) fuel and irradiating it in commercial power reactors. Four lead assemblies were manufactured with weapons-grade MOX and irradiated to a maximum fuel rod burnup of 47.3 MWd/kg. As part of the fuel qualification process, five fuel rods with varying burnups and plutonium contents were selected from one of the assemblies and shipped to Oak Ridge National Laboratory for hot cell examination. This is the first hot cell examination of weapons-grade MOX fuel. The rods have been examined nondestructively with the ADEPT apparatus and are currently being destructively examined. Examinations completed to date include length measurements, visual examination, gamma scanning, profilometry, eddy-current testing, gas measurement and analysis, and optical metallography. Representative results of these examinations are reviewed and found to be consistent with predictions and with prior experience with reactor-grade MOX fuel. The results will be used to support licensing of weapons-grade MOX for batch use in commercial power reactors.

Morris, Robert Noel [ORNL; Bevard, Bruce Balkcom [ORNL; McCoy, Kevin [Areva NP

2010-01-01T23:59:59.000Z

40

APPLICATION OF COLUMN EXTRACTION METHOD FOR IMPURITIES ANALYSIS ON HB-LINE PLUTONIUM OXIDE IN SUPPORT OF MOX FEED PRODUCT SPECIFICATIONS  

SciTech Connect

The current mission at H-Canyon involves the dissolution of an Alternate Feedstocks 2 (AFS-2) inventory that contains plutonium metal. Once dissolved, HB-Line is tasked with purifying the plutonium solution via anion exchange, precipitating the Pu as oxalate, and calcining to form plutonium oxide (PuO{sub 2}). The PuO{sub 2} will provide feed product for the Mixed Oxide (MOX) Fuel Fabrication Facility, and the anion exchange raffinate will be transferred to H-Canyon. The results presented in this report document the potential success of the RE resin column extraction application on highly concentrated Pu samples to meet MOX feed product specifications. The original 'Hearts Cut' sample required a 10000x dilution to limit instrument drift on the ICP-MS method. The instrument dilution factors improved to 125x and 250x for the sample raffinate and sample eluent, respectively. As noted in the introduction, the significantly lower dilutions help to drop the total MRL for the analyte. Although the spike recoveries were half of expected in the eluent for several key elements, they were between 94-98% after Nd tracer correction. It is seen that the lower ICD limit requirements for the rare earths are attainable because of less dilution. Especially important is the extremely low Ga limit at 0.12 {mu}g/g Pu; an ICP-MS method is now available to accomplish this task on the sample raffinate. While B and V meet the column A limits, further development is needed to meet the column B limits. Even though V remained on the RE resin column, an analysis method is ready for investigation on the ICP-MS, but it does not mean that V cannot be measured on the ICP-ES at a low dilution to meet the column B limits. Furthermore, this column method can be applicable for ICP-ES as shown in Table 3-2, in that it trims the sample of Pu, decreasing and sometimes eliminating Pu spectral interferences.

Jones, M.; Diprete, D.; Wiedenman, B.

2012-03-20T23:59:59.000Z

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


41

Neutron Emission Characteristics of Two Mixed-Oxide Fuels: Simulations and Initial Experiments  

Science Conference Proceedings (OSTI)

Simulations and experiments have been carried out to investigate the neutron emission characteristics of two mixed-oxide (MOX) fuels at Idaho National Laboratory (INL). These activities are part of a project studying advanced instrumentation techniques in support of the U.S. Department of Energy's Fuel Cycle Research and Development program and it's Materials Protection, Accounting, and Control for Transmutation (MPACT) campaign. This analysis used the MCNP-PoliMi Monte Carlo simulation tool to determine the relative strength and energy spectra of the different neutron source terms within these fuels, and then used this data to simulate the detection and measurement of these emissions using an array of liquid scintillator neutron spectrometers. These calculations accounted for neutrons generated from the spontaneous fission of the actinides in the MOX fuel as well as neutrons created via (alpha,n) reactions with oxygen in the MOX fuel. The analysis was carried out to allow for characterization of both neutron energy as well as neutron coincidences between multiple detectors. Coincidences between prompt gamma rays and neutrons were also analyzed. Experiments were performed at INL with the same materials used in the simulations to benchmark and begin validation tests of the simulations. Data was collected in these experiments using an array of four liquid scintillators and a high-speed waveform digitizer. Advanced digital pulse-shape discrimination algorithms were developed and used to collect this data. Results of the simulation and modeling studies are presented together with preliminary results from the experimental campaign.

D. L. Chichester; S. A. Pozzi; J. L. Dolan; M. Flaska; J. T. Johnson; E. H. Seabury; E. M. Gantz

2009-07-01T23:59:59.000Z

42

Radiation Effects in Oxide Ceramics and Novel LWR Fuels  

Science Conference Proceedings (OSTI)

Nuclear fuels, such as uranium dioxide (UO2) and Mixed Oxide (MOX) fuels, have been used in current light water reactors (LWRs) to produce about 15% of the ... of oxide ceramics for nuclear applications through experiment, theory and ...

43

Decay Heat Calculations for PWR and BWR Assemblies Fueled with Uranium and Plutonium Mixed Oxide Fuel using SCALE  

Science Conference Proceedings (OSTI)

In currently operating commercial nuclear power plants (NPP), there are two main types of nuclear fuel, low enriched uranium (LEU) fuel, and mixed-oxide uranium-plutonium (MOX) fuel. The LEU fuel is made of pure uranium dioxide (UO{sub 2} or UOX) and has been the fuel of choice in commercial light water reactors (LWRs) for a number of years. Naturally occurring uranium contains a mixture of different uranium isotopes, primarily, {sup 235}U and {sup 238}U. {sup 235}U is a fissile isotope, and will readily undergo a fission reaction upon interaction with a thermal neutron. {sup 235}U has an isotopic concentration of 0.71% in naturally occurring uranium. For most reactors to maintain a fission chain reaction, the natural isotopic concentration of {sup 235}U must be increased (enriched) to a level greater than 0.71%. Modern nuclear reactor fuel assemblies contain a number of fuel pins potentially having different {sup 235}U enrichments varying from {approx}2.0% to {approx}5% enriched in {sup 235}U. Currently in the United States (US), all commercial nuclear power plants use UO{sub 2} fuel. In the rest of the world, UO{sub 2} fuel is still commonly used, but MOX fuel is also used in a number of reactors. MOX fuel contains a mixture of both UO{sub 2} and PuO{sub 2}. Because the plutonium provides the fissile content of the fuel, the uranium used in MOX is either natural or depleted uranium. PuO{sub 2} is added to effectively replace the fissile content of {sup 235}U so that the level of fissile content is sufficiently high to maintain the chain reaction in an LWR. Both reactor-grade and weapons-grade plutonium contains a number of fissile and non-fissile plutonium isotopes, with the fraction of fissile and non-fissile plutonium isotopes being dependent on the source of the plutonium. While only RG plutonium is currently used in MOX, there is the possibility that WG plutonium from dismantled weapons will be used to make MOX for use in US reactors. Reactor-grade plutonium in MOX fuel is generally obtained from reprocessed irradiated nuclear fuel, whereas weapons-grade plutonium is obtained from decommissioned nuclear weapons material and thus has a different plutonium (and other actinides) concentration. Using MOX fuel instead of UOX fuel has potential impacts on the neutronic performance of the nuclear fuel and the design of the nuclear fuel must take these differences into account. Each of the plutonium sources (RG and WG) has different implications on the neutronic behavior of the fuel because each contains a different blend of plutonium nuclides. The amount of heat and the number of neutrons produced from fission of plutonium nuclides is different from fission of {sup 235}U. These differences in UOX and MOX do not end at discharge of the fuel from the reactor core - the short- and long-term storage of MOX fuel may have different requirements than UOX fuel because of the different discharged fuel decay heat characteristics. The research documented in this report compares MOX and UOX fuel during storage and disposal of the fuel by comparing decay heat rates for typical pressurized water reactor (PWR) and boiling water reactor (BWR) fuel assemblies with and without weapons-grade (WG) and reactor-grade (RG) MOX fuel.

Ade, Brian J [ORNL; Gauld, Ian C [ORNL

2011-10-01T23:59:59.000Z

44

ANALYSIS AND EXAMINATION OF MOX FUEL FROM NONPROLIFERATION PROGRAMS  

SciTech Connect

The U.S. Department of Energy has decided to dispose of a portion of the nation s surplus plutonium by reconstituting it into mixed oxide (MOX) fuel and irradiating it in commercial power reactors. Four lead assemblies were manufactured and irradiated to a maximum fuel rod burnup of 47.3 MWd/kg heavy metal. This was the first commercial irradiation of MOX fuel with a 240Pu/239Pu ratio of less than 0.10. Five fuel rods with varying burnups and plutonium contents were selected from one of the assemblies and shipped to Oak Ridge National Laboratory for hot cell examination. The performance of the rods was analyzed with AREVA s next-generation GALILEO code. The results of the analysis confirmed that the fuel rods had performed safely and predictably, and that GALILEO is applicable to MOX fuel with a low 240Pu/239Pu ratio as well as to standard MOX. The results are presented and compared to the GALILEO database. In addition, the fuel cladding was tested to confirm that traces of gallium in the fuel pellets had not affected the mechanical properties of the cladding. The irradiated cladding was found to remain ductile at both room temperature and 350 C for both the axial and circumferential directions.

McCoy, Kevin [Areva NP; Machut, Dr McLean [Areva NP; Morris, Robert Noel [ORNL; Blanpain, Patrick [AREVA NP SAS; Hemrick, James Gordon [ORNL

2013-01-01T23:59:59.000Z

45

Benchmark of SCALE (SAS2H) isotopic predictions of depletion analyses for San Onofre PWR MOX fuel  

Science Conference Proceedings (OSTI)

The isotopic composition of mixed-oxide (MOX) fuel, fabricated with both uranium and plutonium, after discharge from reactors is of significant interest to the Fissile Materials Disposition Program. The validation of the SCALE (SAS2H) depletion code for use in the prediction of isotopic compositions of MOX fuel, similar to previous validation studies on uranium-only fueled reactors, has corresponding significance. The EEI-Westinghouse Plutonium Recycle Demonstration Program examined the use of MOX fuel in the San Onofre PWR, Unit 1, during cycles 2 and 3. Isotopic analyses of the MOX spent fuel were conducted on 13 actinides and {sup 148}Nd by either mass or alpha spectrometry. Six fuel pellet samples were taken from four different fuel pins of an irradiated MOX assembly. The measured actinide inventories from those samples has been used to benchmark SAS2H for MOX fuel applications. The average percentage differences in the code results compared with the measurement were {minus}0.9% for {sup 235}U and 5.2% for {sup 239}Pu. The differences for most of the isotopes were significantly larger than in the cases for uranium-only fueled reactors. In general, comparisons of code results with alpha spectrometer data had extreme differences, although the differences in the calculations compared with mass spectrometer analyses were not extremely larger than that of uranium-only fueled reactors. This benchmark study should be useful in estimating uncertainties of inventory, criticality and dose calculations of MOX spent fuel.

Hermann, O.W.

2000-02-01T23:59:59.000Z

46

Mixed oxide nanoparticles and method of making  

DOE Green Energy (OSTI)

Methods and apparatus for producing mixed oxide nanoparticulates are disclosed. Selected thermophilic bacteria cultured with suitable reducible metals in the presence of an electron donor may be cultured under conditions that reduce at least one metal to form a doped crystal or mixed oxide composition. The bacteria will form nanoparticles outside the cell, allowing easy recovery. Selection of metals depends on the redox potentials of the reducing agents added to the culture. Typically hydrogen or glucose are used as electron donors.

Lauf, Robert J. (Oak Ridge, TN); Phelps, Tommy J. (Knoxville, TN); Zhang, Chuanlun (Columbia, MO); Roh, Yul (Oak Ridge, TN)

2002-09-03T23:59:59.000Z

47

LLNL MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of Fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. LLNL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within a Category 1 area. Building 332 will be used to receive and store the bulk PuO{sub 2} powder, fabricate MOX fuel pellets, and assemble fuel rods. Building 334 will be used to assemble, store, and ship fuel bundles. Only minor modifications would be required of Building 332. Uncontaminated glove boxes would need to be removed, petition walls would need to be removed, and minor modifications to the ventilation system would be required.

O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

1998-08-01T23:59:59.000Z

48

Transmutation of Transuranic Elements in Advanced MOX and IMF Fuel Assemblies Utilizing Multi-recycling Strategies  

E-Print Network (OSTI)

The accumulation of spent nuclear fuel may be hindering the expansion of nuclear electricity production. However, the reprocessing and recycling of spent fuel may reduce its volume and environmental burden. Although fast spectrum reactors are the preferred modality for transuranic element transmutation, such fast spectrum systems are in very short supply. It is therefore legitimate to investigate the recycling potential of thermal spectrum systems, which constitute the overwhelming majority of nuclear power plants worldwide. To do so efficiently, several new fuel assembly designs are proposed in this Thesis: these include (1) Mixed Oxide Fuel (MOX), (2) MOX fuel with Americium coating, (3) Inert-Matrix Fuel (IMF) with UOX as inner zone, and (4) IMF with MOX as inner zone. All these designs are investigated in a multi-recycling strategy, whereby the spent fuel from a given generation is re-used for the next generation. The accumulation of spent nuclear fuel may be hindering the expansion of nuclear electricity production. However, the reprocessing and recycling of spent fuel may reduce its volume and environmental burden. Although fast spectrum reactors are the preferred modality for transuranic element transmutation, such fast spectrum systems are in very short supply. It is therefore legitimate to investigate the recycling potential of thermal spectrum systems, which constitute the overwhelming majority of nuclear power plants worldwide. To do so efficiently, several new fuel assembly designs are proposed in this Thesis: these include (1) Mixed Oxide Fuel (MOX), (2) MOX fuel with Americium coating, (3) Inert-Matrix Fuel (IMF) with UOX as inner zone, and (4) IMF with MOX as inner zone. All these designs are investigated in a multi-recycling strategy, whereby the spent fuel from a given generation is re-used for the next generation.

Zhang, Yunhuang

2009-12-01T23:59:59.000Z

49

MOX Lead Assembly Fabrication at the Savannah River Site  

SciTech Connect

The U. S. Department of Energy (DOE) announced its intent to prepare an Environmental Impact Statement (EIS) under the National Environmental Policy Act (NEPA) on the disposition of the nations weapon-usable surplus plutonium.This EIS is tiered from the Storage and Disposition of Weapons-Usable Fissile Material Programmatic Environmental Impact Statement issued in December 1996,and the associated Record of Decision issued on January, 1997. The EIS will examine reasonable alternatives and potential environmental impacts for the proposed siting, construction, and operation of three types of facilities for plutonium disposition. The three types of facilities are: a pit disassembly and conversion facility, a facility to immobilize surplus plutonium in a glass or ceramic form for disposition, and a facility to fabricate plutonium oxide into mixed oxide (MOX) fuel.As an integral part of the surplus plutonium program, Oak Ridge National Laboratory (ORNL) was tasked by the DOE Office of Fissile Material Disposition(MD) as the technical lead to organize and evaluate existing facilities in the DOE complex which may meet MD`s need for a domestic MOX fuel fabrication demonstration facility. The Lead Assembly (LA) facility is to produce 1 MT of usable test fuel per year for three years. The Savannah River Site (SRS) as the only operating plutonium processing site in the DOE complex, proposes two options to carry out the fabrication of MOX fuel lead test assemblies: an all Category I facility option and a combined Category I and non-Category I facilities option.

Geddes, R.L. [Westinghouse Savannah River Company, AIKEN, SC (United States); Spiker, D.L.; Poon, A.P.

1997-12-01T23:59:59.000Z

50

Evaluation of Co-precipitation Processes for the Synthesis of Mixed-Oxide Fuel Feedstock Materials  

SciTech Connect

The focus of this report is the evaluation of various co-precipitation processes for use in the synthesis of mixed oxide feedstock powders for the Ceramic Fuels Technology Area within the Fuels Cycle R&D (FCR&D) Program's Advanced Fuels Campaign. The evaluation will include a comparison with standard mechanical mixing of dry powders and as well as other co-conversion methods. The end result will be the down selection of a preferred sequence of co-precipitation process for the preparation of nuclear fuel feedstock materials to be used for comparison with other feedstock preparation methods. A review of the literature was done to identify potential nitrate-to-oxide co-conversion processes which have been applied to mixtures of uranium and plutonium to achieve recycle fuel homogeneity. Recent studies have begun to study the options for co-converting all of the plutonium and neptunium recovered from used nuclear fuels, together with appropriate portions of recovered uranium to produce the desired mixed oxide recycle fuel. The addition of recycled uranium will help reduce the safeguard attractiveness level and improve proliferation resistance of the recycled fuel. The inclusion of neptunium is primarily driven by its chemical similarity to plutonium, thus enabling a simple quick path to recycle. For recycle fuel to thermal-spectrum light water reactors (LWRs), the uranium concentration can be {approx}90% (wt.), and for fast spectrum reactors, the uranium concentration can typically exceed 70% (wt.). However, some of the co-conversion/recycle fuel fabrication processes being developed utilize a two-step process to reach the desired uranium concentration. In these processes, a 50-50 'master-mix' MOX powder is produced by the co-conversion process, and the uranium concentration is adjusted to the desired level for MOX fuel recycle by powder blending (milling) the 'master-mix' with depleted uranium oxide. In general, parameters that must be controlled for co-precipitation processes include (1) feed solution concentration adjustment, (2) precipitant concentration and addition methods, (3) pH, temperature, mixing method and time, (4) valence adjustment, (5) solid precipitate separation from the filtrate 'mother liquor,' generally by means of centrifugation or filtration, and (6) temperatures and times for drying, calcination, and reduction of the MOX product powder. Also a recovery step is necessary because of low, but finite solubility of the U/TRU metals in the mother liquor. The recovery step usually involves destruction of the residual precipitant and disposal of by-product wastes. Direct denitrations of U/TRU require fewer steps, but must utilize various methods to enable production of MOX with product characteristics that are acceptable for recycle fuel fabrication. The three co-precipitation processes considered for evaluation are (1) the ammonia co-precipitation process being developed in Russia, (2) the oxalate co-precipitation process, being developed in France, and (3) the ammonium-uranyl-plutonyl-carbonate (AUPuC) process being developed in Germany. Two direct denitration processes are presented for comparison: (1) the 'Microwave Heating (MH)' automated multi-batch process developed in Japan and (2) the 'Modified Direct Denitration (MDD)' continuous process being developed in the USA. Brief comparative descriptions of the U/TRU co-conversion processes are described. More complete details are provided in the references.

Collins, Emory D [ORNL; Voit, Stewart L [ORNL; Vedder, Raymond James [ORNL

2011-06-01T23:59:59.000Z

51

Process for etching mixed metal oxides  

DOE Patents (OSTI)

An etching process using dicarboxylic and tricarboxylic acids as chelating etchants for mixed metal oxide films such as high temperature superconductors and ferroelectric materials. Undesirable differential etching rates between different metal oxides are avoided by selection of the proper acid or combination of acids. Feature sizes below one micron, excellent quality vertical edges, and film thicknesses in the 100 Angstom range may be achieved by this method.

Ashby, Carol I. H. (Edgewood, NM); Ginley, David S. (Evergreen, CO)

1994-01-01T23:59:59.000Z

52

Process for etching mixed metal oxides  

DOE Patents (OSTI)

An etching process is described using dicarboxylic and tricarboxylic acids as chelating etchants for mixed metal oxide films such as high temperature superconductors and ferroelectric materials. Undesirable differential etching rates between different metal oxides are avoided by selection of the proper acid or combination of acids. Feature sizes below one micron, excellent quality vertical edges, and film thicknesses in the 100 Angstrom range may be achieved by this method. 1 fig.

Ashby, C.I.H.; Ginley, D.S.

1994-10-18T23:59:59.000Z

53

Characterization of candidate DOE sites for fabricating MOX fuel for lead assemblies  

Science Conference Proceedings (OSTI)

The Office of Fissile Materials Disposition (MD) of the Department of Energy (DOE) is directing the program to disposition US surplus weapons-usable plutonium. For the reactor option for disposition of this surplus plutonium, MD is seeking to contract with a consortium, which would include a mixed-oxide (MOX) fuel fabricator and a commercial US reactor operator, to fabricate and burn MOX fuel in existing commercial nuclear reactors. This option would entail establishing a MOX fuel fabrication facility under the direction of the consortium on an existing DOE site. Because of the lead time required to establish a MOX fuel fabrication facility and the need to qualify the MOX fuel for use in a commercial reactor, MD is considering the early fabrication of lead assemblies (LAs) in existing DOE facilities under the technical direction of the consortium. The LA facility would be expected to produce a minimum of 1 metric ton heavy metal per year and must be operational by June 2003. DOE operations offices were asked to identify candidate sites and facilities to be evaluated for suitability to fabricate MOX fuel LAs. Savannah River Site, Argonne National Laboratory-West, Hanford, Lawrence Livermore National Laboratory, and Los Alamos National Laboratory were identified as final candidates to host the LA project. A Site Evaluation Team (SET) worked with each site to develop viable plans for the LA project. SET then characterized the suitability of each of the five plans for fabricating MOX LAs using 28 attributes and documented the characterization to aid DOE and the consortium in selecting the site for the LA project. SET concluded that each option has relative advantages and disadvantages in comparison with other options; however, each could meet the requirements of the LA project as outlined by MD and SET.

Holdaway, R.F.; Miller, J.W.; Sease, J.D.; Moses, R.J.; O`Connor, D.G. [Oak Ridge National Lab., TN (United States); Carrell, R.D. [Technical Resources International, Inc., Richland, WA (United States); Jaeger, C.D. [Sandia National Labs., Albuquerque, NM (United States); Thompson, M.L.; Strasser, A.A. [Delta-21 Resources, Inc., Oak Ridge, TN (United States)

1998-03-01T23:59:59.000Z

54

Reactor Physics Assessment of the Inclusion of Unseparated Neptunium in MOX Reactor Fuel  

Science Conference Proceedings (OSTI)

Reducing the number of actinide separation streams in a spent fuel recovery process would reduce the cost and complexity of the process, and lower the quantity and numbers of solvents needed. It is more difficult and costly to separate Np and recombine it with Am-Cm prior to co-conversion than to simply co-strip it with the U-Pu-Np. Inclusion of the Np in mixed oxide (MOX) fuel for light water reactor (LWR) applications should not seriously affect the operating behavior of the reactor, nor should it pose insurmountable fuel design issues. In this work, the U, Pu, and Np from typical discharged and cooled PWR spent nuclear fuel are assumed to be used together in the preparation of MOX fuel for use in a pressurized water reactor (PWR). The reactor grade Pu isotopic vector is used in the model and the relative mass ratio of the Pu and Np content (Np/Pu mass is 0.061) from the cooled spent fuel is maintained but the overall Pu-Np MOX wt% is adjusted with respect to the U content (assumed to be at 0.25 wt% 235U enrichment) to offset reactivity and cycle length effects. The SCALE 5.1 scientific package (especially modules TRITON, NEWT, ORIGEN-S, ORIGEN-ARP) was used for the calculations presented in this paper. A typical Westinghouse 17x17 fuel assembly design was modeled at nominal PWR operating conditions. It was seen that U-Pu-Np MOX fuel with NpO2 and PuO2 representing 11.5wt% of the total MOX fuel would be similar to standard MOX fuel in which PuO2 is 9wt% of the fuel. The reactivity, isotopic composition, and neutron and ? sources, and the decay heat details for the discharged MOX fuel are presented and discussed in this paper.

Ellis, Ronald James [ORNL

2009-01-01T23:59:59.000Z

55

Utilization of Surplus Weapons Plutonium As Mixed Oxide Fuel Position Statement  

E-Print Network (OSTI)

The American Nuclear Society (ANS) endorses the rapid application of mixed uraniumplutonium oxide (MOX) fuel technology to accomplish the timely disposition of surplus weapons-grade plutonium. The end of the Cold War has led to universal recognition that both the United States and Russia possess stockpiles of weapons-grade plutonium that far exceed their defense requirements. In 1994 the National Academy of Sciences (NAS) stated the following: “The existence of this material [surplus weapons-usable plutonium and highly enriched uranium] constitutes a clear and present danger to national and international security. 1 ” Russia and the United States have held extensive discussions on plutonium disposition, culminating in a September 2000 agreement 2 to dispose of 34 metric tons of surplus weaponsgrade plutonium in each country. The U.S. Department of Energy has completed two major Environmental Impact Statements on surplus plutonium disposition. 3,4 Implementation of the associated Records of Decision 5,6 has resulted in an ongoing program to dispose of surplus U.S. weapons-grade plutonium by fabricating the material into MOX fuel and using the fuel in commercial nuclear reactors. As with the blend-down of highly enriched uranium, a

unknown authors

2009-01-01T23:59:59.000Z

56

An Investigation into the Oxidation State of Molybdenum in Simplified High Level Nuclear Waste Glass Compositions  

E-Print Network (OSTI)

a full simulated HLW stream based upon 4:1 ratio of high burn up UO2/mixed oxide (HBU/MOX) fuel. EXPERIMENTAL A series of simplified simulated HLW glasses (based on the 4:1 HBU/MOX composition) were melted

Sheffield, University of

57

Analysis of Some Uranium Oxide and Mixed Oxide Lattice Measurements  

Science Conference Proceedings (OSTI)

A series of critical lattice experiments using uranium oxide and mixed-oxide fuel (uranium-plutonium) moderated by clean or borated water was expected to provide information for testing computer programs and nuclear data libraries used in analyzing nuclear reactor cores. Uncertainties inherent in the measurements must be small for experimental information to be of value in such a validation. In general, experimental parameters such as reaction ratios or disadvantage factors (which can be compared with ca...

1977-12-01T23:59:59.000Z

58

MOX Fuel Presentation to Duke Board of Directors  

National Nuclear Security Administration (NNSA)

The MOX Adventure The MOX Adventure Tamara Reavis Duke Energy May 2006 Page 2 Overview of Presentation > U. S. MOX Fuel Project - Background * Characteristics of MOX Fuel * MOX...

59

Conversion of mixed plutonium-uranium oxides. [COPRECAL  

SciTech Connect

Coprocessing is among the several reprocessing schemes being considered to improve the proliferation resistance of the back end of the nuclear fuel cycle. Coconversion of mixed oxides has been developed but not demonstrated on a production scale. AGNS developed a preliminary conceptual design for a production scale facility to convert mixed plutonium-uranium nitrate to the mixed oxide.

Thomas, L.L.

1980-04-01T23:59:59.000Z

60

design and synthesis of mixed oxides nanoparticles for biofuel applications.  

E-Print Network (OSTI)

??The work in this dissertation presents the synthesis of two mixed metal oxides for biofuel applications and NMR characterization of silica materials. In the chapter… (more)

Chen, Senniang

2010-01-01T23:59:59.000Z

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


61

Capability of the MIMAS process to convert the stockpiles of separated plutonium into MOX fuel for use in LWRs  

Science Conference Proceedings (OSTI)

Long-term storage of plutonium separated from fission products is not a good solution according to the current non-proliferation criteria as well as from an economic point of view. This material has thus to be converted to the equivalent of the “spent fuel standard.” Only one technique has so far reached the industrial maturity necessary to convert the important existing plutonium stockpiles: it is the use of plutonium to manufacture and irradiate mixed-oxide (MOX) fuel.

Paul Deramaix; Yvon Vanderborck; Werner Couwenbergh

2000-01-01T23:59:59.000Z

62

Hanford MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. Six initial site combinations were proposed: (1) Argonne National Laboratory-West (ANL-W) with support from Idaho National Engineering and Environmental Laboratory (INEEL), (2) Hanford, (3) Los Alamos National Laboratory (LANL) with support from Pantex, (4) Lawrence Livermore National Laboratory (LLNL), (5) Oak Ridge Reservation (ORR), and (6) Savannah River Site (SRS). After further analysis by the sites and DOE-MD, five site combinations were established as possible candidates for producing MOX LAs: (1) ANL-W with support from INEEL, (2) Hanford, (3) LANL, (4) LLNL, and (5) SRS. Hanford has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. An alternate approach would allow fabrication of fuel pellets and assembly of fuel rods in an S and S Category 1 facility. In all, a total of three LA MOX fuel fabrication options were identified by Hanford that could accommodate the program. In every case, only minor modification would be required to ready any of the facilities to accept the equipment necessary to accomplish the LA program.

O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

1998-08-01T23:59:59.000Z

63

ANL-W MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement (EIS). This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. The paper describes the following: Site map and the LA facility; process descriptions; resource needs; employment requirements; wastes, emissions, and exposures; accident analysis; transportation; qualitative decontamination and decommissioning; post-irradiation examination; LA fuel bundle fabrication; LA EIS data report assumptions; and LA EIS data report supplement.

O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

1997-08-01T23:59:59.000Z

64

Neutronics and safety characteristics of a 100% MOX fueled PWR using weapons grade plutonium  

Science Conference Proceedings (OSTI)

Preliminary neutronics and safety studies, pertaining to the feasibility of using 100% weapons grade mixed-oxide (MOX) fuel in an advanced PWR Westinghouse design are presented in this paper. The preliminary results include information on boron concentration, power distribution, reactivity coefficients and xenon and control rode worth for the initial and the equilibrium cycle. Important safety issues related to rod ejection and steam line break accidents and shutdown margin requirements are also discussed. No significant change from the commercial design is needed to denature weapons-grade plutonium under the current safety and licensing criteria.

Biswas, D.; Rathbun, R.; Lee, Si Young [Westinghouse Savannah River Co., Aiken, SC (United States); Rosenthal, P. [Westinghouse Electric Corp., Pittsburgh, PA (United States)

1993-12-31T23:59:59.000Z

65

LAB-SCALE DEMONSTRATION OF PLUTONIUM PURIFICATION BY ANION EXCHANGE, PLUTONIUM (IV) OXALATE PRECIPITATION, AND CALCINATION TO PLUTONIUM OXIDE TO SUPPORT THE MOX FEED MISSION  

SciTech Connect

H-Canyon and HB-Line are tasked with the production of PuO{sub 2} from a feed of plutonium metal. The PuO{sub 2} will provide feed material for the MOX Fuel Fabrication Facility. After dissolution of the Pu metal in H-Canyon, the solution will be transferred to HB-Line for purification by anion exchange. Subsequent unit operations include Pu(IV) oxalate precipitation, filtration and calcination to form PuO{sub 2}. This report details the results from SRNL anion exchange, precipitation, filtration, calcination, and characterization tests, as requested by HB-Line1 and described in the task plan. This study involved an 80-g batch of Pu and employed test conditions prototypical of HB-Line conditions, wherever feasible. In addition, this study integrated lessons learned from earlier anion exchange and precipitation and calcination studies. H-Area Engineering selected direct strike Pu(IV) oxalate precipitation to produce a more dense PuO{sub 2} product than expected from Pu(III) oxalate precipitation. One benefit of the Pu(IV) approach is that it eliminates the need for reduction by ascorbic acid. The proposed HB-Line precipitation process involves a digestion time of 5 minutes after the time (44 min) required for oxalic acid addition. These were the conditions during HB-line production of neptunium oxide (NpO{sub 2}). In addition, a series of small Pu(IV) oxalate precipitation tests with different digestion times were conducted to better understand the effect of digestion time on particle size, filtration efficiency and other factors. To test the recommended process conditions, researchers performed two nearly-identical larger-scale precipitation and calcination tests. The calcined batches of PuO{sub 2} were characterized for density, specific surface area (SSA), particle size, moisture content, and impurities. Because the 3013 Standard requires that the calcination (or stabilization) process eliminate organics, characterization of PuO{sub 2} batches monitored the presence of oxalate by thermogravimetric analysis-mass spectrometry (TGA-MS). To use the TGA-MS for carbon or oxalate content, some method development will be required. However, the TGA-MS is already used for moisture measurements. Therefore, SRNL initiated method development for the TGA-MS to allow quantification of oxalate or total carbon. That work continues at this time and is not yet ready for use in this study. However, the collected test data can be reviewed later as those analysis tools are available.

Crowder, M.; Pierce, R.

2012-08-22T23:59:59.000Z

66

SMALL-SCALE TESTING OF PLUTONIUM (IV) OXALATE PRECIPITATION AND CALCINATION TO PLUTONIUM OXIDE TO SUPPORT THE MOX FEED MISSION  

Science Conference Proceedings (OSTI)

The H-Canyon facility will be used to dissolve Pu metal for subsequent purification and conversion to plutonium dioxide (PuO{sub 2}) using Phase II of HB-Line. To support the new mission, SRNL conducted a series of experiments to produce calcined plutonium (Pu) oxide and measure the physical properties and water adsorption of that material. This data will help define the process operating conditions and material handling steps for HB-Line. An anion exchange column experiment produced 1.4 L of a purified 52.6 g/L Pu solution. Over the next nine weeks, seven Pu(IV) oxalate precipitations were performed using the same stock Pu solution, with precipitator feed acidities ranging from 0.77 M to 3.0 M nitric acid and digestion times ranging from 5 to 30 minutes. Analysis of precipitator filtrate solutions showed Pu losses below 1% for all precipitations. The four larger precipitation batches matched the target oxalic acid addition time of 44 minutes within 4 minutes. The three smaller precipitation batches focused on evaluation of digestion time and the oxalic acid addition step ranged from 25-34 minutes because of pump limitations in the low flow range. Following the precipitations, 22 calcinations were performed in the range of 610-690 C, with the largest number of samples calcined at either 650 or 635 C. Characterization of the resulting PuO{sub 2} batches showed specific surface areas in the range of 5-14 m{sup 2}/g, with 16 of the 22 samples in the range of 5-10 m2/g. For samples analyzed with typical handling (exposed to ambient air for 15-45 minutes with relative humidities of 20-55%), the moisture content as measured by Mass Spectrometry ranged from 0.15 to 0.45 wt % and the total mass loss at 1000 C, as measured by TGA, ranged from 0.21 to 0.58 wt %. For the samples calcined between 635 and 650 C, the moisture content without extended exposure ranged from 0.20 to 0.38 wt %, and the TGA mass loss ranged from 0.26 to 0.46 wt %. Of these latter samples, the samples calcined at 650 C generally had lower specific surface areas and lower moisture contents than the samples calcined at 635 C, which matches expectations from the literature. Taken together, the TGA-MS results for samples handled at nominally 20-50% RH, without extended exposure, indicate that the Pu(IV) oxalate precipitation process followed by calcination at 635-650 C appears capable of producing PuO{sub 2} with moisture content < 0.5 wt% as required by the 3013 Standard. Exposures of PuO{sub 2} samples to ambient air for 3 or more hours generally showed modest mass gains that were primarily gains in moisture content. These results point to the need for a better understanding of the moisture absorption of PuO{sub 2} and serve as a warning that extended exposure times, particularly above the 50% RH level observed in this study will make the production of PuO{sub 2} with less than 0.5 wt % moisture more challenging. Samples analyzed in this study generally contained approximately 2 monolayer equivalents of moisture. In this study, the bulk of the moisture released from samples below 300 C, as did a significant portion of the CO{sub 2}. Samples in this study consistently released a minor amount of NO in the 40-300 C range, but no samples released CO or SO{sub 2}. TGA-MS results also showed that MS moisture content accounted for 80 {+-} 8% of the total mass loss at 1000 C measured by the TGA. The PuO{sub 2} samples produced had particles sizes that typically ranged from 0.2-88 {micro}m, with the mean particle size ranging from 6.4-9.3 {micro}m. The carbon content of ten different calcination batches ranged from 190-480 {micro}g C/g Pu, with an average value of 290 {micro}g C/g Pu. A statistical review of the calcination conditions and resulting SSA values showed that in both cases tested, calcination temperature had a significant effect on SSA, as expected from literature data. The statistical review also showed that batch size had a significant effect on SSA, but the narrow range of batch sizes tested is a compelling reason to set aside that result until tests

Crowder, M.; Pierce, R.; Scogin, J.; Daniel, G.; King, W.

2012-06-25T23:59:59.000Z

67

SMALL-SCALE TESTING OF PLUTONIUM (IV) OXALATE PRECIPITATION AND CALCINATION TO PLUTONIUM OXIDE TO SUPPORT THE MOX FEED MISSION  

SciTech Connect

The H-Canyon facility will be used to dissolve Pu metal for subsequent purification and conversion to plutonium dioxide (PuO{sub 2}) using Phase II of HB-Line. To support the new mission, SRNL conducted a series of experiments to produce calcined plutonium (Pu) oxide and measure the physical properties and water adsorption of that material. This data will help define the process operating conditions and material handling steps for HB-Line. An anion exchange column experiment produced 1.4 L of a purified 52.6 g/L Pu solution. Over the next nine weeks, seven Pu(IV) oxalate precipitations were performed using the same stock Pu solution, with precipitator feed acidities ranging from 0.77 M to 3.0 M nitric acid and digestion times ranging from 5 to 30 minutes. Analysis of precipitator filtrate solutions showed Pu losses below 1% for all precipitations. The four larger precipitation batches matched the target oxalic acid addition time of 44 minutes within 4 minutes. The three smaller precipitation batches focused on evaluation of digestion time and the oxalic acid addition step ranged from 25-34 minutes because of pump limitations in the low flow range. Following the precipitations, 22 calcinations were performed in the range of 610-690 C, with the largest number of samples calcined at either 650 or 635 C. Characterization of the resulting PuO{sub 2} batches showed specific surface areas in the range of 5-14 m{sup 2}/g, with 16 of the 22 samples in the range of 5-10 m2/g. For samples analyzed with typical handling (exposed to ambient air for 15-45 minutes with relative humidities of 20-55%), the moisture content as measured by Mass Spectrometry ranged from 0.15 to 0.45 wt % and the total mass loss at 1000 C, as measured by TGA, ranged from 0.21 to 0.58 wt %. For the samples calcined between 635 and 650 C, the moisture content without extended exposure ranged from 0.20 to 0.38 wt %, and the TGA mass loss ranged from 0.26 to 0.46 wt %. Of these latter samples, the samples calcined at 650 C generally had lower specific surface areas and lower moisture contents than the samples calcined at 635 C, which matches expectations from the literature. Taken together, the TGA-MS results for samples handled at nominally 20-50% RH, without extended exposure, indicate that the Pu(IV) oxalate precipitation process followed by calcination at 635-650 C appears capable of producing PuO{sub 2} with moisture content < 0.5 wt% as required by the 3013 Standard. Exposures of PuO{sub 2} samples to ambient air for 3 or more hours generally showed modest mass gains that were primarily gains in moisture content. These results point to the need for a better understanding of the moisture absorption of PuO{sub 2} and serve as a warning that extended exposure times, particularly above the 50% RH level observed in this study will make the production of PuO{sub 2} with less than 0.5 wt % moisture more challenging. Samples analyzed in this study generally contained approximately 2 monolayer equivalents of moisture. In this study, the bulk of the moisture released from samples below 300 C, as did a significant portion of the CO{sub 2}. Samples in this study consistently released a minor amount of NO in the 40-300 C range, but no samples released CO or SO{sub 2}. TGA-MS results also showed that MS moisture content accounted for 80 {+-} 8% of the total mass loss at 1000 C measured by the TGA. The PuO{sub 2} samples produced had particles sizes that typically ranged from 0.2-88 {micro}m, with the mean particle size ranging from 6.4-9.3 {micro}m. The carbon content of ten different calcination batches ranged from 190-480 {micro}g C/g Pu, with an average value of 290 {micro}g C/g Pu. A statistical review of the calcination conditions and resulting SSA values showed that in both cases tested, calcination temperature had a significant effect on SSA, as expected from literature data. The statistical review also showed that batch size had a significant effect on SSA, but the narrow range of batch sizes tested is a compelling reason to set aside that result until tests

Crowder, M.; Pierce, R.; Scogin, J.; Daniel, G.; King, W.

2012-06-25T23:59:59.000Z

68

The behaviour of transuranic mixed oxide fuel in a Candu-900 reactor  

SciTech Connect

The production of transuranic actinide fuels for use in current thermal reactors provides a useful intermediary step in closing the nuclear fuel cycle. Extraction of actinides reduces the longevity, radiation and heat loads of spent material. The burning of transuranic fuels in current reactors for a limited amount of cycles reduces the infrastructure demand for fast reactors and provides an effective synergy that can result in a reduction of as much as 95% of spent fuel waste while reducing the fast reactor infrastructure needed by a factor of almost 13.5 [1]. This paper examines the features of actinide mixed oxide fuel, TRUMOX, in a CANDU{sup R}* nuclear reactor. The actinide concentrations used were based on extraction from 30 year cooled spent fuel and mixed with natural uranium in 3.1 wt% actinide MOX fuel. Full lattice cell modeling was performed using the WIMS-AECL code, super-cell calculations were analyzed in DRAGON and full core analysis was executed in the RFSP 2-group diffusion code. A time-average full core model was produced and analyzed for reactor coefficients, reactivity device worth and online fuelling impacts. The standard CANDU operational limits were maintained throughout operations. The TRUMOX fuel design achieved a burnup of 27.36 MWd/kg HE. A full TRUMOX fuelled CANDU was shown to operate within acceptable limits and provided a viable intermediary step for burning actinides. The recycling, reprocessing and reuse of spent fuels produces a much more sustainable and efficient nuclear fuel cycle. (authors)

Morreale, A. C.; Ball, M. R.; Novog, D. R.; Luxat, J. C. [Dept. of Engineering Physics, McMaster Univ., 1280 Main St. W, Hamilton, ON (Canada)

2012-07-01T23:59:59.000Z

69

Chemical and Radiochemical Composition of Thermally Stabilized Plutonium Oxide from the Plutonium Finishing Plant Considered as Alternate Feedstock for the Mixed Oxide Fuel Fabrication Facility  

Science Conference Proceedings (OSTI)

Eighteen plutonium oxide samples originating from the Plutonium Finishing Plant (PFP) on the Hanford Site were analyzed to provide additional data on the suitability of PFP thermally stabilized plutonium oxides and Rocky Flats oxides as alternate feedstock to the Mixed Oxide Fuel Fabrication Facility (MFFF). Radiochemical and chemical analyses were performed on fusions, acid leaches, and water leaches of these 18 samples. The results from these destructive analyses were compared with nondestructive analyses (NDA) performed at PFP and the acceptance criteria for the alternate feedstock. The plutonium oxide materials considered as alternate feedstock at Hanford originated from several different sources including Rocky Flats oxide, scrap from the Remote Mechanical C-Line (RMC) and the Plutonium Reclamation Facility (PRF), and materials from other plutonium conversion processes at Hanford. These materials were received at PFP as metals, oxides, and solutions. All of the material considered as alternate feedstock was converted to PuO2 and thermally stabilized by heating the PuO2 powder at 950 C in an oxidizing environment. The two samples from solutions were converted to PuO2 by precipitation with Mg(OH)2. The 18 plutonium oxide samples were grouped into four categories based on their origin. The Rocky Flats oxide was divided into two categories, low- and high-chloride Rocky Flats oxides. The other two categories were PRF/RMC scrap oxides, which included scrap from both process lines and oxides produced from solutions. The two solution samples came from samples that were being tested at Pacific Northwest National Laboratory because all of the plutonium oxide from solutions at PFP had already been processed and placed in 3013 containers. These samples originated at the PFP and are from plutonium nitrate product and double-pass filtrate solutions after they had been thermally stabilized. The other 16 samples originated from thermal stabilization batches before canning at PFP. Samples varied in appearance depending on the original source of material. Rocky Flats items were mostly dark olive green with clumps that crushed easily with a mortar and pestle. PRF/RMC items showed more variability. These items were mostly rust colored. One sample contained white particles that were difficult to crush, and another sample was a dark grey with a mixture of fines and large, hard fragments. The appearance and feel of the fragments indicated they might be an alloy. The color of the solution samples was indicative of the impurities in the sample. The double-pass filtrate solution was a brown color indicative of the iron impurities in the sample. The other solution sample was light gray in color. Radiochemical analyses, including thermal ionization mass spectrometry (TIMS), alpha and gamma energy analysis (AEA and GEA), and kinetic phosphorescence analysis (KPA), indicate that these materials are all weapons-grade plutonium with consistent plutonium isotopics. A small amount of uranium (Rocky Flats materials was Cl-, but the PRF/RMC samples had significant quantities of all of the primary anions observed. Prompt gamma measurements provide a representative analysis of the Cl- concentration in the bulk material. The primary anions observed in the solution samples were NO3-, and PO43-. The concentration of these anions did not exceed the mixed oxide (MOX) specification limits. Cations that exceeded the MOX specification limits included Cr, Fe, Ni, Al, Cu, and Si. All of the samples exceeded at least the 75% specification limit in one element.

Tingey, Joel M.; Jones, Susan A.

2005-07-01T23:59:59.000Z

70

Chemical and Radiochemical Composition of Thermally Stabilized Plutonium Oxide from the Plutonium Finishing Plant Considered as Alternate Feedstock for the Mixed Oxide Fuel Fabrication Facility  

SciTech Connect

Eighteen plutonium oxide samples originating from the Plutonium Finishing Plant (PFP) on the Hanford Site were analyzed to provide additional data on the suitability of PFP thermally stabilized plutonium oxides and Rocky Flats oxides as alternate feedstock to the Mixed Oxide Fuel Fabrication Facility (MFFF). Radiochemical and chemical analyses were performed on fusions, acid leaches, and water leaches of these 18 samples. The results from these destructive analyses were compared with nondestructive analyses (NDA) performed at PFP and the acceptance criteria for the alternate feedstock. The plutonium oxide materials considered as alternate feedstock at Hanford originated from several different sources including Rocky Flats oxide, scrap from the Remote Mechanical C-Line (RMC) and the Plutonium Reclamation Facility (PRF), and materials from other plutonium conversion processes at Hanford. These materials were received at PFP as metals, oxides, and solutions. All of the material considered as alternate feedstock was converted to PuO2 and thermally stabilized by heating the PuO2 powder at 950 C in an oxidizing environment. The two samples from solutions were converted to PuO2 by precipitation with Mg(OH)2. The 18 plutonium oxide samples were grouped into four categories based on their origin. The Rocky Flats oxide was divided into two categories, low- and high-chloride Rocky Flats oxides. The other two categories were PRF/RMC scrap oxides, which included scrap from both process lines and oxides produced from solutions. The two solution samples came from samples that were being tested at Pacific Northwest National Laboratory because all of the plutonium oxide from solutions at PFP had already been processed and placed in 3013 containers. These samples originated at the PFP and are from plutonium nitrate product and double-pass filtrate solutions after they had been thermally stabilized. The other 16 samples originated from thermal stabilization batches before canning at PFP. Samples varied in appearance depending on the original source of material. Rocky Flats items were mostly dark olive green with clumps that crushed easily with a mortar and pestle. PRF/RMC items showed more variability. These items were mostly rust colored. One sample contained white particles that were difficult to crush, and another sample was a dark grey with a mixture of fines and large, hard fragments. The appearance and feel of the fragments indicated they might be an alloy. The color of the solution samples was indicative of the impurities in the sample. The double-pass filtrate solution was a brown color indicative of the iron impurities in the sample. The other solution sample was light gray in color. Radiochemical analyses, including thermal ionization mass spectrometry (TIMS), alpha and gamma energy analysis (AEA and GEA), and kinetic phosphorescence analysis (KPA), indicate that these materials are all weapons-grade plutonium with consistent plutonium isotopics. A small amount of uranium (<0.14 wt%) is also present in these samples. The isotopic composition of the uranium varied widely but was consistent among each category of material. The primary water-soluble anions in these samples were Cl-, NO3-, SO42-, and PO43-. The only major anion observed in the Rocky Flats materials was Cl-, but the PRF/RMC samples had significant quantities of all of the primary anions observed. Prompt gamma measurements provide a representative analysis of the Cl- concentration in the bulk material. The primary anions observed in the solution samples were NO3-, and PO43-. The concentration of these anions did not exceed the mixed oxide (MOX) specification limits. Cations that exceeded the MOX specification limits included Cr, Fe, Ni, Al, Cu, and Si. All of the samples exceeded at least the 75% specification limit in one element.

Tingey, Joel M.; Jones, Susan A.

2005-07-01T23:59:59.000Z

71

LANL MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. LANL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within both Category 1 and 2 areas. Technical Area (TA) 55/Plutonium Facility 4 will be used to store the bulk PuO{sub 2} powder, fabricate MOX fuel pellets, assemble rods, and store fuel bundles. Bundles will be assembled at a separate facility, several of which have been identified as suitable for that activity. The Chemistry and Metallurgy Research Building (at TA-3) will be used for analytical chemistry support. Waste operations will be conducted in TA-50 and TA-54. Only very minor modifications will be needed to accommodate the LA program. These modifications consist mostly of minor equipment upgrades. A commercial reactor operator has not been identified for the LA irradiation. Postirradiation examination (PIE) of the irradiated fuel will take place at either Oak Ridge National Laboratory or ANL-W. The only modifications required at either PIE site would be to accommodate full-length irradiated fuel rods. Results from this program are critical to the overall plutonium distribution schedule.

Fisher, S.E.; Holdaway, R.; Ludwig, S.B. [and others

1998-08-01T23:59:59.000Z

72

Resistive Switching Characteristics of Mixed Oxides  

Science Conference Proceedings (OSTI)

Forming free bipolar switching was observed in case of Graphene Oxide. The switching ... A New Class of Molecularly-tailored Nanomaterials and Interfaces For Energy Conversion and Thermal Management · A Review of ... Novel Bimetallic Plasmonic Nanomaterials ... The Surface Energy of the Al-Cu-Fe Quasicrystal.

73

Composite mixed oxide ionic and electronic conductors for hydrogen separation  

DOE Patents (OSTI)

A mixed ionic and electronic conducting membrane includes a two-phase solid state ceramic composite, wherein the first phase comprises an oxygen ion conductor and the second phase comprises an n-type electronically conductive oxide, wherein the electronically conductive oxide is stable at an oxygen partial pressure as low as 10.sup.-20 atm and has an electronic conductivity of at least 1 S/cm. A hydrogen separation system and related methods using the mixed ionic and electronic conducting membrane are described.

Gopalan, Srikanth (Westborough, MA); Pal, Uday B. (Dover, MA); Karthikeyan, Annamalai (Quincy, MA); Hengdong, Cui (Allston, MA)

2009-09-15T23:59:59.000Z

74

PRIVACY IMPACT ASSESSMENT: Shaw Areva MOX Services, LLC MOX  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

. . ,-) ')7 73?Â¥i5": )~"'f"YC-:;'~dt?f(~"'f9'FrrZ , . PRIVACY IMPACT ASSESSMENT: Shaw Areva MOX Services, LLC MOX Services Unclassified Information System Template - January 30, 2009, Version 2 Department of Energy Privacy Impact Assessment (pIA) Guidance is provided in the template. See DOE Order 206.1, Department of Energy Privacy Program, Appendix A, Privacy Impact Assessments, for requirements and additional guidance for conducting a PIA: hltp:llwww.directives.doe.gov/pdfs/doe/doetextlneword/206/o2061.pdf Please complete electronically: no hand-written submissions will be accepted. (803) 819-22700 Dstlnson@moxprolect.com Dave Stinson, President and Chief Executive Officer, Shaw AREVA MOX Services, LLC NNSA Shaw AREVA MOX Services Savannah River Site, Aiken SC .. .. . ": .' . ' .... .- ...: ......

75

Design and synthesis of mixed oxides nanoparticles for biofuel applications  

DOE Green Energy (OSTI)

The work in this dissertation presents the synthesis of two mixed metal oxides for biofuel applications and NMR characterization of silica materials. In the chapter 2, high catalytic efficiency of calcium silicate is synthesized for transesterfication of soybean oil to biodisels. Chapter 3 describes the synthesis of a new Rh based catalyst on mesoporous manganese oxides. The new catalyst is found to have higher activity and selectivity towards ethanol. Chapter 4 demonstrates the applications of solid-state Si NMR in the silica materials.

Chen, Senniang

2010-05-15T23:59:59.000Z

76

Microbial Manganese(II) oxidation : biogeochemistry of a deep-sea hydrothermal plume, enzymatic mechanism, and genomic perspectives  

E-Print Network (OSTI)

Mn(II) oxidation. Near the Mox-1 region there is a predictedCu-binding regions. In the Mox-2 region there is a permeasethat are duplicated in both Mox regions include several

Dick, Gregory J.

2006-01-01T23:59:59.000Z

77

Mixed-conducting oxides for gas separation applications.  

DOE Green Energy (OSTI)

Mixed-conducting oxides are attracting increased attention because of their potential uses in high-temperature electrochemical applications such as solid-oxide fuel cells, batteries, sensors, and gas-permeable membranes. We are developing mixed-conducting, dense ceramic membranes to selectively transport oxygen and hydrogen. Ceramic membranes made of Sr-Fe-Co oxide (SFC), which exhibits high combined electronic and oxygen ionic conductivities, can be used to selectively transport oxygen during the partial oxidation of methane to synthesis gas (syngas, a mixture of CO and H{sub 2}). Steady-state oxygen permeability of SrFeCo{sub 0.5}O{sub x} has been measured as a function of oxygen-partial-pressure gradient and temperature. At 900 C, oxygen permeability was {approx}2.5 scc{center_dot}cm{sup {minus}2}-min{sup {minus}1} for a 2.9-mm-thick membrane, and this value increases as membrane thickness decreases. We have fabricated tubular SrFeCo{sub 0.5}O{sub x} membranes and operated them at 900 C for >1000 h during conversion of methane into syngas. Yttria-doped BaCeO{sub 3} (BCY) is a good protonic conductor; however, its lack of electronic conductivity can potentially limit its hydrogen permeability. To enhance the electronic conductivity and thus improve hydrogen permeation, a membrane composite material was developed. Nongalvanic permeation of hydrogen through the composite membrane was characterized as a function of thickness.

Balachandran, U.

1999-04-20T23:59:59.000Z

78

Development of mixed-conducting oxides for gas separation  

DOE Green Energy (OSTI)

Mixed-conducting oxides have been used in many applications, including fuel cells, gas separation membranes, sensors, and electrocatalysis. The authors are developing a mixed-conducting, dense ceramic membrane for selectively transporting oxygen and hydrogen. Ceramic membranes made of Sr-Fe-Co oxide, which has high combined electronic and oxygen ionic conductions, can be used to selectively transport oxygen during the partial oxidation of methane to synthesis gas (syngas, CO + H{sub 2}). The authors have measured the steady-state oxygen permeability of SrFeCo{sub 0.5}O{sub x} as a function of oxygen-partial-pressure gradient and temperature. At 900{degrees}C, oxygen permeability was {approx}2.5 scc{center_dot}cm{sup {minus}2}{center_dot}min{sup {minus}1} for a 2.9-mm-thick membrane and this value increases as membrane thickness decreases. The authors have fabricated tubular SrFeCo{sub 0.5}O{sub x} membranes and operated them at 900{degrees}C for >1000 h during conversion of methane into syngas. The hydrogen ion (proton) transport properties of yttria-doped BaCeO{sub 3} were investigated by impedance spectroscopy and open-cell voltage measurements. High proton conductivity and a high protonic transference number make yttria-doped BaCeO{sub 3} a potential membrane for hydrogen separation.

Balachandran, U.; Ma, B.; Maiya, P.S. [and others

1997-08-01T23:59:59.000Z

79

Reduction of spalling in mixed metal oxide desulfurization sorbents by addition of a large promoter metal oxide  

DOE Patents (OSTI)

Mixed metal oxide pellets for removing hydrogen sulfide from fuel gas mixes derived from coal are stabilized for operation over repeated cycles of desulfurization and regeneration reactions by addition of a large promoter metal oxide such as lanthanum trioxide. The pellets, which may be principally made up of a mixed metal oxide such as zinc titanate, exhibit physical stability and lack of spalling or decrepitation over repeated cycles without loss of reactivity. The lanthanum oxide is mixed with pellet-forming components in an amount of 1 to 10 weight percent.

Poston, James A. (Star City, WV)

1997-01-01T23:59:59.000Z

80

Study of lithium diffusion in RF sputtered Nickel/Vanadium mixed oxides thin films  

E-Print Network (OSTI)

Study of lithium diffusion in RF sputtered NickelÁ/Vanadium mixed oxides thin films F. Artuso a lithium insertion inside RF sputtered Ni/V mixed oxides thin films have been investigated employing, showed three steps clearly involved in the intercalation mechanism of lithium in the oxide films: (i

Artuso, Florinda

Note: This page contains sample records for the topic "mox mixed oxide" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
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81

Slurry calcination process for conversion of aqueous uranium and plutonium to a mixed oxide powder  

SciTech Connect

Pilot plant studies indicate that a slurry calcination process for conversion of uranium and plutonium solutions to a mixed oxide powder can be operated at a plant scale.

Jones, M K; Jenkins, W J

1980-01-01T23:59:59.000Z

82

Information Handling Plan For The Mixed Oxide Fuel Fabrication Facility  

E-Print Network (OSTI)

responses to the NRC's Request for Additional Information (RAI), and a revision to the Classified Matter Protection Plan (CMPP) for the Mixed Oxide Fuel Fabrication Facility (MFFF). Enclosure (1) provides the detailed responses to the Reference (A) RAIs, and indicates corresponding changes to the CMPP. Enclosure (2) provides a List of Effective Pages for the revised CMPP. Enclosure (3) is the revised CMPP itself; it is a page revision with respect to the previous revision of Reference (C). Enclosure (4) lists substantive changes in addition to those resulting from the RAIs. Changes resulting from the RAI responses, as well as other changes, are denoted by vertical lines in the right margin and revised pages have a current revision date. The enclosures herein concern protection of classified matter in accordance with 10 CFR 2.390(d), and should be withheld from public disclosure.

Shaw Areva; Mox Services

2008-01-01T23:59:59.000Z

83

Reduction of spalling in mixed metal oxide desulfurization sorbents by addition of a large promoter metal oxide  

DOE Patents (OSTI)

Mixed metal oxide pellets for removing hydrogen sulfide from fuel gas mixtures derived from coal are stabilized for operation over repeated cycles of desulfurization and regeneration reactions by addition of a large promoter metal oxide such as lanthanum trioxide. The pellets, which may be principally made up of a mixed metal oxide such as zinc titanate, exhibit physical stability and lack of spalling or decrepitation over repeated cycles without loss of reactivity. The lanthanum oxide is mixed with pellet-forming components in an amount of 1 to 10 weight percent.

Poston, J.A.

1996-12-31T23:59:59.000Z

84

Treatment of Mixed Wastewater of Slaughterhouse Wastewater and Biogas Slurry with Pilot Contact Oxidation System  

Science Conference Proceedings (OSTI)

In this paper, a pilot contact oxidation system was used to different mixing ratio wastewater of slaughterhouse wastewater and biogas slurry. The results showed that when the mixing ratio of slaughterhouse wastewater and biogas slurry was 19:1 and the ... Keywords: contact oxidation process, slaughterhouse wastewater and biogas slurry, COD removal, ammonia removal

Peng Li; Qun-Hui Wang; Jie Zhang; Tian-Long Zheng; Juan Wang

2012-05-01T23:59:59.000Z

85

MOX Reprocessing at Tokai Reprocessing Plant  

Science Conference Proceedings (OSTI)

In March 2007, the first reprocessing of the 'Type B' MOX spent fuels of the Prototype Advanced Thermal Reactor FUGEN was initiated at Tokai Reprocessing Plant as a plant-scale demonstration of MOX fuel reprocessing. The operation was advanced satisfactorily and it has been confirmed that the MOX fuels as well as UO{sub 2} fuels can be reprocessed safely. Some characteristics of MOX fuels on reprocessing, such as properties of undissolved residue affecting the clarification process, are becoming visible. Reprocessing of the 'Type B' MOX fuels will be continued for several more years from now on, further investigations on solubility of fuels, characteristics of undissolved residues, progress of solvent degradation and so on will be continued. (authors)

Taguchi, Katsuya; Nagaoka, Shinichi; Yamanaka, Atsushi; Nakamura, Yoshinobu; Omori, Eiichi [Tokai Reprocessing Technology Development Center, Japan Atomic Energy Agency 4-33 Muramatsu, Tokai-mura, Naka-gun, Ibaraki, 319-1194 (Japan); SATO, Takehiko; MIURA, Nobuyuki [Nuclear Fuel Cycle Technology Development Directorate, Japan Atomic Energy Agency 4-33 Muramatsu, Tokai-mura, Naka-gun, Ibaraki, 319-1194 (Japan)

2007-07-01T23:59:59.000Z

86

Performance of Thorium-Based Mixed Oxide Fuels for the Consumption of Plutonium and Minor Actinides in Current and Advanced Reactors  

SciTech Connect

A renewed interest in thorium-based fuels has arisen lately based on the need for proliferation resistance, longer fuel cycles, higher burnup and improved wasteform characteristics. Recent studies have been directed toward homogeneously mixed, heterogeneously mixed, and seed-and-blanket thorium-uranium fuel cycles that rely on "in situ" use of the bred-in U-233. However, due to the higher initial enrichment required to achieve acceptable burnups, these fuels are encountering economic constraints. Thorium can nevertheless play a large role in the nuclear fuel cycle; particularly in the reduction of plutonium. While uranium-based mixedoxide (MOX) fuel will decrease the amount of plutonium, the reduction is limited due to the breeding of more plutonium (and higher actinides) from the U-238. Here we present calculational results and a comparison of the potential burnup of a thorium-based and uranium-based mixed oxide fuel in a light water reactor (LWR). Although the uranium-based fuels outperformed the thorium-based fuels in achievable burnup, a depletion comparison of the initially charged plutonium (both reactor and weapons grade) showed that the thorium-based fuels outperformed the uranium-based fuels by more that a factor of 2; where more than 70% of the total plutonium in the thorium-based fuel is consumed during the cycle. This is significant considering that the achievable burnup of the thorium-based fuels were 1.4 to 4.6 times less than the uranium-based fuels. Furthermore, use of a thorium-based fuel could also be used as a strategy for reducing the amount of long-lived nuclides (including the minor actinides), and thus the radiotoxicity in spent nuclear fuel. Although the breeding of U-233 is a concern, the presence of U-232 and its daughter products can aid in making this fuel self-protecting, and/or enough U-238 can be added to denature the fissile uranium. From these calculations, it appears that thorium-based fuel for plutonium incineration is superior as compared to uranium-based fuel, and should be considered as an alternative to traditional MOX in both current and future reactor designs.

Weaver, Kevan Dean; Herring, James Stephen

2002-06-01T23:59:59.000Z

87

Experiment Safety Assurance Package for the 40- to 52-GWd/MT Burnup Phase of Mixed Oxide Fuel Irradiation in Small I-hole Positions in the Advanced Test Reactor  

SciTech Connect

This experiment safety assurance package (ESAP) is a revision of the last mixed uranium and plutonium oxide (MOX) ESAP issued in June 2002). The purpose of this revision is to provide a basis to continue irradiation up to 52 GWd/MT burnup [as predicted by MCNP (Monte Carlo N-Particle) transport code The last ESAP provided basis for irradiation, at a linear heat generation rate (LHGR) no greater than 9 kW/ft, of the highest burnup capsule assembly to 50 GWd/MT. This ESAP extends the basis for irradiation, at a LHGR no greater than 5 kW/ft, of the highest burnup capsule assembly from 50 to 52 GWd/MT.

S. T. Khericha; R. C. Pedersen

2003-09-01T23:59:59.000Z

88

Synthesis and Characterization of MnO2-Based Mixed Oxides as Supercapacitors  

E-Print Network (OSTI)

Synthesis and Characterization of MnO2-Based Mixed Oxides as Supercapacitors Hansung Kim. Available electronically January 28, 2003. The development of a high-power-density supercapacitor made to develop supercapacitors based on non-noble oxides.13 Hydrous manganese oxide (a-MnO2 · nH2O

Popov, Branko N.

89

Research and development of americium-containing mixed oxide fuel for fast reactors  

SciTech Connect

The present status of the R and D program for americium-containing MOX fuel is reported. Successful achievements for development of fabrication technology with remote handling and evaluation of irradiation behavior together with evaluation of thermo-chemical properties based on the out-of-pile experiments are mentioned with emphasis on effects of Am addition on the MOX fuel properties. (authors)

Tanaka, Kosuke; Osaka, Masahiko; Sato, Isamu; Miwa, Shuhei; Koyama, Shin-ichi; Ishi, Yohei; Hirosawa, Takashi; Obayashi, Hiroshi; Yoshimochi, Hiroshi; Tanaka, Kenya [Japan Atomic Energy Agency: 4002 Narita-cho, O-arai-machi, Higashiibaraki-gun, Ibaraki, 311-1393 (Japan)

2007-07-01T23:59:59.000Z

90

ORNL/TM-2010/43 OrigenArp Primer  

E-Print Network (OSTI)

.................................................................................................. 17 6. MOX EXPRESS FORM...................................................................................................................17 Fig. 9. MOX Express form available to interpolate cross sections for mixed-oxide (MOX) fuels using the variables burnup, plutonium

91

Opportunities for mixed oxide fuel testing in the advanced test reactor to support plutonium disposition  

Science Conference Proceedings (OSTI)

Numerous technical issues must be resolved before LWR operating licenses can be amended to allow the use of MOX fuel. These issues include the following: (1) MOX fuel fabrication process verification; (2) Whether and how to use burnable poisons to depress MOX fuel initial reactivity, which is higher than that of urania; (3) The effects of WGPu isotopic composition; (4) The feasibility of loading MOX fuel with plutonia content up to 7% by weight; (5) The effects of americium and gallium in WGPu; (6) Fission gas release from MOX fuel pellets made from WGPu; (7) Fuel/cladding gap closure; (8) The effects of power cycling and off-normal events on fuel integrity; (9) Development of radial distributions of burnup and fission products; (10) Power spiking near the interfaces of MOX and urania fuel assemblies; and (11) Fuel performance code validation. The Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory possesses many advantages for performing tests to resolve most of the issues identified above. We have performed calculations to show that the use of hafnium shrouds can produce spectrum adjustments that will bring the flux spectrum in ATR test loops into a good approximation to the spectrum anticipated in a commercial LWR containing MOX fuel while allowing operation of the test fuel assemblies near their optimum values of linear heat generation rate. The ATR would be a nearly ideal test bed for developing data needed to support applications to license LWRs for operation with MOX fuel made from weapons-grade plutonium. The requirements for planning and implementing a test program in the ATR have been identified. The facilities at Argonne National Laboratory-West can meet all potential needs for pre- and post-irradiation examination that might arise in a MOX fuel qualification program.

Terry, W.K.; Ryskamp, J.M.; Sterbentz, J.W. [and others

1995-08-01T23:59:59.000Z

92

PLUTONIUM LOADING CAPACITY OF REILLEX HPQ ANION EXCHANGE COLUMN - AFS-2 PLUTONIUM FLOWSHEET FOR MOX  

SciTech Connect

Radioactive plutonium (Pu) anion exchange column experiments using scaled HB-Line designs were performed to investigate the dependence of column loading performance on the feed composition in the H-Canyon dissolution process for plutonium oxide (PuO{sub 2}) product shipped to the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). These loading experiments show that a representative feed solution containing {approx}5 g Pu/L can be loaded onto Reillex{trademark} HPQ resin from solutions containing 8 M total nitrate and 0.1 M KF provided that the F is complexed with Al to an [Al]/[F] molar ratio range of 1.5-2.0. Lower concentrations of total nitrate and [Al]/[F] molar ratios may still have acceptable performance but were not tested in this study. Loading and washing Pu losses should be relatively low (<1%) for resin loading of up to 60 g Pu/L. Loading above 60 g Pu/L resin is possible, but Pu wash losses will increase such that 10-20% of the additional Pu fed may not be retained by the resin as the resin loading approaches 80 g Pu/L resin.

Kyser, E.; King, W.; O'Rourke, P.

2012-07-26T23:59:59.000Z

93

Laser Inertial Fusion-based Energy: Neutronic Design Aspects of a Hybrid Fusion-Fission Nuclear Energy System  

E-Print Network (OSTI)

Code MFE Magnetic Fusion Energy MOX Mixed Oxide NES Nuclearreprocessing mixed oxide (MOX) fuels, as will be discussedbegun using Mixed ox- ide or MOX fuel as a means of both

Kramer, Kevin James

2010-01-01T23:59:59.000Z

94

HB-LINE ANION EXCHANGE PURIFICATION OF AFS-2 PLUTONIUM FOR MOX  

SciTech Connect

Non-radioactive cerium (Ce) and radioactive plutonium (Pu) anion exchange column experiments using scaled HB-Line designs were performed to investigate the feasibility of using either gadolinium nitrate (Gd) or boric acid (B as H{sub 3}BO{sub 3}) as a neutron poison in the H-Canyon dissolution process. Expected typical concentrations of probable impurities were tested and the removal of these impurities by a decontamination wash was measured. Impurity concentrations are compared to two specifications - designated as Column A or Column B (most restrictive) - proposed for plutonium oxide (PuO{sub 2}) product shipped to the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). Use of Gd as a neutron poison requires a larger volume of wash for the proposed Column A specification. Since boron (B) has a higher proposed specification and is more easily removed by washing, it appears to be the better candidate for use in the H-Canyon dissolution process. Some difficulty was observed in achieving the Column A specification due to the limited effectiveness that the wash step has in removing the residual B after {approx}4 BV's wash. However a combination of the experimental 10 BV's wash results and a calculated DF from the oxalate precipitation process yields an overall DF sufficient to meet the Column A specification. For those impurities (other than B) not removed by 10 BV's of wash, the impurity is either not expected to be present in the feedstock or process, or recommendations have been provided for improvement in the analytical detection/method or validation of calculated results. In summary, boron is recommended as the appropriate neutron poison for H-Canyon dissolution and impurities are expected to meet the Column A specification limits for oxide production in HB-Line.

Kyser, E.; King, W.

2012-04-25T23:59:59.000Z

95

HB-LINE ANION EXCHANGE PURIFICATION OF AFS-2 PLUTONIUM FOR MOX  

SciTech Connect

Non-radioactive cerium (Ce) and radioactive plutonium (Pu) anion exchange column experiments using scaled HB-Line designs were performed to investigate the feasibility of using either gadolinium nitrate (Gd) or boric acid (B as H{sub 3}BO{sub 3}) as a neutron poison in the H-Canyon dissolution process. Expected typical concentrations of probable impurities were tested and the removal of these impurities by a decontamination wash was measured. Impurity concentrations are compared to two specifications - designated as Column A or Column B (most restrictive) - proposed for plutonium oxide (PuO{sub 2}) product shipped to the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). Use of Gd as a neutron poison requires a larger volume of wash for the proposed Column A specification. Since boron (B) has a higher proposed specification and is more easily removed by washing, it appears to be the better candidate for use in the H-Canyon dissolution process. Some difficulty was observed in achieving the Column A specification due to the limited effectiveness that the wash step has in removing the residual B after ~4 BV's wash. However a combination of the experimental 10 BV's wash results and a calculated DF from the oxalate precipitation process yields an overall DF sufficient to meet the Column A specification. For those impurities (other than B) not removed by 10 BV's of wash, the impurity is either not expected to be present in the feedstock or process, or recommendations have been provided for improvement in the analytical detection/method or validation of calculated results. In summary, boron is recommended as the appropriate neutron poison for H-Canyon dissolution and impurities are expected to meet the Column A specification limits for oxide production in HB-Line.

Kyser, E. A.; King, W. D.

2012-07-31T23:59:59.000Z

96

ENDF/B-VII.0, ENDF/B-VI, JEFF-3.1, AND JENDL-3.3 RESULTS FOR UNREFLECTED PLUTONIUM SOLUTIONS AND MOX LATTICES (U)  

SciTech Connect

Previous studies have indicated that ENDF/B-VII preliminary releases {beta}-2 and {beta}-3, predecessors to the recent initial release of ENDF/B-VII.0, produce significantly better overall agreement with criticality benchmarks than does ENDF/B-VI. However, one of those studies also suggests that improvements still may be needed for thermal plutonium cross sections. The current study substantiates that concern by examining criticality benchmarks for unreflected spheres of plutonium-nitrate solutions and for slightly and heavily borated mixed-oxide (MOX) lattices. Results are presented for the JEFF-3.1 and JENDL-3.3 nuclear data libraries as well as ENDF/B-VII.0 and ENDF/B-VI. It is shown that ENDF/B-VII.0 tends to overpredict reactivity for thermal plutonium benchmarks over at least a portion of the thermal range. In addition, it is found that additional benchmark data are needed for the deep thermal range.

MOSTELLER, RUSSELL D. [Los Alamos National Laboratory

2007-02-09T23:59:59.000Z

97

Brazing a Mixed Ionic/Electronic Conductor to an Oxidation Resistant Metal  

DOE Green Energy (OSTI)

Mixed ionically/electrically conducting oxides such as lanthanum calcium manganate are currently being investigated for use as electrodes in a number of high temperature devices, including solid oxide fuel cells. Traditionally, glass seals have been employed as a means of hermetically joining the ceramic components that lie at the heart of these devices to the heat resistant metal frame that gives the device its structural integrity. The present paper outlines an alternative brazing technique for joining these dissimilar materials and discusses recent findings regarding the wettability of the braze on the two joining surfaces, as well as the strength of the resulting joint.

Weil, K. Scott; Hardy, John S.

2003-09-05T23:59:59.000Z

98

Crystal structures of mixed-conducting oxides present in the Sr-Fe-Co-O system.  

DOE Green Energy (OSTI)

The potential applications of mixed-conducting ceramic oxides include solid-oxide fuel cells, rechargeable batteries, gas sensors and oxygen-permeable membranes. Several perovskite-derived mixed Sr-Fe-Co oxides show not only high electrical-conductivity but also appreciable oxygen-permeability at elevated temperatures. For example, dense ceramic membranes of SrFeCo{sub 0.5}O{sub 3{minus}{delta}} can be used to separate oxygen from air without the need for external electrical circuitry. The separated oxygen can be directly used for the partial oxidation of methane to produce syngas. Quantitative phase analysis of the SrFeCo{sub 0.5}O{sub 3{minus}{delta}} material has revealed that it is predominantly composed of two Sr-Fe-Co-O systems, Sr{sub 4}Fe{sub 6{minus}x}Co{sub x}O{sub 13} and SrFe{sub 1{minus}x}Co{sub x}O{sub 3{minus}{delta}}. Here we report preliminary structural findings on the SrFe{sub 1{minus}x}Co{sub x}O{sub 3{minus}{delta}} (0 {le} x {le} 0.3) system.

Hodges, J. P.; Jorgensen, J. D.; Miler, D. J.; Ma, B.; Balachandran, U.; Richardson, J. W., Jr.

1998-01-14T23:59:59.000Z

99

Sulfidation of mixed metal oxides in a fluidized-bed reactor  

SciTech Connect

Mixed metal oxides were used for the removal of hydrogen sulfide from a hot gas stream. Sorbents were prepared according to the dry and wet impregnation techniques. The desulfurization performance of the metal oxide sorbents was experimentally tested in a fluidized-bed reactor system. Sulfidation experiments performed under reaction conditions similar to those at the exit of a coal gasifier showed that the preparation procedure and technique, the type and the amount of the impregnated metal oxide, the type of the solid carrier, and the size of the solid reactant affect the H[sub 2]S removal capacity of the sorbents. The pore structure of fresh and sulfided sorbents was analyzed using mercury porosimetry, nitrogen adsorption, and scanning electron microscopy.

Christoforou, S.C.; Efthimiadis, E.A.; Vasalos, I.A. (Aristotelian Univ. of Thessaloniki (Greece))

1995-01-01T23:59:59.000Z

100

Evaluation of weapons-grade mixed oxide fuel performance in U.S. Light Water Reactors using COMETHE 4D release 23 computer code  

E-Print Network (OSTI)

The COMETHE 4D Release 23 computer code was used to evaluate the thermal, chemical and mechanical performance of weapons-grade MOX fuel irradiated under U.S. light water reactor typical conditions. Comparisons were made to and UO? fuels exhibited similar conventional UO? fuel. Weapons-grade MOX behavior. However, MOX fuel rods feature higher fuel centerline temperatures due to a lower thermal conductivity. Moreover, higher diffusion in MOX fuel results in a slightly higher fission gas release. Finally, MOX fuel shows better mechanical behavior than UO? fuel due to lower pellet-cladding mechanical interaction and rod deformation. These results indicate that the MOX fuel meets all potential licensing requirements.

Bellanger, Philippe

1999-01-01T23:59:59.000Z

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


101

EDF Nuclear Power Plants Operating Experience with MOX fuel  

Science Conference Proceedings (OSTI)

EDF started Plutonium recycling in PWR in 1987 and progressively all the 20 reactors, licensed in using MOX fuel, have been loaded with MOX assemblies. At the origin of MOX introduction, these plants operated at full power in base load and the core management limited the irradiation time of MOX fuel assemblies to 3 annual cycles. Since 1995 all these reactors can operate in load follow mode. Since that time, a large amount of experience has been accumulated. This experience is very positive considering: - Receipt, handling, in core behaviour, pool storage and shipment of MOX fuel; - Operation of the various systems of the plant; - Environment impact; - Radioprotection; - Safety file requirements; - Availability for the grid. In order to reduce the fuel cost and to reach a better adequacy between UO{sub 2} fuel reprocessing flow and plutonium consumption, EDF had decided to improve the core management of MOX plants. This new core management call 'MOX Parity' achieves parity for MOX and UO{sub 2} assemblies in term of discharge burn-up. Compared to the current MOX assembly the Plutonium content is increased from 7,08% to 8,65% (equivalent to natural uranium enriched to respectively 3,25% and 3,7%) and the maximum MOX assembly burn-up moves from 42 to 52 GWd/t. This amount of burn-up is obtained from loading MOX assemblies for one additional annual cycle. Some, but limited, adaptations of the plant are necessary. In addition a new MOX fuel assembly has been designed to comply with the safety criteria taking into account the core management performances. These design improvements are based on the results of an important R and D program including numerous experimental tests and post-irradiated fuel examinations. In particular, envelope conditions compared to MOX Parity neutronic solicitations has been extensively investigated in order to get a full knowledge of the in reactor fuel behavior. Moreover, the operating conditions of the plant have been evaluated in many details and finally no important impact is anticipated. The industrial maturity of plutonium recycling activities is fully demonstrated and a new progress can be done with a complete confidence. The licensing process of 'MOX Parity' core management is in progress and its implementation on the 20 PWR is now expected at mid 2007. (author)

Thibault, Xavier [EDF Generation, Tour EDF Part Dieu - 9 rue des Cuirassiers B.P.3181 - 69402 Lyon Cedex 03 (France)

2006-07-01T23:59:59.000Z

102

NNSA Holds Groundbreaking at MOX Facility | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Groundbreaking at MOX Facility | National Nuclear Security Groundbreaking at MOX Facility | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > NNSA Holds Groundbreaking at MOX Facility NNSA Holds Groundbreaking at MOX Facility October 14, 2005 Aiken, SC NNSA Holds Groundbreaking at MOX Facility

104

ORIGINAL PAPER Genome-wide expression profiling in Geobacter  

E-Print Network (OSTI)

) MOX mixed oxide (fuel) MPC multipurpose canister NEA Nuclear Energy Agency NEPA National Environmental

Lovley, Derek

105

EFFECTS OF MATERIALS RECOVERY WASTE-TO-ENERGY CO  

E-Print Network (OSTI)

met 'Multinational Nuclear Approach' MNP Milieu en Natuur Planbureau MOX Mixed oxide fuel, aanduiding

Columbia University

106

Preliminary Study on Utilization of Carbon Dioxide as a Coolant of High Temperature Engineering Test Reactor with MOX and Minor Actinides Fuel  

Science Conference Proceedings (OSTI)

High temperature engineering test reactor (HTTR) is an uranium oxide (UO2) fuel, graphite moderator and helium gas-cooled reactor with 30 MW in thermal output and outlet coolant temperature of 950 deg. C. Instead of using helium gas, we have utilized carbon dioxide as a coolant in the present study. Beside that, uranium and plutonium oxide (mixed oxide, MOX) and minor actinides have been employed as a new fuel type of HTTR. Utilization of plutonium and minor actinide is one of the support system to non-proliferation issue in the nuclear development. The enrichment for uranium oxide has been varied of 6-20% with plutonium and minor actinides concentration of 10%. In this study, burnup period is 1100 days. The reactor cell calculation was performed by using SRAC 2002 code, with nuclear data library was derived from JENDL3.2. Reactor core calculation was done by using CITATION module. The result shows that HTTR can achieve its criticality condition with 14% of {sup 235}U enrichment.

Fauzia, A. F.; Waris, A.; Novitrian [Bosscha Laboratory, Department of Physics, Nuclear Physics and Biophysics Research Group, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, INDONESIA Jl. Ganesa 10 Bandung 40132 (Indonesia)

2010-06-22T23:59:59.000Z

107

Joining Mixed Conducting Oxides Using an Air-Fired Electrically Conductive Braze  

DOE Green Energy (OSTI)

Due to their mixed oxygen ion and electron conducting properties, ceramics such as lanthanum strontium cobalt ferrites (LSCF) are attractive materials for use in active electrochemical devices such as solid oxide fuel cells (SOFC) and oxygen separation membranes. However, to take full advantage of the unique properties of these materials, reliable joining techniques need to be developed. If such a joining technique yields a ceramic-to-metal junction that is also electrically conductive, the hermetic seals in the device could provide the added function of either drawing current from the mixed conducting oxide, in the case of SOFC applications, or carrying it to the oxide to initate ionic conduction, in the case of oxygen separation and electrocatalysis applications. This would greatly reduce the need for complex interconnect design, thereby simplifying one of the major challenges faced in SOFC development. A process referred to as reactive air brazing (RAB) has been developed in which firing a Ag-CuO filler material in air creates a functional ceramic-to-metal junction, in which the silver-based matrix of the braze affords both metallic ductility and conductivity in the joint. Investigating a range of Ag-CuO alloy combinations determined that compositions containing between 1.4 and 16 mol% CuO appear to offer the best combination of wettability, joint strength, and electrical conductivity.

Hardy, John S.; Kim, Jin Yong Y.; Weil, K. Scott

2004-10-01T23:59:59.000Z

108

Method for acid oxidation of radioactive, hazardous, and mixed organic waste materials  

DOE Patents (OSTI)

The present invention is directed to a process for reducing the volume of low level radioactive and mixed waste to enable the waste to be more economically stored in a suitable repository, and for placing the waste into a form suitable for permanent disposal. The invention involves a process for preparing radioactive, hazardous, or mixed waste for storage by contacting the waste starting material containing at least one organic carbon-containing compound and at least one radioactive or hazardous waste component with nitric acid and phosphoric acid simultaneously at a contacting temperature in the range of about 140.degree. C. to about 210 .degree. C. for a period of time sufficient to oxidize at least a portion of the organic carbon-containing compound to gaseous products, thereby producing a residual concentrated waste product containing substantially all of said radioactive or inorganic hazardous waste component; and immobilizing the residual concentrated waste product in a solid phosphate-based ceramic or glass form.

Pierce, Robert A. (Aiken, SC); Smith, James R. (Corrales, NM); Ramsey, William G. (Aiken, SC); Cicero-Herman, Connie A. (Aiken, SC); Bickford, Dennis F. (Folly Beach, SC)

1999-01-01T23:59:59.000Z

109

Thermal-Hydraulic Analysis of Advanced Mixed-Oxide Fuel Assemblies with VIPRE-01  

E-Print Network (OSTI)

Two new fuel assembly designs for light water reactors using advanced mixed-oxide fuels have been proposed to reduce the radiotoxicity of used nuclear fuel discharged from nuclear power plants. The research efforts of this thesis are the first to consider the effects of burnup on advanced mixed-oxide fuel assembly performance and thermal safety margin over an assembly?s expected operational burnup lifetime. In order to accomplish this, a new burnup-dependent thermal-hydraulic analysis methodology has been developed. The new methodology models many of the effects of burnup on an assembly design by including burnup-dependent variations in fuel pin relative power from neutronic calculations, assembly power reductions due to fissile content depletion and core reshuffling, and fuel material thermal-physical properties. Additionally, a text-based coupling method is developed to facilitate the exchange of information between the neutronic code DRAGON and thermal-hydraulic code VIPRE-01. The new methodology effectively covers the entire assembly burnup lifetime and evaluates the thermal-hydraulic performance against ANS Condition I, II, and III events with respect to the minimum departure from nucleate boiling ratio, peak cladding temperatures, and fuel centerline temperatures. A comprehensive literature survey on the thermal conductivity of posed fuel materials with burnup-dependence has been carried out to model the advanced materials in the thermal-hydraulic code VIPRE-01. Where documented conductivity values are not available, a simplified method for estimating the thermal conductivity has been developed. The new thermal conductivity models are based on established FRAPCON-3 fuel property models used in the nuclear industry, with small adjustments having been made to account for actinide additions. Steady-state and transient thermal-hydraulic analyses are performed with VIPRE- 01 for a reference UO2 assembly design, and two advanced mixed-oxide fuel assembly designs using the new burnup-dependent thermal-hydraulic analysis methodology. All three designs maintain a sufficiently large thermal margin with respect to the minimum departure from nucleate boiling ratio, and maximum cladding and fuel temperatures during partial and complete loss-of-flow accident scenarios. The presence of a thin (Am,Zr)O2 outer layer on the fuel pellet in the two advanced mixed-oxide fuel assembly designs increases maximum fuel temperatures during transient conditions, but does not otherwise greatly compromise the thermal margin of the new designs.

Bingham, Adam R.

2009-05-01T23:59:59.000Z

110

A National Tracking Center for Monitoring Shipments of HEU, MOX, and Spent Nuclear Fuel: How do we implement?  

SciTech Connect

Nuclear material safeguards specialists and instrument developers at US Department of Energy (USDOE) National Laboratories in the United States, sponsored by the National Nuclear Security Administration (NNSA) Office of NA-24, have been developing devices to monitor shipments of UF6 cylinders and other radioactive materials , . Tracking devices are being developed that are capable of monitoring shipments of valuable radioactive materials in real time, using the Global Positioning System (GPS). We envision that such devices will be extremely useful, if not essential, for monitoring the shipment of these important cargoes of nuclear material, including highly-enriched uranium (HEU), mixed plutonium/uranium oxide (MOX), spent nuclear fuel, and, potentially, other large radioactive sources. To ensure nuclear material security and safeguards, it is extremely important to track these materials because they contain so-called “direct-use material” which is material that if diverted and processed could potentially be used to develop clandestine nuclear weapons . Large sources could be used for a dirty bomb also known as a radioactive dispersal device (RDD). For that matter, any interdiction by an adversary regardless of intent demands a rapid response. To make the fullest use of such tracking devices, we propose a National Tracking Center. This paper describes what the attributes of such a center would be and how it could ultimately be the prototype for an International Tracking Center, possibly to be based in Vienna, at the International Atomic Energy Agency (IAEA).

Mark Schanfein

2009-07-01T23:59:59.000Z

111

Evaluation of methods for seismic analysis of mixed-oxide fuel fabrication plants  

SciTech Connect

Guidelines are needed for selecting appropriate methods of structural analyses to evaluate the seismic hazard of mixed-oxide fuel fabrication plants. This study examines the different available methods and their applicability to fabrication plants. These results should provide a basis for establishing guidelines recommending methods of analysis to ensure safe design against seismic hazards. Using the Westinghouse Recycle Fuels Plant as representative of future mixed-oxide fuel fabrication plants, critical structures and equipment (systems, components, and piping/ducting) were identified. These included the manufacturing building and 11 different pieces of equipment. After examination of the dynamic response characteristics of the building and the different methods available to analyze equipment, appropriate methods of analyses were recommended. Because critical equipment analysis and test methods generally use floor-response spectra as their seismic input loading, several methods used to generate floor spectra were also examined. These include the time-history approach and the Kapur and Biggs approximate methods. The examination included the effect of site characteristics and both horizontal and vertical structural response. (auth)

Tokarz, F.J.; Arthur, D.F.; Murray, R.C.

1975-10-01T23:59:59.000Z

112

Evaluation of tubular reactor designs for supercritical water oxidation of U.S. Department of Energy mixed waste  

Science Conference Proceedings (OSTI)

Supercritical water oxidation (SCWO) is an emerging technology for industrial waste treatment and is being developed for treatment of the US Department of Energy (DOE) mixed hazardous and radioactive wastes. In the SCWO process, wastes containing organic material are oxidized in the presence of water at conditions of temperature and pressure above the critical point of water, 374 C and 22.1 MPa. DOE mixed wastes consist of a broad spectrum of liquids, sludges, and solids containing a wide variety of organic components plus inorganic components including radionuclides. This report is a review and evaluation of tubular reactor designs for supercritical water oxidation of US Department of Energy mixed waste. Tubular reactors are evaluated against requirements for treatment of US Department of Energy mixed waste. Requirements that play major roles in the evaluation include achieving acceptable corrosion, deposition, and heat removal rates. A general evaluation is made of tubular reactors and specific reactors are discussed. Based on the evaluations, recommendations are made regarding continued development of supercritical water oxidation reactors for US Department of Energy mixed waste.

Barnes, C.M.

1994-12-01T23:59:59.000Z

113

Technical specification: Mixed-oxide pellets for the light-water reactor irradiation demonstration test  

Science Conference Proceedings (OSTI)

This technical specification is a Level 2 Document as defined in the Fissile Materials Disposition Program Light-Water Reactor Mixed-oxide Fuel Irradiation Test Project Plan. It is patterned after the pellet specification that was prepared by Atomic Energy of Canada, Limited, for use by Los Alamos National Laboratory in fabrication of the test fuel for the Parallex Project, adjusted as necessary to reflect the differences between the Canadian uranium-deuterium reactor and light-water reactor fuels. This specification and the associated engineering drawing are to be utilized only for preparation of test fuel as outlined in the accompanying Request for Quotation and for additional testing as directed by Oak Ridge National Laboratory or the Department of Energy.

Cowell, B.S.

1997-06-01T23:59:59.000Z

114

Low temperature photochemical vapor deposition of alloy and mixed metal oxide films  

DOE Patents (OSTI)

Method and apparatus for formation of an alloy thin film, or a mixed metal oxide thin film, on a substrate at relatively low temperatures. Precursor vapor(s) containing the desired thin film constituents is positioned adjacent to the substrate and irradiated by light having wavelengths in a selected wavelength range, to dissociate the gas(es) and provide atoms or molecules containing only the desired constituents. These gases then deposit at relatively low temperatures as a thin film on the substrate. The precursor vapor(s) is formed by vaporization of one or more precursor materials, where the vaporization temperature(s) is selected to control the ratio of concentration of metals present in the precursor vapor(s) and/or the total precursor vapor pressure.

Liu, David K. (San Pablo, CA)

1992-01-01T23:59:59.000Z

115

EIS-0283-S2: Interim Action Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Environmental Impact Statement (EIS) DOE, 1999. DOE and the MFFF contractor, ShawAreva MOX Services, are pursuing utility customers for mixed oxide (MOX) fuel. At the present...

116

LLNL Site plan for a MOX fuel lead assembly mission in support of surplus plutonium disposition  

SciTech Connect

The principal facilities that LLNL would use to support a MOX Fuel Lead Assembly Mission are Building 332 and Building 334. Both of these buildings are within the security boundary known as the LLNL Superblock. Building 332 is the LLNL Plutonium Facility. As an operational plutonium facility, it has all the infrastructure and support services required for plutonium operations. The LLNL Plutonium Facility routinely handles kilogram quantities of plutonium and uranium. Currently, the building is limited to a plutonium inventory of 700 kilograms and a uranium inventory of 300 kilograms. Process rooms (excluding the vaults) are limited to an inventory of 20 kilograms per room. Ongoing operations include: receiving SSTS, material receipt, storage, metal machining and casting, welding, metal-to-oxide conversion, purification, molten salt operations, chlorination, oxide calcination, cold pressing and sintering, vitrification, encapsulation, chemical analysis, metallography and microprobe analysis, waste material processing, material accountability measurements, packaging, and material shipping. Building 334 is the Hardened Engineering Test Building. This building supports environmental and radiation measurements on encapsulated plutonium and uranium components. Other existing facilities that would be used to support a MOX Fuel Lead Assembly Mission include Building 335 for hardware receiving and storage and TRU and LLW waste storage and shipping facilities, and Building 331 or Building 241 for storage of depleted uranium.

Bronson, M.C.

1997-10-01T23:59:59.000Z

117

Molten salt oxidation of mixed wastes: Separation of radioactive materials and Resource Conservation and Recovery Act (RCRA) materials  

Science Conference Proceedings (OSTI)

The Oak Ridge National Laboratory (ORNL) is involved in a program to apply a molten salt oxidation (MSO) process to the treatment of mixed wastes at Oak Ridge and other Department of Energy (DOE) sites. Mixed wastes are defined as those wastes that contain both radioactive components, which are regulated by the atomic energy legislation, and hazardous waste components, which are regulated under the Resource Conservation and Recovery Act (RCRA). A major part of our ORNL program involves the development of separation technologies that are necessary for the complete treatment of mixed wastes. The residues from the MSO treatment of the mixed wastes must be processed further to separate the radioactive components, to concentrate and recycle residues, or to convert the residues into forms acceptable for final disposal. This paper is a review of the MSO requirements for separation technologies, the information now available, and the concepts for our development studies.

Bell, J.T.; Haas, P.A.; Rudolph, J.C.

1993-12-01T23:59:59.000Z

118

Mesoporous mixed metal oxides derived from P123-templated Mg-Al layered double hydroxides  

SciTech Connect

We report the preparation of mesoporous mixed metal oxides (MMOs) through a soft template method. Different amounts of P123 were used as structure directing agent to synthesize P123-templated Mg-Al layered double hydroxides (LDHs). After calcination of as-synthesized LDHs at 500 {sup o}C, the ordered mesopores were obtained by removal of P123. The mesoporous Mg-Al MMOs fabricated by using 2 wt% P123 exhibited a high specific surface area of 108.1 m{sup 2}/g, and wide distribution of pore size (2-18 nm). An investigation of the 'memory effect' of the mesoporous MMOs revealed that they were successfully reconstructed to ibuprofen intercalated LDHs having different gallery heights, which indicated different intercalation capacities. Due to their mesoporosity these unique MMOs have particular potential as drug or catalyst carriers. - Graphical abstract: Ordered mesoporous Mg-Al MMOs can be obtained through the calcination of P123-templated Mg-Al-CO{sub 3} LDHs. The pore diameter is 2.2 nm. At the presence of ibuprofen, the Mg-Al MMOs can recover to Mg-Al-IBU LDHs, based on its 'remember effect'. Display Omitted

Wang Jun, E-mail: zhqw1888@sohu.co [College of Material Science and Chemical Engineering, Harbin Engineering University, Harbin 150001 (China); College of Chemical Engineering, Harbin Institute of Technology, Harbin 150001 (China); Key Laboratory of Superlight Materials and Surface Technology, Ministry of Education, 150001 (China); Zhou Jideng; Li Zhanshuang; He Yang; Lin Shuangshuang; Liu Qi [College of Material Science and Chemical Engineering, Harbin Engineering University, Harbin 150001 (China); Zhang Milin [College of Material Science and Chemical Engineering, Harbin Engineering University, Harbin 150001 (China); Key Laboratory of Superlight Materials and Surface Technology, Ministry of Education, 150001 (China); Jiang Zhaohua [College of Chemical Engineering, Harbin Institute of Technology, Harbin 150001 (China)

2010-11-15T23:59:59.000Z

119

Integrated demonstration of molten salt oxidation with salt recycle for mixed waste treatment  

Science Conference Proceedings (OSTI)

Molten Salt Oxidation (MSO) is a thermal, nonflame process that has the inherent capability of completely destroying organic constituents of mixed wastes, hazardous wastes, and energetic materials while retaining inorganic and radioactive constituents in the salt. For this reason, MSO is considered a promising alternative to incineration for the treatment of a variety of organic wastes. Lawrence Livermore National Laboratory (LLNL) has prepared a facility and constructed an integrated pilot-scale MSO treatment system in which tests and demonstrations are performed under carefully controlled (experimental) conditions. The system consists of a MSO processor with dedicated off-gas treatment, a salt recycle system, feed preparation equipment, and equipment for preparing ceramic final waste forms. This integrated system was designed and engineered based on laboratory experience with a smaller engineering-scale reactor unit and extensive laboratory development on salt recycle and final forms preparation. In this paper we present design and engineering details of the system and discuss its capabilities as well as preliminary process demonstration data. A primary purpose of these demonstrations is identification of the most suitable waste streams and waste types for MSO treatment.

Hsu, P.C.

1997-11-01T23:59:59.000Z

120

Evaluation of the advanced mixed oxide fuel test FO-2 irradiated in Fast Flux Test Facility  

SciTech Connect

The advanced mixed-oxide (UO/sub 2/-PuO/sub 2/) test assembly, FO-2, irradiated in the Fast Flux Test Facility (FFTF), is undergoing postirradiation examination (PIE). This is one of the first FFTF tests examined that used the advanced ferrite-martensite alloy, HT9, which is highly resistant to irradiation swelling. The FO-2 includes the first annular fueled pins irradiated in FFTF to undergo destructive examination. The FO-2 is a lead assembly for the ongoing FFTF Core Demonstration Experiment (CDE) (Leggett and Omberg 1987) and was designed to evaluate the effects of fuel design variables, such as pellet density, smeared density, and fuel form (annular or solid fuel), on advanced pin performance. The assembly contains a total of 169 fuel pins of twelve different types. The test was irradiated for 312 equivalent full power days (EFPD) in FFTF. It had a peak pin power of 13.7 kW/ft and reached a peak burnup of 65.2 MWd/kgM with a peak fast fluence of 9.9 /times/ 10/sup 22/ n/cm/sup 2/ (E > 0.1 MeV). This document discusses the test and its results. 6 refs., 19 figs., 4 tabs.

Gilpin, L.L.; Baker, R.B.; Chastain, S.A.

1989-05-01T23:59:59.000Z

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


121

Pulsed Corona in Air for Water PROEFSCHRIFT  

E-Print Network (OSTI)

and construction of the U.S. mixed oxide (MOX) fuel fabrication facility and purchase of long lead equipment MOX fuel fabrication facility; fabricate U.S. and Russian MOX fuel lead assemblies, and publish final

Eindhoven, Technische Universiteit

122

Creation of Exotic Features in Metal Oxides by Surface Treatment for Enhanced Gas Sensing  

E-Print Network (OSTI)

followed by oxidation in a well-defined pO2 regime near the M-MOx proximity line by a suitable buffer gas Model. Fig. 4. Thermodynamic criteria for several M/MOx coexistence and practical pO2 regimes for phase as a function of temperature for several M-MOx pairs. By manipulating the ambient pO2 across these lines, one

Azad, Abdul-Majeed

123

Technique for preparation of prototypic fast test reactor mixed-oxide fuel pins for ceramography and metallography  

Science Conference Proceedings (OSTI)

Irradiated liquid metal fast breeder reactor prototypic mixed-oxide fuel and cladding have been sectioned and examined in remote hot cell facilities for ceramographic and metallographic examinations. Metallography, shielded electron microprobe examinations, electron microscopy from replicas and autoradiography are routinely employed to obtain postirradiation data for statistical evaluation. Selection of preparatory techniques are based on fuel type, burnup, customer requirements and fuel pin condition.

Chastain, S.A.

1981-01-01T23:59:59.000Z

124

Calibration Tools for Measurement of Highly Enriched Uranium in Oxide and Mixed Uranium-Plutonium Oxide with a Passive-Active Neutron Drum Shuffler  

SciTech Connect

Lawrence Livermore National Laboratory (LLNL) has completed an extensive effort to calibrate the LLNL passive-active neutron drum (PAN) shuffler (Canberra Model JCC-92) for accountability measurement of highly enriched uranium (HEU) oxide and HEU in mixed uranium-plutonium (U-Pu) oxide. Earlier papers described the PAN shuffler calibration over a range of item properties by standards measurements and an extensive series of detailed simulation calculations. With a single normalization factor, the simulations agree with the HEU oxide standards measurements to within {+-}1.2% at one standard deviation. Measurement errors on mixed U-Pu oxide samples are in the {+-}2% to {+-}10% range, or {+-}20 g for the smaller items. The purpose of this paper is to facilitate transfer of the LLNL procedure and calibration algorithms to external users who possess an identical, or equivalent, PAN shuffler. Steps include (1) measurement of HEU standards or working reference materials (WRMs); (2) MCNP simulation calculations for the standards or WRMs and a range of possible masses in the same containers; (3) a normalization of the calibration algorithms using the standard or WRM measurements to account for differences in the {sup 252}Cf source strength, the delayed-neutron nuclear data, effects of the irradiation protocol, and detector efficiency; and (4) a verification of the simulation series trends against like LLNL results. Tools include EXCEL/Visual Basic programs which pre- and post-process the simulations, control the normalization, and embody the calibration algorithms.

Mount, M; O' Connell, W; Cochran, C; Rinard, P

2003-06-13T23:59:59.000Z

125

P2-03: 3D Characterization of High Burn-up MOX Fuel  

Science Conference Proceedings (OSTI)

Currently fast reactor performance is largely defined by the limitations of the materials involved in reactors, especially the metallic or mixed oxide ((U, Pu)O2) fuel ...

126

Mixed nanostructured Ti-W oxides films for efficient electrochromic windows  

Science Conference Proceedings (OSTI)

With the aim to enhance the electrochromic (EC) efficiency and electrochemical stability of electrochromic devices (ECD), mixed nanostructured TiO2/WO3 films were prepared by an electrochemical deposition method with the purpose ...

Nguyen Nang Dinh; Dang Hai Ninh; Tran Thi Thao; Truong Vo-Van

2012-01-01T23:59:59.000Z

127

Solar energy as an alternate energy source to mixed oxide fuels in light-water cooled reactors  

DOE Green Energy (OSTI)

Supplemental information pertaining to the generic environmental impact statement on the Pu recycling process for mixed oxide light-water cooled reactors (GESMO) was requested from several sources. In particular, the role of alternate sources of energy was to be explored and the implications of these alternate sources to the question of Pu recycle in LWRs were to be investigated. In this vein, solar energy as an alternate source is the main subject of this report, along with other information related to solar energy. The general conclusion is that solar energy should have little effect on the decisions concerning GESMO.

Bertini, H.W.

1977-06-30T23:59:59.000Z

128

Evaluation of the advanced mixed-oxide fuel test FO-2 irradiated in the FFTF (Fast Flux Test Facility)  

SciTech Connect

The advanced mixed-oxide (UO{sub 2}-PuO{sub 2}) test assembly, FO-2, irradiated in the Fast Flux Test Facility (FFTF) is undergoing postirradiation examination. This is one of the first FFTF tests examined that used the advanced ferrite-martensite alloy, HT9, which is highly resistant to irradiation swelling. The FO-2 includes the first annular fueled pins irradiated in FFTF to undergo destructive examination. The FO-2 is a lead assembly for the ongoing FFTF Core Demonstration Experiment (CDE) and was designed to evaluate the effects of fuel design variables, such as pellet density, smeared density, and fuel form (annular or solid fuel), on advanced pin performance. The assembly contains a total of 169 fuel pins of 12 different types. Two L (annular) fuel pins, GF02L04 (FFTF and transient tested) and GF02L09 (FFTF only), were destructively examined. Evaluation of the FO-2 fuel pins and assembly shows the excellent and predictable performance of the mixed-oxide fuels with HT9 structural material. This, combined with the robust behavior of the pins in transient tests, and the continued excellent performance of the CDE indicate this is a superior fuel system for liquid-metal reactors. It offers greatly reduced deformation during irradiation, while maintaining good operating characteristics.

Burley Gilpin, L.L.; Chastain, S.A.; Baker, R.B.

1989-01-01T23:59:59.000Z

129

Nuclear waste treatment - Studying the mixed ion type effects and concentration on the behaviour of oxide dispersions  

Science Conference Proceedings (OSTI)

In order to gain good control over a particulate dispersion it is necessary to accurately characterise the strength of inter-particle forces that may be operating. Such control is not routinely used, as yet, in the nuclear industry despite the possible benefits. We are investigating the impact of mixed electrolyte systems, for example NaCl and Na{sub 2}SO{sub 4}, on the stability of oxide simulant particle dispersions. The electro-acoustic zeta potentials and shear yield stresses for concentrated dispersions have been measured across a range of pH conditions and electrolyte concentrations (0.001 M - 1.0 M). This paper summarizes initial data from these studies showing how the shear yield stress of concentrated aqueous oxide particle dispersions, can be adjusted through regulation of pH and the addition of background electrolytes (salt). The yield stress as a function of pH for these dispersions in mixed electrolytes showed a direct correlation with corresponding measurements of the zeta potential. Changes in the background electrolyte concentration or type were seen to cause a shift in the position of the isoelectric point (iep). Measurements of the shear yield stress showed a maximum at the iep corresponding to the position of maximum instability in the suspension. The consequences of these data for the efficient treatment of solid-liquid systems will be discussed. (authors)

Omokanye, Qanitalillahi; Biggs, Simon [Institute of Particle Science and Engineering, University of Leeds, Leeds LS2 9JT (United Kingdom)

2007-07-01T23:59:59.000Z

130

NUCLEAR SCIENCE AND ENGINEERING: 148, 129 ~2004! Development of a Method for Measuring the Moderator Temperature  

E-Print Network (OSTI)

as semblies~improvedfueleconomy,i.e.,longercyclelength!, or mixed-oxide ~MOX! fuel assemblies. For the former

Demazière, Christophe

131

TOWARDS BENCHMARK MEASUREMENTS FOR USED NUCLEAR FUEL ASSAY USING A LEAD SLOWING-DOWN SPECTROMETER  

E-Print Network (OSTI)

and the Karlsruhe Nuclear Research Center, Germany designed and operated a LSDS to assayed fresh mixed oxide (MOX

Danon, Yaron

132

Process modeling of plutonium conversion and MOX fabrication for plutonium disposition  

SciTech Connect

Two processes are currently under consideration for the disposition of 35 MT of surplus plutonium through its conversion into fuel for power production. These processes are the ARIES process, by which plutonium metal is converted into a powdered oxide form, and MOX fuel fabrication, where the oxide powder is combined with uranium oxide powder to form ceramic fuel. This study was undertaken to determine the optimal size for both facilities, whereby the 35 MT of plutonium metal will be converted into fuel and burned for power. The bounding conditions used were a plutonium concentration of 3--7%, a burnup of 20,000--40,000 MWd/MTHM, a core fraction of 0.1 to 0.4, and the number of reactors ranging from 2--6. Using these boundary conditions, the optimal cost was found with a plutonium concentration of 7%. This resulted in an optimal throughput ranging from 2,000 to 5,000 kg Pu/year. The data showed minimal costs, resulting from throughputs in this range, at 3,840, 2,779, and 3,497 kg Pu/year, which results in a facility lifetime of 9.1, 12.6, and 10.0 years, respectively.

Schwartz, K.L. [Univ. of Texas, Austin, TX (United States). Dept. of Nuclear Engineering

1998-10-01T23:59:59.000Z

133

Calibration of the Lawrence Livermore National Laboratory Passive-Active Neutron Drum Shuffler for Measurement of Highly Enriched Uranium in Mixed Oxide  

SciTech Connect

As a follow-on to the Lawrence Livermore National Laboratory (LLNL) effort to calibrate the LLNL passive-active neutron drum (PAN) shuffler for measurement of highly enriched uranium (HEU) oxide, a method has been developed to extend the use of the PAN shuffler to the measurement of HEU in mixed uranium-plutonium (U-Pu) oxide. This method uses the current LLNL HEU oxide calibration algorithms, appropriately corrected for the mixed U-Pu oxide assay time, and recently developed PuO{sub 2} calibration algorithms to yield the mass of {sup 235}U present via differences between the expected count rate for the PuO{sub 2} and the measured count rate of the mixed U-Pu oxide. This paper describes the LLNL effort to use PAN shuffler measurements of units of certified reference material (CRM) 149 [uranium (93% Enriched) Oxide - U{sub 3}O{sub 8} Standard for Neutron Counting Measurements] and CRM 146 [Uranium Isotopic Standard for Gamma Spectrometry Measurements] and a selected set of LLNL PuO{sub 2}-bearing containers in consort with Monte Carlo simulations of the PAN shuffler response to each to (1) establish and validate a correction to the HEU calibration algorithm for the mixed U-Pu oxide assay time, (2) develop a PuO{sub 2} calibration algorithm that includes the effect of PuO{sub 2} density (2.4 g/cm{sup 3} to 4.8 g/cm{sup 3}) and container size (8.57 cm to 9.88 cm inside diameter and 9.60 cm to 13.29 cm inside height) on the PAN shuffler response, and (3) develop and validate the method for establishing the mass of {sup 235}U present in an unknown of mixed U-Pu oxide.

Mount, M; O' Connell, W; Cochran, C; Rinard, P; Dearborn, D; Endres, E

2002-05-23T23:59:59.000Z

134

Final assessment of MOX fuel performance experiment with Japanese PWR specification fuel in the HBWR  

Science Conference Proceedings (OSTI)

In order to obtain high burn-up MOX fuel irradiation performance data, SBR and MIMAS MOX fuel rods with Pu-fissile enrichment of about 6 wt% had been irradiated in the HBWR from 1995 to 2006. The peak burn-up of MOX pellet achieved 72 GWd/tM. In this test, fuel centerline temperature, rod internal pressure, stack length and cladding length were measured for MOX fuel and UO{sub 2} fuel as reference. MOX fuel temperature is confirmed to have no significant difference in comparison with UO{sub 2}, taking into account of adequate thermal conductivity degradation due to PuO{sub 2} addition and burn-up development. And the measured fuel temperature agrees well with FINE code calculation up to high burn-up region. Fission gas release of MOX is possibly greater than UO{sub 2} based on temperature and pressure assessment. No significant difference is confirmed between SBR and MIMAS MOX on FGR behavior. MOX fuel swelling rate agrees well with solid swelling rate in the literature. Cladding elongation data shows onset of PCMI in high power region. (authors)

Fujii, Hajime; Teshima, Hideyuki; Kanasugi, Katsumasa [Mitsubishi Heavy Industries, Ltd., 1-1, Wadasaki-cho 1-chome, Hyogo-ku, Kobe 652-8585 (Japan); Kosaka, Yuji [Nuclear Development Corporation, 622-12 Funaishikawa, Tokai-mura, Ibaraki 319-1111 (Japan); Arakawa, Yasushi [The Kansai Electric Power Co., Inc., 8 Yokota, 13 Goichi, Mihama-cho, Mikata-gun, Fukui, 919-1141 (Japan)

2007-07-01T23:59:59.000Z

135

A Neutronic Analysis of TRU Recycling in PWRs Loaded with MOX-UE Fuel (MOX with U-235 Enriched U Support)  

SciTech Connect

This report presents the results of a study dealing with the homogeneous recycling of either Pu or Pu+Np or Pu+Np+Am or Pu+Np+Am+Cm in PWRs using MOX-UE fuel, i.e. standard MOX fuel with a U235 enriched uranium support instead of the standard tail uranium (0.25%) for standard MOX fuel. This approach allows to multirecycle Pu or TRU (Pu+MA) as long as U235 is available, by keeping the Pu or TRU content in the fuel constant and at a value ensuring a negative moderator void coefficient (i.e. the loss of the coolant brings imperatively the reactor to a subcritical state). Once this value is determined, the U235 enrichment of the MOX-UE fuel is adjusted in order to reach the target burnup (51 GWd/t in this study).

G. Youinou; S. Bays

2009-05-01T23:59:59.000Z

136

Use of impure inert gases in the controlled heating and cooling of mixed conducting metal oxide materials  

SciTech Connect

Method for processing an article comprising mixed conducting metal oxide material. The method comprises contacting the article with an oxygen-containing gas and either reducing the temperature of the oxygen-containing gas during a cooling period or increasing the temperature of the oxygen-containing gas during a heating period; during the cooling period, reducing the oxygen activity in the oxygen-containing gas during at least a portion of the cooling period and increasing the rate at which the temperature of the oxygen-containing gas is reduced during at least a portion of the cooling period; and during the heating period, increasing the oxygen activity in the oxygen-containing gas during at least a portion of the heating period and decreasing the rate at which the temperature of the oxygen-containing gas is increased during at least a portion of the heating period.

Carolan, Michael Francis (Allentown, PA); Bernhart, John Charles (Fleetwood, PA)

2012-08-21T23:59:59.000Z

137

LITERATURE REVIEW FOR OXALATE OXIDATION PROCESSES AND PLUTONIUM OXALATE SOLUBILITY  

SciTech Connect

A literature review of oxalate oxidation processes finds that manganese(II)-catalyzed nitric acid oxidation of oxalate in precipitate filtrate is a viable and well-documented process. The process has been operated on the large scale at Savannah River in the past, including oxidation of 20 tons of oxalic acid in F-Canyon. Research data under a variety of conditions show the process to be robust. This process is recommended for oxalate destruction in H-Canyon in the upcoming program to produce feed for the MOX facility. Prevention of plutonium oxalate precipitation in filtrate can be achieved by concentrated nitric acid/ferric nitrate sequestration of oxalate. Organic complexants do not appear practical to sequester plutonium. Testing is proposed to confirm the literature and calculation findings of this review at projected operating conditions for the upcoming campaign. H Canyon plans to commence conversion of plutonium metal to low-fired plutonium oxide in 2012 for eventual use in the Mixed Oxide Fuel (MOX) Facility. The flowsheet includes sequential operations of metal dissolution, ion exchange, elution, oxalate precipitation, filtration, and calcination. All processes beyond dissolution will occur in HB-Line. The filtration step produces an aqueous filtrate that may have as much as 4 M nitric acid and 0.15 M oxalate. The oxalate needs to be removed from the stream to prevent possible downstream precipitation of residual plutonium when the solution is processed in H Canyon. In addition, sending the oxalate to the waste tank farm is undesirable. This report addresses the processing options for destroying the oxalate in existing H Canyon equipment.

Nash, C.

2012-02-03T23:59:59.000Z

138

Molybdenum-based additives to mixed-metal oxides for use in hot gas cleanup sorbents for the catalytic decomposition of ammonia in coal gases  

DOE Patents (OSTI)

This invention relates to additives to mixed-metal oxides that act simultaneously as sorbents and catalysts in cleanup systems for hot coal gases. Such additives of this type, generally, act as a sorbent to remove sulfur from the coal gases while substantially simultaneously, catalytically decomposing appreciable amounts of ammonia from the coal gases.

Ayala, Raul E. (Clifton Park, NY)

1993-01-01T23:59:59.000Z

139

Role of hydrous ruthenium oxide in Pt-Ru direct methanol fuel cell anode electrocatalysts: The importance of mixed electron/proton conductivity  

Science Conference Proceedings (OSTI)

Pt-Ru is the favored anode catalyst for the oxidation of methanol in direct methanol fuel cells (DMFCs). The nanoscale Pt-Ru blacks are accepted to be bimetallic alloys as based on their X-ray diffraction patterns. These bulk and surface analyses show that although practical Pt-Ru blacks have diffraction patterns consistent with an alloy assignment, they are primarily a mix of Pt metal and Ru oxides plus some Pt oxides and only small amounts of Ru metal. Thermogravimetric analysis and X-ray photoelectron spectroscopy of as-received Pt-Ru electrocatalysts indicate that DMFC materials contain substantial amounts of hydrous ruthenium oxide (RuO{sub x}H{sub y}). A potential misidentification of nanoscale Pt-Ru blacks arises because RuO{sub x}H{sub y} is amorphous and cannot be discerned by X-ray diffraction. Hydrous ruthenium oxide is a mixed proton and electron conductor and innately expresses Ru-OH speciation. These properties are of key importance in the mechanism of methanol oxidation, in particular, Ru-OH is a critical component of the bifunctional mechanism proposed for direct methanol oxidation in that it is the oxygen-transfer species that oxidatively dissociates {single_bond}C{triple_bond}O fragments from the Pt surface. The catalysts and membrane-electrode assemblies of DMFCs should not be processed at or exposed to temperatures >150 C, as such conditions deleteriously lower the proton conductivity of hydrous ruthenium oxide and thus affect the ability of the Ru component of the electrocatalyst to dissociate water. With this analytical understanding of the true nature of practical nanoscale Pt-Ru electrocatalysts, the authors can now recommend that hydrous ruthenium oxide, rather than Ru metal or anhydrous RuO{sub 2}, is the preferred Ru speciation in these catalysts.

Rolison, D.R.; Hagans, P.L.; Swider, K.E.; Long, J.W. [Naval Research Lab., Washington, DC (United States). Surface Chemistry Branch

1999-02-02T23:59:59.000Z

140

Options for converting excess plutonium to feed for the MOX fuel fabrication facility  

SciTech Connect

The storage and safekeeping of excess plutonium in the United States represents a multibillion-dollar lifecycle cost to the taxpayers and poses challenges to National Security and Nuclear Non-Proliferation. Los Alamos National Laboratory is considering options for converting some portion of the 13 metric tons of excess plutonium that was previously destined for long-term waste disposition into feed for the MOX Fuel Fabrication Facility (MFFF). This approach could reduce storage costs and security ri sks, and produce fuel for nuclear energy at the same time. Over the course of 30 years of weapons related plutonium production, Los Alamos has developed a number of flow sheets aimed at separation and purification of plutonium. Flow sheets for converting metal to oxide and for removing chloride and fluoride from plutonium residues have been developed and withstood the test oftime. This presentation will address some potential options for utilizing processes and infrastructure developed by Defense Programs to transform a large variety of highly impure plutonium into feedstock for the MFFF.

Watts, Joe A [Los Alamos National Laboratory; Smith, Paul H [Los Alamos National Laboratory; Psaras, John D [Los Alamos National Laboratory; Jarvinen, Gordon D [Los Alamos National Laboratory; Costa, David A [Los Alamos National Laboratory; Joyce, Jr., Edward L [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

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


141

Direct Conversion of Bio-ethanol to Isobutene on Nanosized ZnxZryOz Mixed Oxides with Balanced Acid–Base Sites  

Science Conference Proceedings (OSTI)

Bio-mass conversion has attracted increasing research interests to produce bio-fuels with bio-ethanol being a major product. Development of advanced processes to further upgrade bio-ethanol to other value added fuels or chemicals are pivotal to improving the economics of biomass conversion and deversifying the utilization of biomass resources. In this paper, for the first time, we report the direct conversion of bio-ethanol to isobutene with high yield (~83%) on a multifunctional ZnxZryOz mixed oxide with a dedicated balance of surface acid-base properties. This work illustrates the significance of rational design of a multifunctional mixed oxide catalyst for one step bio-ethanol conversion to a value-added intermediate, isobutene, for chemical and fuel production. This work was supported by the US Department of Energy Basic Energy Sciences' Chemical Sciences, Geosciences & Biosciences Division. Pacific Northwest National Laboratory is operated by Battelle for the US Department of Energy.

Sun, Junming; Zhu, Kake; Gao, Feng; Wang, Chong M.; Liu, Jun; Peden, Charles HF; Wang, Yong

2011-06-17T23:59:59.000Z

142

Obtaining Mixed Ionic/Electronic Conductivity in Perovskite Oxides in a Reducing Environment: A Computational Prediction for Doped SrTiO3  

Science Conference Proceedings (OSTI)

The electronic conductivity and thermodynamic stability of mixed p- and n-doped SrTiO3 perovskites have been investigated under anodic solid oxide fuel cell conditions using density functional theory (DFT). In particular, constrained ab initio thermodynamic calculations have been performed to evaluate the phase stability of various Ga- and La-doped SrTiO3 at synthesized and anodic SOFC conditions. The density of states (DOS) of these materials was analyzed to determine the number of charge carriers and the degree of electronic conductivity. We find that a mixed ionic/electronic conductor can be obtained when doping SrTiO3 perovskite oxide with both p-type and n-type dopants. Calculations show that 10% Ga- and 20% La-doped SrTiO3 exhibit mixed ionic/electronic conductivity at high temperature and low oxygen partial pressure whereas doping with higher concentrations of Ga, e.g., 20%, diminishes the electronic conductivity of the material. Furthermore, changing the n-dopant from La (A-site) to Nb (B-site) does not significantly affect the reducibility and number of charge carriers in p- and n-doped SrTiO3. However, a higher degree of oxygen vacancy clustering is observed for the La-doped material which reduces the oxygen ion diffusion rate and traps electrons. Nevertheless, our findings suggest that independent of doping site, mixed ionic/ electronic conductivity can be obtained in SrTiO3 perovskite oxides under reducing conditions and high temperatures when using a mixed p- and n-type doping strategy that uses a p-dopant concentration smaller than the n-dopant concentration.

Suthirakun, Suwit; Ammal, Salai Cheettu; Xiao, Guoliang; Chen, Fanglin; Huang, Kevin; zur Loye, Hans-Conrad; Heyden, Andreas

2012-11-30T23:59:59.000Z

143

U.S. weapons-usable plutonium disposition policy: Implementation of the MOX fuel option  

SciTech Connect

A comprehensive case study was conducted on the policy problem of disposing of US weapons-grade plutonium, which has been declared surplus to strategic defense needs. Specifically, implementation of the mixed-oxide fuel disposition option was examined in the context of national and international nonproliferation policy, and in contrast to US plutonium policy. The study reveals numerous difficulties in achieving effective implementation of the mixed-oxide fuel option including unresolved licensing and regulatory issues, technological uncertainties, public opposition, potentially conflicting federal policies, and the need for international assurances of reciprocal plutonium disposition activities. It is believed that these difficulties can be resolved in time so that the implementation of the mixed-oxide fuel option can eventually be effective in accomplishing its policy objective.

Woods, A.L. [ed.] [Amarillo National Resource Center for Plutonium, TX (United States); Gonzalez, V.L. [Texas A and M Univ., College Station, TX (United States). Dept. of Political Science

1998-10-01T23:59:59.000Z

144

US weapons-useable plutonium disposition policy: implementation of the MOX fuel option  

E-Print Network (OSTI)

A comprehensive case study was conducted on the policy problem of disposing of U.S. weapons-grade plutonium which has been declared surplus to strategic defense needs. Specifically, implementation of the mixed-oxide fuel disposition option was examined in the context of national and international nonproliferation policy, and in contrast to U.S. plutonium policy. The study reveals numerous difficulties in achieving effective implementation of the mixed-oxide fuel option including unresolved licensing and regulatory issues, technological uncertainties, public opposition, potentially conflicting federal policies, and the need for international assurances of reciprocal plutonium disposition activities. It is believed that these difficulties can be resolved in time so that the implementation of the mixed-oxide fuel option can eventually be effective in accomplishing its policy objective.

Gonzalez, Vanessa L

1998-01-01T23:59:59.000Z

145

Critical Experiments that Simulated Damp MOX Powders - Do They Meet the Need?  

DOE Green Energy (OSTI)

The OECD Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS) identified the MOX fuel manufacturing process as an area in which there is a need for additional integral benchmark data. The specific need focused on damp MOX powders. The WPNCS was ultimately asked by the NEA Nuclear Science Committee (NSC) to provide the framework for the selection and performance of new experiments that fill the identified need. A set of criteria was established to enable uniform comparison of experimental proposals with generic MOX application data. Criteria were established for five general characteristics: (1) neutronic parameters, (2) type of experiments, (3) financial aspects, (4) schedule, and (5) other considerations. Proposals were judged most importantly on their ability to match the neutronic parameters of predetermined MOX applications. The neutronic parameters that formed the basis for comparison included core average values (not local values) for flux, fission and capture rate; detailed balance data (fission and capture) for the main isotopes (Actinides, H and O); sensitivity coefficients to important nuclear reactions (fission, capture, elastic and inelastic scatter, nu-bar, mu-bar) for all uranium and plutonium isotopes, hydrogen, and oxygen; sensitivity profiles to the main nuclear reactions for uranium and plutonium isotopes; energy of average lethargy causing fission; and the average fission group energy. The focus of this paper is on the definition of the need; the neutronics criteria established to assess which, if any, of three proposed MOX experimental programs best meet the need; and the actual assessment of the proposed experimental programs.

J. Blair Briggs; Dr. Ali Nouri; Dr. Claes Nordborg

2005-09-01T23:59:59.000Z

146

Additional public meeting on plutonium disposition on September...  

NLE Websites -- All DOE Office Websites (Extended Search)

produce an oxide form of plutonium suitable for disposition and the use of mixed oxide (MOX) fuel fabricated from surplus plutonium in domestic commercial nuclear power reactors...

147

Adsorption of propane, isopropyl, and hydrogen on cluster models of the M1 phase of Mo-V-Te-Nb-O mixed metal oxide catalyst  

Science Conference Proceedings (OSTI)

The Mo-V-Te-Nb-O mixed metal oxide catalyst possessing the M1 phase structure is uniquely capable of directly converting propane into acrylonitrile. However, the mechanism of this complex eight-electron transformation, which includes a series of oxidative H-abstraction and N-insertion steps, remains poorly understood. We have conducted a density functional theory study of cluster models of the proposed active and selective site for propane ammoxidation, including the adsorption of propane, isopropyl (CH{sub 3}CHCH{sub 3}), and H which are involved in the first step of this transformation, that is, the methylene C-H bond scission in propane, on these active site models. Among the surface oxygen species, the telluryl oxo (Te=O) is found to be the most nucleophilic. Whereas the adsorption of propane is weak regardless of the MO{sub x} species involved, isopropyl and H adsorption exhibits strong preference in the order of Te=O > V=O > bridging oxygens > empty Mo apical site, suggesting the importance of TeO{sub x} species for H abstraction. The adsorption energies of isopropyl and H and consequently the reaction energy of the initial dehydrogenation of propane are strongly dependent on the number of ab planes included in the cluster, which points to the need to employ multilayer cluster models to correctly capture the energetics of surface chemistry on this mixed metal oxide catalyst.

Govindasamy, Agalya [University of Cincinnati; Muthukumar, Kaliappan [University of Cincinnati; Yu, Junjun [University of Cincinnati; Xu, Ye [ORNL; Guliants, Vadim V. [University of Cincinnati

2010-01-01T23:59:59.000Z

148

IDENTIFYING IMPURITIES IN SURPLUS NON PIT PLUTONIUM FEEDS FOR MOX OR ALTERNATIVE DISPOSITION  

SciTech Connect

This report provides a technical basis for estimating the level of corrosion products in materials stored in DOE-STD-3013 containers based on extrapolating available chemical sample results. The primary focus is to estimate the levels of nickel, iron, and chromium impurities in plutonium-bearing materials identified for disposition in the United States Mixed Oxide fuel process.

Allender, J; Moore, E

2010-07-14T23:59:59.000Z

149

energy.gov -Headquarters' Press Release (Print Version) Tuesday, February 4, 2003 http://www.energy.gov/HQPress/releases03/febpr/pr03027_v.htm Page: 1  

E-Print Network (OSTI)

of a mixed oxide (MOX) fuel fabrication facility in the U.S. and U.S. efforts to assist Russia with the start of construction of an industrial scale MOX fuel fabrication facility. Additionally, the request includes $30

150

The MOXE X-ray all-sky monitor for Spectrum-X-Gamma  

SciTech Connect

MOXE is an X-ray all-sky monitor to be flown on the Russian Spectrum-X-Gamma satellite, to be launched in a few years. It will monitor several hundred X-ray sources on a daily basis, and will be the first instrument to monitor most of the X-ray sky most of the time. MOXE will alert users of more sensitive instruments on Russia`s giant high energy astrophysics observatory and of other instruments to transient activity. MOXE consists of an array of 6 X-ray pinhole cameras, sensitive from 3 to 25 keV, which views 4{pi} steradians (except for a 20{degree} {times} 80{degree} patch which includes the Sun). The pinhole apertures of 0.625 {times} 2.556 cm{sup 2} imply an angular resolution of 2{degree}.4 {times} 9{degree}.7 (on-axis). The MOXE hardware program includes an engineering model, now delivered, and a flight model. The flight instrument will mass approximately 118 kg and draw 38 Watts. For a non-focusing all-sky instrument that is limited by sky background, the limiting sensitivity is a function only of detector area. MOXE, with 6,000 cm{sup 2} of detector area, will, for a 24 hrs exposure, have a sensitivity of approximately 2 mCrab. MOXE distinguishes itself with respect to other all-sky monitors in its high duty cycle, thus being particularly sensitive to transient phenomena with time scales between minutes and hours.

In`t Zand, J.J.M.; Priedhorsky, W.C.; Moss, C.E. [and others

1994-08-01T23:59:59.000Z

151

QUALIFICATION OF THE SAVANNAH RIVER SITE 252CF SHUFFLER FOR RECEIPT VERIFICATION MEASUREMENTS OF MIXED U-PU OXIDES STORED IN 9975 SHIPPING CONTAINERS  

Science Conference Proceedings (OSTI)

To extend their ability to perform accountability and verification measurements of {sup 235}U in a U-Pu oxide matrix, the K-Area Material Storage facility commissioned the development and construction of a Passive/Active {sup 252}Cf Shuffler. A series of {sup 252}Cf, PuO{sub 2}, and U-Pu oxide standards, in addition to a single U{sub 3}O{sub 8} standard, were measured to characterize and calibrate the shuffler. Accompanying these measurements were simulations using MCNP5/MCNPX, aimed at isolating the neutron countrate contributions for each of the isotopes present. Two calibration methods for determining the {sup 235}U content in mixed UPu oxide were then developed, yielding comparable results. The first determines the {sup 235}U mass by estimating the {sup 239}Pu/{sup 235}U ratio-dependent contributions from the primary delayed neutron contributors. The second defines an average linear response based on the {sup 235}U and {sup 239}Pu mass contents. In each case, it was observed that self-shielding due to {sup 235}U mass has a large influence on the observed rates, requiring bounds on the applicable limits of each calibration method.

Dubose, F.

2011-05-26T23:59:59.000Z

152

A Dependence of the Electronuclear System Parameters on the Component Concentration in Fuel MOX  

E-Print Network (OSTI)

A dependence of the parameters of a electronuclear system with U-Pu fuel MOX on the relative share of plutonium and its isotope ^{240}Pu in fuel is investigated by means of mathematical modelling. As an example, we consider an experimental system with a heat power 10-20 kW designed in Dubna on the basis of the 660 MeV proton phasotron. The 2 % admixture of ^{240}Pu decreases the value of the neutron multiplication coefficient from 0.95 down to 0.90, neutron yield and heat power are diminished almost twice. Such a decrease can be compensated by the increase of Plutonium share in MOX from 25 up to 27 %.

Barashenkov, V S

2001-01-01T23:59:59.000Z

153

Thermal conductivity, microstructure and gas release from a 44 GWd ...  

Science Conference Proceedings (OSTI)

Abstract Scope, Plutonium recycling in mixed oxide fuel (MOX) occurs in more ... burn-up and irradiation temperature profiles and Pu-content on properties and ...

154

CX-009610: Categorical Exclusion Determination | Department of...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Location(s): South Carolina Offices(s): Savannah River Operations Office Mixed oxide (MOX) services proposes to install a communication cable beginning at the existing Manhole...

155

SRNL - News Room  

NLE Websites -- All DOE Office Websites (Extended Search)

WSB to treat and solidify the liquid waste that will be generated by the Mixed Oxide (MOX) Fuel Fabrication Facility and planned pit disassembly and conversion activities. The...

156

Microstructural Evolution  

Science Conference Proceedings (OSTI)

Feb 16, 2010... mixed oxide (MOX) fuels, and will also inform multiscale simulations of fission gas behavior by providing realistic microstructural information.

157

Application of wavelet scaling function expansion continuous-energy resonance calculation method to MOX fuel problem  

Science Conference Proceedings (OSTI)

More and more MOX fuels are used in all over the world in the past several decades. Compared with UO{sub 2} fuel, it contains some new features. For example, the neutron spectrum is harder and more resonance interference effects within the resonance energy range are introduced because of more resonant nuclides contained in the MOX fuel. In this paper, the wavelets scaling function expansion method is applied to study the resonance behavior of plutonium isotopes within MOX fuel. Wavelets scaling function expansion continuous-energy self-shielding method is developed recently. It has been validated and verified by comparison to Monte Carlo calculations. In this method, the continuous-energy cross-sections are utilized within resonance energy, which means that it's capable to solve problems with serious resonance interference effects without iteration calculations. Therefore, this method adapts to treat the MOX fuel resonance calculation problem natively. Furthermore, plutonium isotopes have fierce oscillations of total cross-section within thermal energy range, especially for {sup 240}Pu and {sup 242}Pu. To take thermal resonance effect of plutonium isotopes into consideration the wavelet scaling function expansion continuous-energy resonance calculation code WAVERESON is enhanced by applying the free gas scattering kernel to obtain the continuous-energy scattering source within thermal energy range (2.1 eV to 4.0 eV) contrasting against the resonance energy range in which the elastic scattering kernel is utilized. Finally, all of the calculation results of WAVERESON are compared with MCNP calculation. (authors)

Yang, W. [Shanghai Nuclear Engineering Research and Design Inst., Hong Cao road 29, Shanghai (China); Dept. of Nuclear Engineering, Xi'an Jiaotong Univ., Xian Ning west road 28, Xi'an, Shaanxi (China); Wu, H.; Cao, L. [Dept. of Nuclear Engineering, Xi'an Jiaotong Univ., Xian Ning west road 28, Xi'an, Shaanxi (China)

2012-07-01T23:59:59.000Z

158

Rational synthesis of unidimensional mixed valence solids. Structure oxidation state-charge transport relationships in iodinated nickel and palladium bisbenzoquinonedioximates  

SciTech Connect

A detailed study is presented of crystal structure, stoichiometry, oxidation state, and electron transport in the materials Ni(bqd)/sub 2/, Pd(bqd)/sub 2/, Ni(bqd)/sub 2/I/sub 0/ /sub 018/, Ni(bqd)/sub 2/I/sub 0/ /sub 5/ . S, and Pd(bqd)/sub 2/I/sub 0/ /sub 5/ . S, where bqd = o-benzoquinonedioximato and S = an aromatic solvent. The compound Pd(bqd)/sub 2/I/sub 0/ /sub 50/ . 0.52o-C/sub 6/H/sub 4/Cl/sub 2/ was shown by single-crystal x-ray diffraction to crystallize in the tetragonal space group D/sub 4h//sup 2/-P4/mcc, with four formula units in a cell of dimensions a = 16.048 (7) and c = 6.367 (3) A. The crystal structure consists of stacked Pd(bqd)/sub 2/ units, each staggered by 65/sup 0/ with respect to its nearest neighbors, and disordered chains of iodine atoms extending in the c direction. The Pd--Pd distance is 3.184 (3) A, Pd--N = 1.996 (7) A, and the Pd(bqd)/sub 2/ units are rigorously planar. The predominant form of the iodine present is I/sub 3//sup -/ (..nu../sub fundamental/ 107 cm/sup -1/). Crystallization of Ni(bqd)/sub 2/ from benzene containing traces of iodine produces the new orthorhombic phase Ni(bqd)/sub 2/I/sub 0/ /sub 018/. It crystallizes in the space group D/sub 2h//sup 26/-Ibam with four formula units in a unit cell of dimensions a = 16.438 (2), b = 14.759 (4), and c = 6.360 (2) A. Full-matrix least-squares refinement gave a final value of the conventional R index (on F) of 0.11 for 1026 reflections having F/sub 0//sup 2/ > 3 sigma(F/sub 0//sup 2/). The structure contains rigorously planar Ni(bqd)/sub 2/ units stacked along the c axis with each molecule staggered by 68/sup 0/ with respect to its nearest neighbors. The Ni--Ni distance is 3.180 (2) A and Ni--N = 1.88 (10) A. Single-crystal electrical conductivity measurements (dc and 100-Hz ac) in the stacking direction show an increase in conductivity upon partial oxidation of >10/sup 3/ (Ni) and >10/sup 4/ (Pd). Maximum conductivities at 300 K are determined.

Brown, L.D. (Northwestern Univ., Evanston, IL); Kalina, D.W.; McClure, M.S.; Schultz, S.; Ruby, S.L.; Ibers, J.A.; Kannewurf, C.R.; Marks, T.J.

1979-05-23T23:59:59.000Z

159

Will the Bush Administration's GNEP Help or Hurt the Prospects  

E-Print Network (OSTI)

recovered plutonium has been fabricated into mixed-oxide (MOX) fuel and recycled to commercial light water is conventional PUREX reprocessing and recycling of MOX fuel, for which cost information is available. This information makes clear that the conventional MOX fuel cycle is more costly than the alternative

160

FY 1992 Annual report: Mediated electrochemical oxidation treatment for Rocky Flats combustible low-level mixed waste. Final report to Rocky Flats Plant  

SciTech Connect

The Mediated Electrochemical Oxidation (MEO) process was studied for destroying low-level combustible mixed wastes at Rocky Flats (RFP). Tests were performed with nonradioactive surrogate materials: Trimsol for the contaminated oils, and reagent-grade cellulose for the cellulosic wastes. Extensive testing was carried out on Trimsol in both small laboratory-scale apparatus and on a large-scale system incorporating an industrial-size electrochemical cell. Preliminary tests were also carried out in the small-scale system with cellulose. The following operating and system parameters were studied: use of a silver-nitric acid versus a cobalt-sulfuric acid system, effect of electrolyte temperature, effect of acid concentration, effect of current density, and use of ultrasonic agitation. Destruction and coulombic efficiencies were calculated using data obtained from continuous carbon dioxide monitors and total organic carbon (TOC) analysis of electrolyte samples. For Trimsol, the best performance was achieved with the silver-nitrate system at high acid concentrations, temperatures, and current densities. Destruction efficiencies of 98% or greater and coulombic efficiencies close to 50% were obtained in both small- and large-scale systems. For the cellulose, high destruction efficiencies and reasonable coulombic efficiencies were obtained for both silver-nitrate and cobalt-sulfate systems.

Chiba, Z.; Lewis, P.R.; Kahle, R.W.

1993-03-01T23:59:59.000Z

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


161

TRU decontamination of high-level Purex waste by solvent extraction using a mixed octyl(phenyl)-N,N-diisobutyl-carbamoylmethylphosphine oxide/TBP/NPH (TRUEX) solvent  

SciTech Connect

The TRUEX (transuranium extraction) process was tested on a simulated high-level dissolved sludge waste (DSW). A batch counter-current extraction mode was used for seven extraction and three scrub stages. One additional extraction stage and two scrub stages and all strip stages were performed by batch extraction. The TRUEX solvent consisted of 0.20 M octyl(phenyl)-N,N-diisobutylcarbamoyl-methylphosphine oxide-1.4 M TBP in Conoco (C/sub 12/-C/sub 14/). The feed solution was 1.0 M in HNO/sub 3/, 0.3 M in H/sub 2/C/sub 2/O/sub 4/ and contained mixed (stable) fission products, U, Np, Pu, and Am, and a number of inert constituents, e.g., Fe and Al. The test showed that the process is capable of reducing the TRU concentration in the DSW by a factor of 4 x 10/sup 4/ (to <100 nCi/g of disposed form) and reducing the quantity of TRU waste by two orders of magnitude.

Horwitz, E.P.; Kalina, D.G.; Diamond, H.; Kaplan, L.; Vandegrift, G.F.; Leonard, R.A.; Steindler, M.J.; Schulz, W.W.

1984-01-01T23:59:59.000Z

162

Waste Form Development for the Solidification of PDCF/MOX Liquid Waste Streams  

SciTech Connect

At the Savannah River Site, part of the Department of Energy's nuclear materials complex located in South Carolina, cementation has been selected as the solidification method for high-alpha and low-activity waste streams generated in the planned plutonium disposition facilities. A Waste Solidification Building (WSB) that will be used to treat and solidify three radioactive liquid waste streams generated by the Pit Disassembly and Conversion Facility) and the Mixed Oxide Fuel Fabrication Facility is in the preliminary design stage. The WSB is expected to treat a transuranic (TRU) waste stream composed primarily of americium and two low-level waste (LLW) streams. The acidic wastes will be concentrated in the WSB evaporator and neutralized in a cement head tank prior to solidification. A series of TRU mixes were prepared to produce waste forms exhibiting a range of processing and cured properties. The LLW mixes were prepared using the premix from the preferred TRU waste form. All of the waste forms tested passed the Toxicity Characteristic Leaching Procedure. After processing in the WSB, current plans are to dispose of the solidified TRU waste at the Waste Isolation Pilot Plant in New Mexico and the solidified LLW waste at an approved low-level waste disposal facility.

COZZI, ALEX

2004-02-18T23:59:59.000Z

163

Waste Form Development for the Solidification of PDCF/MOX Liquid Waste Streams  

SciTech Connect

At the Savannah River Site, part of the Department of Energy's nuclear materials complex located in South Carolina, cementation has been selected as the solidification method for high-alpha and low-activity waste streams generated in the planned plutonium disposition facilities. A Waste Solidification Building (WSB) that will be used to treat and solidify three radioactive liquid waste streams generated by the Pit Disassembly and Conversion Facility) and the Mixed Oxide Fuel Fabrication Facility is in the preliminary design stage. The WSB is expected to treat a transuranic (TRU) waste stream composed primarily of americium and two low-level waste (LLW) streams. The acidic wastes will be concentrated in the WSB evaporator and neutralized in a cement head tank prior to solidification. A series of TRU mixes were prepared to produce waste forms exhibiting a range of processing and cured properties. The LLW mixes were prepared using the premix from the preferred TRU waste form. All of the waste forms tested passed the Toxicity Characteristic Leaching Procedure. After processing in the WSB, current plans are to dispose of the solidified TRU waste at the Waste Isolation Pilot Plant in New Mexico and the solidified LLW waste at an approved low-level waste disposal facility.

COZZI, ALEX

2004-02-18T23:59:59.000Z

164

Nuclear data uncertainties by the PWR MOX/UO{sub 2} core rod ejection benchmark  

Science Conference Proceedings (OSTI)

Rod ejection transient of the OECD/NEA and U.S. NRC PWR MOX/UO{sub 2} core benchmark is considered under the influence of nuclear data uncertainties. Using the GRS uncertainty and sensitivity software package XSUSA the propagation of the uncertainties in nuclear data up to the transient calculations are considered. A statistically representative set of transient calculations is analyzed and both integral as well as local output quantities are compared with the benchmark results of different participants. It is shown that the uncertainties in nuclear data play a crucial role in the interpretation of the results of the simulation. (authors)

Pasichnyk, I.; Klein, M.; Velkov, K.; Zwermann, W.; Pautz, A. [Boltzmannstr. 14, D-85748 Garching b. Muenchen (Germany)

2012-07-01T23:59:59.000Z

165

Analysis of the IFA-432, IFA-597, and IFA-597 MOX Fuel Performance Experiments by FRAPCON-3.4  

SciTech Connect

Validation of advanced nuclear fuel modeling tools requires careful comparison with reliable experimental benchmark data. A comparison to industry-accepted codes, that are well characterized, and regulatory codes is also a useful evaluation tool. In this report, an independent validation of the FRAPCON-3.4 fuel performance code is conducted with respect to three experimental benchmarks, IFA-432, IFA-597, and IFA-597mox. FRAPCON was found to most accurately model the mox rods, to within 2% of the experimental data, depending on the simulation parameters. The IFA-432 and IFA-597 rods were modeled with FRAPCON predicting centerline temperatures different, on average, by 21 percent.

Phillippe, Aaron M [ORNL; Ott, Larry J [ORNL; Clarno, Kevin T [ORNL; Banfield, James E [ORNL

2012-08-01T23:59:59.000Z

166

Full Core 3-D Simulation of a Partial MOX LWR Core  

Science Conference Proceedings (OSTI)

A comparative analysis and comparison of results obtained between 2-D lattice calculations and 3-D full core nodal calculations, in the frame of MOX fuel design, was conducted. This study revealed a set of advantages and disadvantages, with respect to each method, which can be used to guide the level of accuracy desired for future fuel and fuel cycle calculations. For the purpose of isotopic generation for fuel cycle analyses, the approach of using a 2-D lattice code (i.e., fuel assembly in infinite lattice) gave reasonable predictions of uranium and plutonium isotope concentrations at the predicted 3-D core simulation batch average discharge burnup. However, it was found that the 2-D lattice calculation can under-predict the power of pins located along a shared edge between MOX and UO2 by as much as 20%. In this analysis, this error did not occur in the peak pin. However, this was a coincidence and does not rule out the possibility that the peak pin could occur in a lattice position with high calculation uncertainty in future un-optimized studies. Another important consideration in realistic fuel design is the prediction of the peak axial burnup and neutron fluence. The use of 3-D core simulation gave peak burnup conditions, at the pellet level, to be approximately 1.4 times greater than what can be predicted using back-of-the-envelope assumptions of average specific power and irradiation time.

S. Bays; W. Skerjanc; M. Pope

2009-05-01T23:59:59.000Z

167

Irradiation performance of fast reactor MOX fuel pins with ferritic/martensitic cladding irradiated to high burnups  

Science Conference Proceedings (OSTI)

The ACO-3 irradiation test, which attained extremely high burnups of about 232 GWd/t and resisted a high neutron fluence (E > 0.1 MeV) of about 39 × 1026 n/m2 as one of the lead tests of the Core Demonstration Experiment in the Fast Flux Test Facility, demonstrated that the fuel pin cladding made of ferritic/martensitic HT-9 alloy had superior void swelling resistance. The measured diameter profiles of the irradiated ACO-3 fuel pins showed axially extensive incremental strain in the MOX fuel column region and localized incremental strain near the interfaces between the MOX fuel and upper blanket columns. These incremental strains were as low as 1.5% despite the extremely high level of the fast neutron fluence. Evaluation of the pin diametral strain indicated that the incremental strain in the MOX fuel column region was substantially due to cladding void swelling and irradiation creep caused by internal fission gas pressure, while the localized strain near the MOX fuel/upper blanket interface was likely the result of the pellet/cladding mechanical interaction (PCMI) caused by cesium/fuel reactions. The evaluation also suggested that the PCMI was effectively mitigated by a large gap size between the cladding and blanket column.

Tomoyuki Uwaba; Masahiro Ito; Kozo Katsuyama; Bruce J. Makenas; David W. Wootan; Jon Carmack

2011-05-01T23:59:59.000Z

168

Irradiation performance of fast reactor MOX fuel pins with ferritic/martensitic cladding irradiated to high burnups  

Science Conference Proceedings (OSTI)

The ACO-3 irradiation test, which attained extremely high burnups of about 232 GWd/t and resisted a high neutron fluence (E > 0.1 MeV) of about 39E26 n/m2 as one of the lead tests of the Core Demonstration Experiment in the Fast Flux Test Facility, demonstrated that the fuel pin cladding made of ferritic/martensitic HT-9 alloy had superior void swelling resistance. The measured diameter profiles of the irradiated ACO-3 fuel pins showed axially extensive incremental strain in the MOX fuel column region and localized incremental strain near the interfaces between the MOX fuel and upper blanket columns. These incremental strains were as low as 1.5% despite the extremely high level of the fast neutron fluence. Evaluation of the pin diametral strain indicated that the incremental strain in the MOX fuel column region was substantially due to cladding void swelling and irradiation creep caused by internal fission gas pressure, while the localized strain near the MOX fuel/upper blanket interface was likely the result of the pellet/cladding mechanical interaction (PCMI) caused by cesium/fuel reactions. The evaluation also suggested that the PCMI was effectively mitigated by a large gap size between the cladding and blanket column.

Uwaba, Tomoyuki; Ito, Masahiro; Mizuno, Tomoyasu; Katsuyama, Kozo; Makenas, Bruce J.; Wootan, David W.; Carmack, Jon

2011-06-16T23:59:59.000Z

169

ANALYTICAL RESULTS FOR MOX COLEMANITE CONCRETE SAMPLES RECEIVED ON NOVEMBER, 2013  

SciTech Connect

The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory (SRNL) is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. SRNL received two samples of colemanite concrete for analysis on November 21, 2013. The average total density of each of the samples measured by the ASTM method C 642, the average partial hydrogen density was measured using method ASTM E 1131, and the average partial boron density of each sample was measured according to ASTM C 1301. For all the samples tested, the total density and the boron partial density met or exceeded the specified limit. None of the samples met the lower limit for hydrogen partial density.

Reigel, M.

2013-12-18T23:59:59.000Z

170

ANALYTICAL RESULTS FOR MOX COLEMANITE CONCRETE SAMPLES RECEIVED ON SEPTEMBER 4, 2013  

SciTech Connect

The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory (SRNL) is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. SRNL received three samples of colemanite concrete for analysis on September 4, 2013. The average total density of each of the samples measured by the ASTM method C 642, the average partial hydrogen density was measured using method ASTM E 1131, and the average partial boron density of each sample was measured according to ASTM C 1301. The lower limits and measured values for the total density, hydrogen partial density, and boron partial density are presented. For all the samples tested, the total density and the boron partial density met or exceeded the specified limit. None of the samples met the lower limit for hydrogen partial density.

Reigel, M.

2013-09-24T23:59:59.000Z

171

IMPACT OF FISSION PRODUCTS IMPURITY ON THE PLUTONIUM CONTENT IN PWR MOX FUELS  

Science Conference Proceedings (OSTI)

This report presents the results of a neutronics analysis done in response to the charter IFCA-SAT-2 entitled 'Fuel impurity physics calculations'. This charter specifies that the separation of the fission products (FP) during the reprocessing of UOX spent nuclear fuel assemblies (UOX SNF) is not perfect and that, consequently, a certain amount of FP goes into the Pu stream used to fabricate PWR MOX fuel assemblies. Only non-gaseous FP have been considered (see the list of 176 isotopes considered in the calculations in Appendix 1). This mixture of Pu and FP is called PuFP. Note that, in this preliminary analysis, the FP losses are considered element-independent, i.e., for example, 1% of FP losses mean that 1% of all non-gaseous FP leak into the Pu stream.

Gilles Youinou; Andrea Alfonsi

2012-03-01T23:59:59.000Z

172

Research Programme for the 660 Mev Proton Accelerator Driven MOX-Plutonium Subcritical Assembly  

E-Print Network (OSTI)

The paper presents a research programme of the Experimental Acclerator Driven System (ADS), which employs a subcritical assembly and a 660 MeV proton acceletator operating at the Laboratory of Nuclear Problems of the JINR, Dubna. MOX fuel (25% PuO_2 + 75% UO_2) designed for the BN-600 reactor use will be adopted for the core of the assembly. The present conceptual design of the experimental subcritical assembly is based on a core of a nominal unit capacity of 15 kW (thermal). This corresponds to the multiplication coefficient k_eff = 0.945, energetic gain G = 30 and the accelerator beam power 0.5 kW.

Barashenkov, V S; Buttseva, G L; Dudarev, S Yu; Polanski, A; Puzynin, I V; Sissakian, A N

2000-01-01T23:59:59.000Z

173

Integration Strategy for DB-MHR TRISO Fuel production in conjunction with MOX Fuel production  

DOE Green Energy (OSTI)

One of the nuclear power options for the future involves the evolution of gas cooled reactors to support the likely high temperature operations needed for commercial scale hydrogen production. One such proposed option is to use a Gas Turbine Modular Helium Reactor fueled with uranium based TRISO (coated particle) fuel. It has also been suggested that such a MHR could be operated in a ''Deep Burn'' manner fueled with TRISO fuel produced from recycle spent nuclear fuel. This concept known as a DBMHR must withstand significant development and fuel fabrication cost to be economically viable. The purpose of this report is to consider and propose a strategy where synergy with a parallel MOX fuel to LWR program provides economic or other advantage for either or both programs. A strategy involving three phases has been envisioned with potential for economic benefit relative to a stand-alone TRISO/DBMHR program. Such a strategy and related timing will ultimately be driven by economics, but is offered here for consideration of value to the total AFCI program. Phase I Near-term. Conventional spent fuel aqueous processing, MOX fuel fabrication, and use of present and future LWR/ALWR's with objective of a ''Continuous Recycle'' mode of fuel cycle management. Phase II Intermediate. Augmentation of LWR/ALWR industry with MHR deployment as justified by hydrogen economy and/or electrical demand. Phase III Long-term. Introduction of DBMHR's to offer alternative method for transuranic destruction and associated repository benefits, in addition to Phase II benefits. The basic philosophy of this strategy appears sound. However, the details of the technology plans and economic evaluations should receive additional detail and evaluation in the next fiscal year as funding can support.

MCGUIRE, DAVID

2005-09-30T23:59:59.000Z

174

WIMS/PANTHER analysis of UO{sub 2}/MOX cores using embedded super-cells  

Science Conference Proceedings (OSTI)

This paper describes a method of analysing PWR UO{sub 2}MOX cores with WIMS/PANTHER. Embedded super-cells, run within the reactor code, are used to correct the standard methodology of using 2-group smeared data from single assembly lattice calculations. In many other codes the weakness of this standard approach has been improved for MOX by imposing a more realistic environment in the lattice code, or by improving the sophistication of the reactor code. In this approach an intermediate set of calculations is introduced, leaving both lattice and reactor calculations broadly unchanged. The essence of the approach is that the whole core is broken down into a set of 'embedded' super-cells, each extending over just four quarter assemblies, with zero leakage imposed at the assembly mid-lines. Each supercell is solved twice, first with a detailed multi-group pin-by-pin solution, and then with the standard single assembly approach. Correction factors are defined by comparing the two solutions, and these can be applied in whole core calculations. The restriction that all such calculations are modelled with zero leakage means that they are independent of each other and of the core-wide flux shape. This allows parallel pre-calculation for the entire cycle once the loading pattern has been determined, in much the same way that single assembly lattice calculations can be pre-calculated once the range of fuel types is known. Comparisons against a whole core pin-by-pin reference demonstrates that the embedding process does not introduce a significant error, even after burnup and refuelling. Comparisons against a WIMS reference demonstrate that a pin-by-pin multi-group diffusion solution is capable of capturing the main interface effects. This therefore defines a practical approach for achieving results close to lattice code accuracy, but broadly at the cost of a standard reactor calculation. (authors)

Knight, M.; Bryce, P. [EDF Energy, Barnett Way, Barnwood, Gloucester (United Kingdom); Hall, S. [Advanced Modelling and Computation Group, Imperial College, London (United Kingdom)

2012-07-01T23:59:59.000Z

175

TRIPOLI-4 criticality calculations for MOX fuelled SNEAK 7A and 7B fast critical assemblies  

SciTech Connect

A prototype Generation IV fast neutron reactor is under design and development in France. The MOX fuel will be introduced into this self-generating core in order to demonstrate low net plutonium production. To support the TRIPOLI-4 Monte Carlo transport code in criticality calculations of fast reactors, the effective delayed neutron fraction {beta}eff estimation and the Probability Tables (PT) option to treat the unresolved resonance region of cross-sections are two essentials. In this study, TRIPOLI-4 calculations have been made using current nuclear data libraries JEFF-3.1.1 and ENDF/B-VII.0 to benchmark the reactor physics parameters of the MOX fuelled SNEAK 7A and 7B fast critical assemblies. TRIPOLI-4 calculated K{sub eff} and {beta}eff of the homogeneous R-Z models and the 3D multi-cell models have been validated against the measured ones. The impact of the PT option on K{sub eff} is 340 {+-} 10 pcm for SNEAK 7A core and 410 {+-} 12 pcm for 7B. Four-group spectra and energy spectral indices, f8/f5, f9/f5, and c8/f5 in the two SNEAK cores have also been calculated with the TRIPOLI-4 mesh tally. Calculated spectrum-hardening index f8/f5 is 0.0418 for SNEAK 7A and 0.0315 for 7B. From this study the SNEAK 3D models have been verified for the next revision of IRPhE (International Handbook of Evaluated Reactor Physics Benchmark Experiments). (authors)

Lee, Y. K. [Commissariat a l'Energie Atomique et aux Energies Alternatives, CEA-Saclay, DEN/DANS/DM2S/SERMA, 91191 Gif sur Yvette Cedex (France)

2012-07-01T23:59:59.000Z

176

Audit Report: IG-0887 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

7 7 Audit Report: IG-0887 May 15, 2013 The Use of Staff Augmentation Subcontracts at the National Nuclear Security Administration's Mixed Oxide Fuel Fabrication Facility Shaw AREVA MOX Services, LLC (MOX Services) is responsible for the design and construction of the National Nuclear Security Administration's (NNSA) nearly $5 billion Mixed Oxide Fuel Fabrication Facility (MOX Project) at the Savannah River Site near Aiken, South Carolina. The facility will remove impurities from surplus weapons-grade plutonium and mix it with depleted uranium oxide to form fuel pellets for commercial nuclear power reactors. MOX Services used staff augmentation subcontracts to fill professional, technical and administrative support service positions on an as-needed basis on the MOX Project. According to MOX Services officials, a shortage

177

A Modeling Study of Atmospheric Transport and Photochemistry in the Mixed Layer during Anticyclonic Episodes in Europe. Part II. Calculations of Photo-Oxidant Levels along Air Trajectories  

Science Conference Proceedings (OSTI)

A computer model for photochemical oxidant formation in the atmospheric boundary layer has been used to calculate trends in ozone formation in air masses traveling across Europe. Ozone calculations were made for some actual summertime ...

K. Selby

1987-10-01T23:59:59.000Z

178

Analytical Results Of MOX Colemanite Concrete Sample PBC-44.2  

SciTech Connect

The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. Sample PBC-44.2 was received on 9/20/2012 and analyzed. The average total density measured by the ASTM method C 642 was 2.03 g/cm{sup 3}, within the lower bound of 1.88 g/cm{sup 3}. The average partial hydrogen density was 6.64E-02 g/cm{sup 3} as measured using method ASTM E 1311 and met the lower bound of 6.04E-02 g/cm{sup 3}. The average measured partial boron density was 1.97E-01 g/cm{sup 3} which met the lower bound of 1.65E-01 g/cm{sup 3} measured by the ASTM C 1301 method.

Cozzi, A. D.; Best, D. R.; Reigel, M. M.

2012-10-18T23:59:59.000Z

179

ANALYTICAL RESULTS OF MOX COLEMANITE CONCRETE SAMPLE PBC-44.2  

SciTech Connect

The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. Sample PBC-44.2 was received on 9/20/2012 and analyzed. The average total density measured by the ASTM method C 642 was 2.03 g/cm{sup 3}, within the lower bound of 1.88 g/cm3. The average partial hydrogen density was 6.64E-02 g/cm{sup 3} as measured using method ASTM E 1311 and met the lower bound of 6.04E-02 g/cm{sup 3}. The average measured partial boron density was 1.70E-01 g/cm{sup 3} which met the lower bound of 1.65E-01 g/cm{sup 3} measured by the ASTM C 1301 method.

Best, D.; Cozzi, A.; Reigel, M.

2012-12-20T23:59:59.000Z

180

ANALYTICAL RESULTS OF MOX COLEMANITE CONCRETE SAMPLES POURED AUGUST 29, 2012  

SciTech Connect

The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. Samples poured 8/29/12 were received on 9/20/2012 and analyzed. The average total density of each of the samples measured by the ASTM method C 642 was within the lower bound of 1.88 g/cm{sup 3}. The average partial hydrogen density of samples 8.6.1, 8.7.1, and 8.5.3 as measured using method ASTM E 1311 met the lower bound of 6.04E-02 g/cm{sup 3}. The average measured partial boron density of each sample met the lower bound of 1.65E-01 g/cm{sup 3} measured by the ASTM C 1301 method. The average partial hydrogen density of samples 8.5.1, 8.6.3, and 8.7.3 did not meet the lower bound. The samples, as received, were not wrapped in a moist towel as previous samples and appeared to be somewhat drier. This may explain the lower hydrogen partial density with respect to previous samples.

Best, D.; Cozzi, A.; Reigel, M.

2012-12-20T23:59:59.000Z

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


181

ANALYTICAL RESULTS OF MOX COLEMANITE CONCRETE SAMPLE PBC-44.2  

Science Conference Proceedings (OSTI)

The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. Sample PBC-44.2 was received on 9/20/2012 and analyzed. The average total density measured by the ASTM method C 642 was 2.03 g/cm{sup 3}, within the lower bound of 1.88 g/cm{sup 3}. The average partial hydrogen density was 6.64E-02 g/cm{sup 3} as measured using method ASTM E 1311 and met the lower bound of 6.04E-02 g/cm{sup 3}. The average measured partial boron density was 1.97E-01 g/cm{sup 3} which met the lower bound of 1.65E-01 g/cm{sup 3} measured by the ASTM C 1301 method.

Cozzi, A.; Best, D.; Reigel, M.

2012-10-18T23:59:59.000Z

182

ANALYTICAL RESULTS OF MOX COLEMANITE CONCRETE SAMPLES POURED AUGUST 29, 2012  

SciTech Connect

The Mixed Oxide Fuel Fabrication Facility (MFFF) will use colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. Samples poured 8/29/12 were received on 9/20/2012 and analyzed. The average total density of each of the samples measured by the ASTM method C 642 was within the lower bound of 1.88 g/cm{sup 3}. The average partial hydrogen density of samples 8.6.1, 8.7.1, and 8.5.3 as measured using method ASTM E 1311 met the lower bound of 6.04E-02 g/cm{sup 3}. The average measured partial boron density of each sample met the lower bound of 1.65E-01 g/cm{sup 3} measured by the ASTM C 1301 method. The average partial hydrogen density of samples 8.5.1, 8.6.3, and 8.7.3 did not meet the lower bound. The samples, as received, were not wrapped in a moist towel as previous samples and appeared to be somewhat drier. This may explain the lower hydrogen partial density with respect to previous samples.

Cozzi, A.; Best, D.; Reigel, M.

2012-10-30T23:59:59.000Z

183

ANALYTICAL RESULTS OF MOX COLEMANITE CONCRETE SAMPLE POURED JULY 25, 2012 - CURED 28 DAYS  

SciTech Connect

The Mixed Oxide Fuel Fabrication Facility (MFFF) will use Colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses and shielding operators from radiation. The Savannah River National Laboratory is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. Samples 8.1.2, 8.2.2, 8.3.2, and 8.4.2 were received on 8/1/2012 and analyzed after curing for 28 days. The average total density measured by the ASTM method C 642 was 2.09 g/cm{sup 3}, within the lower bound of 1.88 g/cm{sup 3}. The average partial hydrogen density was 7.48E-02 g/cm{sup 3} as measured using method ASTM E 1311 and met the lower bound of 6.04E-02 g/cm{sup 3}. The average measured partial boron density was 1.71E-01 g/cm{sup 3} which met the lower bound of 1.65E-01 g/cm{sup 3} measured by the ASTM C 1301 method.

Cozzi, A. D.; Best, D. R.; Reigel, M. M.

2012-09-18T23:59:59.000Z

184

ANALYTICAL RESULTS OF MOX COLEMANITE CONCRETE SAMPLE POURED MAY 4, 2012  

DOE Green Energy (OSTI)

The Mixed Oxide Fuel Fabrication Facility (MFFF) will use Colemanite bearing concrete neutron absorber panels credited with attenuating neutron flux in the criticality design analyses. The Savannah River National Laboratory is tasked with measuring the total density, partial hydrogen density, and partial boron density of the colemanite concrete. Sample 04 May 12/Test/S1-1, S1-2, and S1-3 was received on 5/9/2012 and analyzed. The total density measure by the ASTM method C 642 was 2.00 g/cm{sup 3}, within the lower bound of 1.88 g/cm{sup 3}. The partial hydrogen density of 6.35E-02 g/cm{sup 3} as measured using method ASTM E 1311 met the lower bound of 6.04E-02 g/cm{sup 3}. The measured partial boron density of 1.88E-01 g/cm{sup 3} exceeded the lower bound of 1.65E-01 g/cm{sup 3} when the sodium peroxide fusion dissolution method was used in place of the prescribed ASTM C 1301 method.

Cozzi, A.; Best, D.; Reigel, M.

2012-06-14T23:59:59.000Z

185

Release and disposal of materials during decommissioning of Siemens MOX fuel fabrication plant at Hanau, Germany  

SciTech Connect

In September 2006, decommissioning and dismantling of the Siemens MOX Fuel Fabrication Plant in Hanau were completed. The process equipment and the fabrication buildings were completely decommissioned and dismantled. The other buildings were emptied in whole or in part, although they were not demolished. Overall, the decommissioning process produced approximately 8500 Mg of radioactive waste (including inactive matrix material); clearance measurements were also performed for approximately 5400 Mg of material covering a wide range of types. All the equipment in which nuclear fuels had been handled was disposed of as radioactive waste. The radioactive waste was conditioned on the basis of the requirements specified for the projected German final disposal site 'Schachtanlage Konrad'. During the pre-conditioning, familiar processes such as incineration, compacting and melting were used. It has been shown that on account of consistently applied activity containment (barrier concept) during operation and dismantling, there has been no significant unexpected contamination of the plant. Therefore almost all the materials that were not a priori destined for radioactive waste were released without restriction on the basis of the applicable legal regulations (chap. 29 of the Radiation Protection Ordinance), along with the buildings and the plant site. (authors)

Koenig, Werner [TUEV NORD EnSys Hannover GmbH and Co. KG (Germany); Baumann, Roland [Siemens AG, Power Generation (Germany)

2007-07-01T23:59:59.000Z

186

EIS-0283-S2: DOE Notice of Availability of the Draft Supplemental...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

and conversion of plutonium metal to oxide and the potential use of mixed oxide (MOX) fuel in reactors at the Sequoyah and Browns Ferry Nuclear Plants of the Tennessee...

187

Characterization and electrocatalytic properties of titanium-based Ru0.3Co0.7-xCex mixed oxide electrodes for oxygen evolution in alkaline solution  

Science Conference Proceedings (OSTI)

Ti-supported RuO2-Co3O4-CeO2 (Ru0.3Co0.7-xCex oxide, 0 ? x ? 0.7) electrodes were prepared by sol-gel process. The phase structure, surface ...

Hongjun Wu; Qin Ruan; Li Li; Baohui Wang

2011-01-01T23:59:59.000Z

188

Band offsets and heterostructures of two-dimensional semiconductors Sefaattin Tongay,2  

E-Print Network (OSTI)

lattice of the oxide anode, forming so-called higher metal oxides (MOx+1), and that these higher oxide be detailed as shown below, where MOx stands for the oxide anode and R stands for the organic pollutant MOx + H2O ! MOx [� OH] + Hþ + e� ð1� MOx[� OH] + R ! CO2 + MOx ð2� MOx [� OH] ! MOxþ1 þ Hþ + e� ð3� MOxþ1

Wu, Junqiao

189

THERMAL EVALUATION OF THE USE OF BWR MOX SNF IN THE MULTI-PURPOSE CANISTER (MPC) WITH ACD DISPOSAL CONTAINER (SCPB: N/A)  

SciTech Connect

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) as specified in the Waste Package Implementation Plan (pp. 4-8,4-11,4-24,5-1, and 5-13; Ref. 5.10) and Waste Package Plan (pp. 3-15,3-17, and 3-24; Ref. 5.9). The design data request addressed herein is: (1) Characterize the conceptual 40 BWR Multi-Purpose Canister (MPC) Waste Package (WP) design to show that the design is feasible for use in the MGDS environment when loaded with BWR MOX SNF. (2) Characterize the conceptual 24 BWR Multi-Purpose Canister (MPC) Waste Package (WP) design to show that the design is feasible for use in the MGDS environment when loaded with BWR MOX SNF. The purpose of this analysis is to respond a concern that the long-term disposal thermal issues for the Multi-Purpose Canister (MPC) Subsystem Design, if used with SNF designed for a MOX fuel cycle, do not preclude MPC compatibility with the MGDS. The objective of this analysis is to provide thermal parameter information for the conceptual MPC design with disposal container which is loaded with BWR MOX SNF under nominal MGDS repository conditions. The results are intended to show that the design has a reasonable chance to meet the MGDS design requirements for normal MGDS operation, to provide the required guidance to determining the major design issues for future design efforts, and to show that the BWR MOX SNF loaded MPC performance is similar to an MPC loaded with commercial BWR SNF. Future design efforts will focus on specific MPC vendor designs and BWR MOX SNF designs when they become available.

T.L. Lotz

1995-11-13T23:59:59.000Z

190

Synthesis and Characterization of Mixed-Conducting Corrosion Resistant Oxide Supports - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

NLE Websites -- All DOE Office Websites (Extended Search)

8 8 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Vijay K. Ramani (Primary Contact), Jai Prakash Illinois Institute of Technology (IIT) 10 W 33 rd Street 127 PH Chicago, IL 60616 Phone: (312) 567-3064 Email: ramani@iit.edu DOE Managers HQ: Kathi Epping Martin Phone: (202) 586-7425 Email: Kathi.Epping@ee.doe.gov GO: Katie Randolph Phone: (720) 356-1759 Email: Katie.Randolph@go.doe.gov Contract Number: DE-EE0000461 Subcontractor: Nissan Technical Center, North America (NTCNA) Farmington Hills, MI Project Start Date: September 1, 2010 Project End Date: August 31, 2013 Fiscal Year (FY) 2012 Objectives To develop and optimize innovative non-carbon mixed * conducting materials that will serve as corrosion resistant, high surface area supports for anode and

191

Thermal Oxidation of Titanium Wires  

Science Conference Proceedings (OSTI)

Structural and Thermal Study of Al2O3 Produced by Oxidation of Al-Powders Mixed with Corn Starch · Study of Silicon Carbide/Silicon Nitride Composite ...

192

Radiation shielding of high-energy neutrons in SAD P. Seltborg1  

E-Print Network (OSTI)

accelerator is cou- pled to a sub-critical core, loaded with fast reactor MOX (Mixed Oxide) fuel assemblies-critical highly enriched MOX-loaded core, driven by a 660 MeV proton beam impinging on a target of lead of the SAD core. The sub-critical core, loaded with fast-reactor MOX fuel, is driven by a 660 MeV proton beam

193

Accident source terms for light-water nuclear power plants using high-burnup or MOX fuel.  

Science Conference Proceedings (OSTI)

Representative accident source terms patterned after the NUREG-1465 Source Term have been developed for high burnup fuel in BWRs and PWRs and for MOX fuel in a PWR with an ice-condenser containment. These source terms have been derived using nonparametric order statistics to develop distributions for the timing of radionuclide release during four accident phases and for release fractions of nine chemical classes of radionuclides as calculated with the MELCOR 1.8.5 accident analysis computer code. The accident phases are those defined in the NUREG-1465 Source Term - gap release, in-vessel release, ex-vessel release, and late in-vessel release. Important differences among the accident source terms derived here and the NUREG-1465 Source Term are not attributable to either fuel burnup or use of MOX fuel. Rather, differences among the source terms are due predominantly to improved understanding of the physics of core meltdown accidents. Heat losses from the degrading reactor core prolong the process of in-vessel release of radionuclides. Improved understanding of the chemistries of tellurium and cesium under reactor accidents changes the predicted behavior characteristics of these radioactive elements relative to what was assumed in the derivation of the NUREG-1465 Source Term. An additional radionuclide chemical class has been defined to account for release of cesium as cesium molybdate which enhances molybdenum release relative to other metallic fission products.

Salay, Michael (U.S. Nuclear Regulatory Commission, Washington, D.C.); Gauntt, Randall O.; Lee, Richard Y. (U.S. Nuclear Regulatory Commission, Washington, D.C.); Powers, Dana Auburn; Leonard, Mark Thomas

2011-01-01T23:59:59.000Z

194

RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO[2] fuel and MOX fuel  

E-Print Network (OSTI)

A RELAP5/MOD3.2 model of a VVER-1000/MODEL V320 nuclear power plant, Balakovo Unit 4, was updated, improved and validated on the basis of an input deck prepared by the Kurchatov Institute of Moscow. The RELAP5 model includes both the primary and the secondary systems. The Emergency Core Cooling System (ECCS) is modeled according to the plant configuration. The feedwater system, along with the emergency feedwater system, is included in the model. The point reactor kinetics model, in which the decay heat is calculated with ANS decay heat data, enables the model to be used for analysis of a large spectrum of transients and accidents. The plant model is used for analysis and prediction of a cold leg Large Break Loss-of-Coolant Accident (LBLOCA). The RELAP5/MOD3.2 results showed a good agreement with calculations obtained with TECH-M computer program. The cladding temperatures of the MOX assembly have been compared with that of the hot UO? assembly. The peak cladding temperature of MOX assembly is about 55 K higher than that of UO? assembly. An uncertainty analysis has been performed for the peak cladding temperature, in which Monte Carlo calculations have been performed using the response surface built up from fifteen sets of RELAP5 calculations. The result shows that the ECCS would be sufficient to keep the cladding temperature during the scenario of a LBLOCA well below the required licensing limit.

Fu, Chun

2000-01-01T23:59:59.000Z

195

In-Situ Evidence for Uranium Immobilization and Remobilization  

E-Print Network (OSTI)

, together with depleted uranium, for fabrication of mixed oxide fuel (MOX) for reuse in a light water with depleted uranium to produce a metallic fuel for a fast reactor. The fast reactor can be designed to produce of depleted uranium and the cost of fabricating the MOX fuel: ( ) ( ) 2,22,22,22,2 bpzupf ++= . (11) The back

Istok, Jonathan "Jack"

196

U.S. Department of Energy Journal of Undergraduate Research 203 http://www.scied.science.doe.gov  

E-Print Network (OSTI)

, together with depleted uranium, for fabrication of mixed oxide fuel (MOX) for reuse in a light water with depleted uranium to produce a metallic fuel for a fast reactor. The fast reactor can be designed to produce of depleted uranium and the cost of fabricating the MOX fuel: ( ) ( ) 2,22,22,22,2 bpzupf ++= . (11) The back

197

Template synthesis and surface modification of metal oxides.  

E-Print Network (OSTI)

??Porous metal oxide monoliths, specifically silica, titania, zirconia and mixed oxides containing aluminum and yttrium, were prepared in a one-pot synthesis. Macroporosity was induced using… (more)

Drisko, Glenna Lynn

2010-01-01T23:59:59.000Z

198

ZPR-6 assembly 7 high {sup 240} PU core : a cylindrical assemby with mixed (PU, U)-oxide fuel and a central high {sup 240} PU zone.  

Science Conference Proceedings (OSTI)

Over a period of 30 years more than a hundred Zero Power Reactor (ZPR) critical assemblies were constructed at Argonne National Laboratory. The ZPR facilities, ZPR-3, ZPR-6, ZPR-9 and ZPPR, were all fast critical assembly facilities. The ZPR critical assemblies were constructed to support fast reactor development, but data from some of these assemblies are also well suited to form the basis for criticality safety benchmarks. Of the three classes of ZPR assemblies, engineering mockups, engineering benchmarks and physics benchmarks, the last group tends to be most useful for criticality safety. Because physics benchmarks were designed to test fast reactor physics data and methods, they were as simple as possible in geometry and composition. The principal fissile species was {sup 235}U or {sup 239}Pu. Fuel enrichments ranged from 9% to 95%. Often there were only one or two main core diluent materials, such as aluminum, graphite, iron, sodium or stainless steel. The cores were reflected (and insulated from room return effects) by one or two layers of materials such as depleted uranium, lead or stainless steel. Despite their more complex nature, a small number of assemblies from the other two classes would make useful criticality safety benchmarks because they have features related to criticality safety issues, such as reflection by soil-like material. The term 'benchmark' in a ZPR program connotes a particularly simple loading aimed at gaining basic reactor physics insight, as opposed to studying a reactor design. In fact, the ZPR-6/7 Benchmark Assembly (Reference 1) had a very simple core unit cell assembled from plates of depleted uranium, sodium, iron oxide, U3O8, and plutonium. The ZPR-6/7 core cell-average composition is typical of the interior region of liquid-metal fast breeder reactors (LMFBRs) of the era. It was one part of the Demonstration Reactor Benchmark Program,a which provided integral experiments characterizing the important features of demonstration-size LMFBRs. As a benchmark, ZPR-6/7 was devoid of many 'real' reactor features, such as simulated control rods and multiple enrichment zones, in its reference form. Those kinds of features were investigated experimentally in variants of the reference ZPR-6/7 or in other critical assemblies in the Demonstration Reactor Benchmark Program.

Lell, R. M.; Schaefer, R. W.; McKnight, R. D.; Tsiboulia, A.; Rozhikhin, Y.; Nuclear Engineering Division; Inst. of Physics and Power Engineering

2007-10-01T23:59:59.000Z

199

Microsoft Word - Document in Microsoft Internet Explorer  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Status of the Mixed Oxide Fuel Status of the Mixed Oxide Fuel Fabrication Facility DOE/IG-0713 December 2005 STATUS OF THE MIXED OXIDE FUEL FABRICATION FACILITY TABLE OF CONTENTS MOX Facility Design Costs Details of Finding 1 Recommendations 5 Comments 6 Appendices Objective, Scope, and Methodology 9 Prior Audit Reports 11 Management Comments 12 MOX Facility Design Costs Page 1 Details of Finding Design and The audit disclosed that the cost of the Mixed Oxide Fuel Construction Budget Facility (MOX) will significantly exceed the amounts reported to Congress. As of July 2005, the National Nuclear Security Administration's (NNSA's) unvalidated estimate for the design and construction of the MOX Facility was about $3.5 billion, which is

200

EIS-0283: Notice of Intent to Prepare a Supplement to the Draft...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

the SPD Draft EIS by examining the potential environmental impacts of using mixed oxide (MOX) fuel in six specific commercial nuclear reactors at three sites for the disposition of...

Note: This page contains sample records for the topic "mox mixed oxide" from the National Library of EnergyBeta (NLEBeta).
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201

CX-009593: Categorical Exclusion Determination | Department of...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

The F-Area Inner Loop Road will be widened to accommodate increased mixed oxide fuel (MOX) traffic through F-Area. CX-009593.pdf More Documents & Publications CX-010308:...

202

Experiment Safety Assurance Package for the 40- to 50-GWd/MT Burnup Phase of Mixed Oxide Fuel Irradiation in Small I-Hole Positions in the Advanced Test Reactor  

SciTech Connect

This experiment safety assurance package (ESAP) is a revision of the last MOX ESAP issued in February 2001(Khericha 2001). The purpose of this revision is to identify the changes in the loading pattern and to provide a basis to continue irradiation up to ~42 GWd/MT burnup (+ 2.5% as predicted by MCNP (Monte Carlo N-Particle) transport code before the preliminary postirradiation examination (PIE) results for 40 GWd/MT burnup are available. Note that the safety analysis performed for the last ESAP is still applicable and no additional analysis is required (Khericha 2001). In July 2001, it was decided to reconfigure the test assembly using the loading pattern for Phase IV, Part 3, at the end of Phase IV, Part 1, as the loading pattern for Phase IV, Parts 2 and 3. Three capsule assemblies will be irradiated until the highest burnup capsule assembly accumulates: ~50 GWd/MT burnup, based on the MCNP code predictions. The last ESAP suggests that at the end of Phase IV, Part 1, we remove the two highest burnup capsule assemblies (@ ~40 GWd/MT burnup) and send them to ORNL for PIE. Then, irradiate the test assembly using the loading pattern for Phase IV, Part 2, until the highest burnup capsule reaches ~40 GWd/MT burnup per MCNP-predicted values.

Khericha, Soli T

2002-06-01T23:59:59.000Z

203

Experiment Safety Assurance Package for the 40- to 50-GWd/MT Burnup Phase of Mixed Oxide Fuel Irradiation in Small I-Hole Positions in the Advanced Test Reactor  

SciTech Connect

This experiment safety assurance package (ESAP) is a revision of the last MOX ESAP issued in February 2001(Khericha 2001). The purpose of this revision is to identify the changes in the loading pattern and to provide a basis to continue irradiation up to {approx}42 GWd/MT burnup (+ 2.5%) as predicted by MCNP (Monte Carlo N-Particle) transport code before the preliminary postirradiation examination (PIE) results for 40 GWd/MT burnup are available. Note that the safety analysis performed for the last ESAP is still applicable and no additional analysis is required (Khericha 2001). In July 2001, it was decided to reconfigure the test assembly using the loading pattern for Phase IV, Part 3, at the end of Phase IV, Part 1, as the loading pattern for Phase IV, Parts 2 and 3. Three capsule assemblies will be irradiated until the highest burnup capsule assembly accumulates: {approx}50 GWd/MT burnup, based on the MCNP code predictions. The last ESAP suggests that at the end of Phase IV, Part 1, we remove the two highest burnup capsule assemblies ({at} {approx}40 GWd/MT burnup) and send them to ORNL for PIE. Then, irradiate the test assembly using the loading pattern for Phase IV, Part 2, until the highest burnup capsule reaches {approx}40 GWd/MT burnup per MCNP-predicted values.

Khericha, S.T.

2002-06-30T23:59:59.000Z

204

Bacterial Production of Mixed Metal Oxide Nanoparticles ...  

... on the selection and tailoring of bacterial strains Applications and Industries • Production of fine particulates of ceramic powders used by indus ...

205

Bacterial Production of Mixed Metal Oxide Nanoparticles  

• Production of fine particulates of ceramic powders used by industry and in chemical processing applications Patent Tommy J. Phelps, Robert J. Lauf, ...

206

Correlational analysis of superconducting mixed copper oxides  

Science Conference Proceedings (OSTI)

A unifying structural scheme of all layered superconducting cuprates is proposed. The paper is a review based on a three level correlational analysis of the behaviour of one compound, of a homologous series and a third interseries analysis, revealing ... Keywords: correlational analysis, homologous series, layered cuprates, superconductivity

Cristina Zarioiu; V. G. Lascu; Lidia Petrova; Anca Novac

2008-06-01T23:59:59.000Z

207

Advanced Mixing Models  

Propose mixing indicators. Turbulence kinetic energy ... (Turbulence intensity observed at Point 8 in Tank B & C) Advanced Mixing Models. Computational Sciences. 13.

208

A Theoretical Insight into the Catalytic Effect of a Mixed-Metal Oxide at the Nanometer Level: The Case of the Highly Active metal/CeOx/TiO2 (110) Catalysts  

SciTech Connect

The structural and electronic properties of CeO{sub x} species supported on the rutile TiO{sub 2}(110) surface have been examined by means of periodic density-functional calculations that use a generalized gradient approximation functional including a Hubbard-like type correction. Deposition of Ce atoms leads in a first step to Ce{sup 3+} ions bound to the surface through bridge and in-plane oxygen atoms, the released electrons occupying the Ti 3d empty orbitals. Further addition of Ce and molecular oxygen gives place to Ce{sub 2}O{sub 3} dimers diagonally arranged on the surface, in agreement with the spots observed in the scanning tunnel microscope images. The formation process of CeO{sub x} nanoparticles (NPs) on the TiO{sub 2} surface is highly exothermic and our calculations show that the redox properties of the Ce(III)-Ce(IV) couple are significantly altered when it is supported on TiO{sub 2}. In particular the reactivity against CO/O{sub 2} indicates that on the surface the presence of Ce(III) is favored over Ce(IV) species. Our results also indicate that the CeO{sub x}/TiO{sub 2} interface should be seen like a real mixed-metal oxide rather than a supported NP of ceria. Finally, in the context of the high catalytic activity of the M/CeO{sub x}/TiO{sub 2} (M = Au,Cu,Pt) systems in the water-gas shift reaction, we have examined the dissociation of water on the CeO{sub x}/TiO{sub 2} surface and estimated a barrier as small as 0.04 eV, i.e. {approx}8 times smaller than that computed for a TiO{sub 2} oxygen vacancy. This result agrees with the experimental superior catalytic activity of the M/CeO{sub x}/TiO{sub 2} systems over M/TiO{sub 2}.

Rodriguez, J.A.; Graciani, J.; Plata, J.J.; Sanz, J.F.; Liu, P.

2010-03-14T23:59:59.000Z

209

ZPR-6 assembly 7 high {sup 240}Pu core experiments : a fast reactor core with mixed (Pu,U)-oxide fuel and a centeral high{sup 240}Pu zone.  

Science Conference Proceedings (OSTI)

ZPR-6 Assembly 7 (ZPR-6/7) encompasses a series of experiments performed at the ZPR-6 facility at Argonne National Laboratory in 1970 and 1971 as part of the Demonstration Reactor Benchmark Program (Reference 1). Assembly 7 simulated a large sodium-cooled LMFBR with mixed oxide fuel, depleted uranium radial and axial blankets, and a core H/D near unity. ZPR-6/7 was designed to test fast reactor physics data and methods, so configurations in the Assembly 7 program were as simple as possible in terms of geometry and composition. ZPR-6/7 had a very uniform core assembled from small plates of depleted uranium, sodium, iron oxide, U{sub 3}O{sub 8} and Pu-U-Mo alloy loaded into stainless steel drawers. The steel drawers were placed in square stainless steel tubes in the two halves of a split table machine. ZPR-6/7 had a simple, symmetric core unit cell whose neutronic characteristics were dominated by plutonium and {sup 238}U. The core was surrounded by thick radial and axial regions of depleted uranium to simulate radial and axial blankets and to isolate the core from the surrounding room. The ZPR-6/7 program encompassed 139 separate core loadings which include the initial approach to critical and all subsequent core loading changes required to perform specific experiments and measurements. In this context a loading refers to a particular configuration of fueled drawers, radial blanket drawers and experimental equipment (if present) in the matrix of steel tubes. Two principal core configurations were established. The uniform core (Loadings 1-84) had a relatively uniform core composition. The high {sup 240}Pu core (Loadings 85-139) was a variant on the uniform core. The plutonium in the Pu-U-Mo fuel plates in the uniform core contains 11% {sup 240}Pu. In the high {sup 240}Pu core, all Pu-U-Mo plates in the inner core region (central 61 matrix locations per half of the split table machine) were replaced by Pu-U-Mo plates containing 27% {sup 240}Pu in the plutonium component to construct a central core zone with a composition closer to that in an LMFBR core with high burnup. The high {sup 240}Pu configuration was constructed for two reasons. First, the composition of the high {sup 240}Pu zone more closely matched the composition of LMFBR cores anticipated in design work in 1970. Second, comparison of measurements in the ZPR-6/7 uniform core with corresponding measurements in the high {sup 240}Pu zone provided an assessment of some of the effects of long-term {sup 240}Pu buildup in LMFBR cores. The uniform core version of ZPR-6/7 is evaluated in ZPR-LMFR-EXP-001. This document only addresses measurements in the high {sup 240}Pu core version of ZPR-6/7. Many types of measurements were performed as part of the ZPR-6/7 program. Measurements of criticality, sodium void worth, control rod worth and reaction rate distributions in the high {sup 240}Pu core configuration are evaluated here. For each category of measurements, the uncertainties are evaluated, and benchmark model data are provided.

Lell, R. M.; Morman, J. A.; Schaefer, R.W.; McKnight, R.D.; Nuclear Engineering Division

2009-02-23T23:59:59.000Z

210

A Comparison of Mixing Depths Observed by Ground-Based Wind Profilers and an Airborne Lidar  

Science Conference Proceedings (OSTI)

The authors compare the mixing depths in the daytime convective boundary layers that were observed remotely by wind profilers and an airborne lidar during the 1995 Southern Oxidants Study. The comparison is used to determine whether the mixing ...

A. B. White; C. J. Senff; R. M. Banta

1999-05-01T23:59:59.000Z

211

Method for hot pressing beryllium oxide articles  

DOE Patents (OSTI)

The hot pressing of beryllium oxide powder into high density compacts with little or no density gradients is achieved by employing a homogeneous blend of beryllium oxide powder with a lithium oxide sintering agent. The lithium oxide sintering agent is uniformly dispersed throughout the beryllium oxide powder by mixing lithium hydroxide in an aqueous solution with beryllium oxide powder. The lithium hydroxide is converted in situ to lithium carbonate by contacting or flooding the beryllium oxide - lithium hydroxide blend with a stream of carbon dioxide. The lithium carbonate is converted to lithium oxide while remaining fixed to the beryllium oxide particles during the hot pressing step to assure uniform density throughout the compact.

Ballard, A.H.; Godfrey, T.G. Jr.; Mowery, E.H.

1986-10-10T23:59:59.000Z

212

HETEROGENEOUS REBURNING BY MIXED FUELS  

SciTech Connect

Recent studies of heterogeneous reburning, i.e., reburning involving a coal-derived char, have elucidated its variables, kinetics and mechanisms that are valuable to the development of a highly efficient reburning process. Young lignite chars contain catalysts that not only reduce NO, but they also reduce HCN that is an important intermediate that recycles to NO in the burnout zone. Gaseous CO scavenges the surface oxides that are formed during NO reduction, regenerating the active sites on the char surface. Based on this mechanistic information, cost-effective mixed fuels containing these multiple features has been designed and tested in a simulated reburning apparatus. Remarkably high reduction of NO and HCN has been observed and it is anticipated that mixed fuel will remove 85% of NO in a three-stage reburning process.

Wei-Yin Chen; Benson B. Gathitu

2005-01-14T23:59:59.000Z

213

Fluorescence-based detection methodologies for nitric oxide using transition metal scaffolds  

E-Print Network (OSTI)

Chapter 1. Fluorescence-Based Detection Methodologies for Nitric Oxide: A Review. Chapter 2. Cobalt Chemistry with Mixed Aminotroponimine Salicylaldimine Ligands: Synthesis, Characterization, and Nitric Oxide Reactivity. ...

Hilderbrand, Scott A. (Scott Alan), 1976-

2004-01-01T23:59:59.000Z

214

Mixed Waste Treatment Study  

Science Conference Proceedings (OSTI)

As part of an ongoing integrated mixed waste program, EPRI has documented nuclear utility industry experience in the on-site treatment of mixed waste. This report reviews all available exclusions/exceptions to EPA permitting requirements for environmentally responsible on-site management of mixed waste. Included is a description of emerging mixed waste treatment technologies along with a detailed evaluation of off-site treatment/disposal facilities.

1996-01-31T23:59:59.000Z

215

Reprinted from Nuclear Physics A654 (1999) 436~457~  

E-Print Network (OSTI)

Actinide alloys Fast Reators Actinide mixed oxides Tc in CANDU L W R / H W R B W R | P W R CANDU homogeneous fuel Actinides MgO Tc Fast Reactors Actinide Mixed oxide (MOX) Tc in CANDU Actinides in inert

216

Mixed Waste Management Guidelines  

Science Conference Proceedings (OSTI)

The management of mixed waste presents serious challenges to nuclear utilities. Regulatory and practical predicaments make compliance with the letter of all applicable regulations extremely difficult. Utility experts developed these guidelines to identify opportunities for improving work practices and regulatory compliance while minimizing any potential adverse impacts of mixed waste management.

1994-12-31T23:59:59.000Z

217

SSA Mixed Canopy Site  

NLE Websites -- All DOE Office Websites (Extended Search)

Mixed Canopy Site (SSA-Mix) Mixed Canopy Site (SSA-Mix) The TE canopy tower The mixed trees Terrestrial Ecology canopy access tower at the SSA mixed coniferous/deciduous site. A picture taken looking down from the TE canopy access tower at the SSA mixed auxiliary site, showing the aspen and spruce canopies. Back to the BOREAS Photo Page Index Other Sites: NSA Photos ||NSA-BP Photos | NSA-Fen Photos | NSA-OA Photos | NSA-OBS Photos | NSA-OJP Photos | NSA-UBS Photos | NSA-YJP Photos | NSA-Ops Photos SSA Photos || SSA-Airport Photos | SSA-Fen Photos | SSA-Mix Photos | SSA-OA Photos | SSA-OBS Photos | SSA-OJP Photos | SSA-YA Photos | SSA-YJP Photos | SSA-Ops Photos | ORNL DAAC Home || ORNL Home || NASA || Privacy, Security, Notices || Data Citation || Rate Us || Help | User Services - Tel: +1 (865) 241-3952 or E-mail: uso@daac.ornl.gov

218

Sustained Removal of Uranium From Contaminated Groundwater  

E-Print Network (OSTI)

approximately 5 mm in diameter by 5 mm tal/. Compositions measured ranged from depleted uranium oxide to mixtures of plutonium and depleted uranium oxide (MOX) and mixed oxides with small percentages of minor.1943 - - - Title: Resonant Ultrasound Spectroscopy Measurements of the Elastic Properties of Uranium

Lovley, Derek

219

Mixed waste characterization reference document  

SciTech Connect

Waste characterization and monitoring are major activities in the management of waste from generation through storage and treatment to disposal. Adequate waste characterization is necessary to ensure safe storage, selection of appropriate and effective treatment, and adherence to disposal standards. For some wastes characterization objectives can be difficult and costly to achieve. The purpose of this document is to evaluate costs of characterizing one such waste type, mixed (hazardous and radioactive) waste. For the purpose of this document, waste characterization includes treatment system monitoring, where monitoring is a supplement or substitute for waste characterization. This document establishes a cost baseline for mixed waste characterization and treatment system monitoring requirements from which to evaluate alternatives. The cost baseline established as part of this work includes costs for a thermal treatment technology (i.e., a rotary kiln incinerator), a nonthermal treatment process (i.e., waste sorting, macronencapsulation, and catalytic wet oxidation), and no treatment (i.e., disposal of waste at the Waste Isolation Pilot Plant (WIPP)). The analysis of improvement over the baseline includes assessment of promising areas for technology development in front-end waste characterization, process equipment, off gas controls, and monitoring. Based on this assessment, an ideal characterization and monitoring configuration is described that minimizes costs and optimizes resources required for waste characterization.

1997-09-01T23:59:59.000Z

220

ADVANCED MIXING MODELS  

Science Conference Proceedings (OSTI)

The process of recovering and processing High Level Waste (HLW) the waste in storage tanks at the Savannah River Site (SRS) typically requires mixing the contents of the tank with one to four mixers (pumps) located within the tank. The typical criteria to establish a mixed condition in a tank are based on the number of pumps in operation and the time duration of operation. To ensure that a mixed condition is achieved, operating times are typically set conservatively long. This approach results in high operational costs because of the long mixing times and high maintenance and repair costs for the same reason. A significant reduction in both of these costs might be realized by reducing the required mixing time based on calculating a reliable indicator of mixing with a suitably validated computer code. The focus of the present work is to establish mixing criteria applicable to miscible fluids, with an ultimate goal of addressing waste processing in HLW tanks at SRS and quantifying the mixing time required to suspend sludge particles with the submersible jet pump. A single-phase computational fluid dynamics (CFD) approach was taken for the analysis of jet flow patterns with an emphasis on the velocity decay and the turbulent flow evolution for the farfield region from the pump. Literature results for a turbulent jet flow are reviewed, since the decay of the axial jet velocity and the evolution of the jet flow patterns are important phenomena affecting sludge suspension and mixing operations. The work described in this report suggests a basis for further development of the theory leading to the identified mixing indicators, with benchmark analyses demonstrating their consistency with widely accepted correlations. Although the indicators are somewhat generic in nature, they are applied to Savannah River Site (SRS) waste tanks to provide a better, physically based estimate of the required mixing time. Waste storage tanks at SRS contain settled sludge which varies in height from zero to 10 ft. The sludge has been characterized and modeled as micron-sized solids, typically 1 to 5 microns, at weight fractions as high as 20 to 30 wt%, specific gravities to 1.4, and viscosities up to 64 cp during motion. The sludge is suspended and mixed through the use of submersible slurry jet pumps. To suspend settled sludge, water is added to the tank as a slurry medium and stirred with the jet pump. Although there is considerable technical literature on mixing and solid suspension in agitated tanks, very little literature has been published on jet mixing in a large-scale tank. One of the main objectives in the waste processing is to provide feed of a uniform slurry composition at a certain weight percentage (e.g. typically {approx}13 wt% at SRS) over an extended period of time. In preparation of the sludge for slurrying, several important questions have been raised with regard to sludge suspension and mixing of the solid suspension in the bulk of the tank: (1) How much time is required to prepare a slurry with a uniform solid composition? (2) How long will it take to suspend and mix the sludge for uniform composition in any particular waste tank? (3) What are good mixing indicators to answer the questions concerning sludge mixing stated above in a general fashion applicable to any waste tank/slurry pump geometry and fluid/sludge combination?

Lee, S.; Dimenna, R.; Tamburello, D.

2011-02-14T23:59:59.000Z

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


221

Guidelines for mixed waste minimization  

SciTech Connect

Currently, there is no commercial mixed waste disposal available in the United States. Storage and treatment for commercial mixed waste is limited. Host States and compacts region officials are encouraging their mixed waste generators to minimize their mixed wastes because of management limitations. This document provides a guide to mixed waste minimization.

Owens, C.

1992-02-01T23:59:59.000Z

222

Lateral Mixing in the Pycnocline by Baroclinic Mixed Layer Eddies  

Science Conference Proceedings (OSTI)

Using a process study model, the effect of mixed layer submesoscale instabilities on the lateral mixing of passive tracers in the pycnocline is explored. Mixed layer eddies that are generated from the baroclinic instability of a front within the ...

Gualtiero Badin; Amit Tandon; Amala Mahadevan

2011-11-01T23:59:59.000Z

223

Mixing method and apparatus  

DOE Patents (OSTI)

Method of mixing particulate materials comprising contacting a primary source and a secondary source thereof whereby resulting mixture ensues; preferably at least one of the two sources has enough motion to insure good mixing and the particulate materials may be heat treated if desired. Apparatus for such mixing comprising an inlet for a primary source, a reactor communicating therewith, a feeding means for supplying a secondary source to the reactor, and an inlet for the secondary source. Feeding means is preferably adapted to supply fluidized materials.

Green, Norman W. (Redwood City, CA)

1982-06-15T23:59:59.000Z

224

Fuel qualification issues and strategies for reactor-based surplus plutonium disposition  

SciTech Connect

The Department of Energy (DOE) has proposed irradiation of mixed-oxide (MOX) fuel in existing commercial reactors as a disposition method for surplus plutonium from the weapons program. The burning of MOX fuel in reactors is supported by an extensive technology base; however, the infrastructure required to implement reactor-based plutonium disposition does not exist domestically. This report identifies and examines the actions required to qualify and license weapons-grade (WG) plutonium-based MOX fuels for use in domestic commercial light-water reactors (LWRs).

Cowell, B.S.; Copeland, G.L.; Moses, D.L.

1997-08-01T23:59:59.000Z

225

Mixed Semiconductor Nanocrystal Compositions  

NLE Websites -- All DOE Office Websites (Extended Search)

Mixed Semiconductor Nanocrystal Compositions Mixed Semiconductor Nanocrystal Compositions Mixed Semiconductor Nanocrystal Compositions Composition comprising one or more energy donors and one or more energy acceptors. Available for thumbnail of Feynman Center (505) 665-9090 Email Mixed Semiconductor Nanocrystal Compositions Composition comprising one or more energy donors and one or more energy acceptors, wherein energy is transferred from the energy donor to the energy acceptor and wherein: the energy acceptor is a colloidal nanocrystal having a lower band gap energy than the energy donor; the energy donor and the energy acceptor are separated by a distance of 40 nm or less; wherein the average peak absorption energy of the acceptor is at least 20 meV greater than the average peak emission energy of the energy donor; and

226

Fuel Mix Disclosure  

Energy.gov (U.S. Department of Energy (DOE))

Hawaii requires the state’s retail electric suppliers to disclose details regarding the fuel mix of their electric generation to retail customers. Such information must be provided on customers’...

227

Mixing by ocean eddies  

E-Print Network (OSTI)

Mesoscale eddies mix and transport tracers such as heat and potential vorticity laterally in the ocean. While this transport plays an important role in the climate system, especially in the Southern Ocean, we lack a, ...

Abernathey, Ryan (Ryan Patrick)

2012-01-01T23:59:59.000Z

228

Short Term Irradiation Test of Fuel Containing Minor Actinides Using the Experimental Fast Reactor Joyo  

Science Conference Proceedings (OSTI)

A mixed oxide containing minor actinides (MA-MOX) fuel irradiation program is being conducted using the experimental fast rector Joyo of the Japan Atomic Energy Agency to research early thermal behavior of MA-MOX fuel. Two irradiation experiments were conducted as part of the short-term phase of this program in May and August 2006. Six prepared fuel pins included MOX fuel containing 3% or 5% americium (Am-MOX), and MOX fuel containing 2% americium and 2% neptunium (Np/Am-MOX). The first test was conducted with high linear heat rates of approximately 430 W/cm maintained during only 10 minutes. After 10 minutes irradiation test, the test subassembly was transferred to the hot cell facility and an Am-MOX pin and a Np/Am-MOX pin were replaced with dummy pins with neutron dosimeters. The test subassembly loaded with the remaining four fuel pins was re-irradiated in Joyo for 24-hours in August 2006 at nearly the same linear power to obtain re-distribution data on MA-MOX fuel. The linear heat rate for each MA-MOX test fuel pin was calculated using the Monte Carlo calculation code MCNP. The calculated fission rates were compared with the measured data based on the Nd-148 method. The maximum linear heat rate was approximately 444{+-}19 W/cm at the actual reactor power of 119.6 MWt. Post irradiation examination of these pins to confirm the absence of fuel melting and the local concentration under irradiation of NpO{sub 2-x} or AmO{sub 2-x}, in the (U,Pu)0{sub 2-x}, fuel are underway. The test results are expected to reduce uncertainties on the margin in the thermal design for MA-MOX fuel. (authors)

Sekine, Takashi; Soga, Tomonori; Koyama, Shin-ichi; Aoyama, Takafumi [Oarai Research and Development Center, Japan Atomic Energy Agency. 4002 Narita, Oarai, Ibaraki 311-1393 (Japan); Wootan, David [Pacific Northwest National Laboratoy, M/S K8-34, P.O. Box 999 Richland, WA 99352 (United States)

2007-07-01T23:59:59.000Z

229

ADVANCED MIXING MODELS  

SciTech Connect

The process of recovering the waste in storage tanks at the Savannah River Site (SRS) typically requires mixing the contents of the tank with one to four dual-nozzle jet mixers located within the tank. The typical criteria to establish a mixed condition in a tank are based on the number of pumps in operation and the time duration of operation. To ensure that a mixed condition is achieved, operating times are set conservatively long. This approach results in high operational costs because of the long mixing times and high maintenance and repair costs for the same reason. A significant reduction in both of these costs might be realized by reducing the required mixing time based on calculating a reliable indicator of mixing with a suitably validated computer code. The work described in this report establishes the basis for further development of the theory leading to the identified mixing indicators, the benchmark analyses demonstrating their consistency with widely accepted correlations, and the application of those indicators to SRS waste tanks to provide a better, physically based estimate of the required mixing time. Waste storage tanks at SRS contain settled sludge which varies in height from zero to 10 ft. The sludge has been characterized and modeled as micron-sized solids, typically 1 to 5 microns, at weight fractions as high as 20 to 30 wt%, specific gravities to 1.4, and viscosities up to 64 cp during motion. The sludge is suspended and mixed through the use of submersible slurry jet pumps. To suspend settled sludge, water is added to the tank as a slurry medium and stirred with the jet pump. Although there is considerable technical literature on mixing and solid suspension in agitated tanks, very little literature has been published on jet mixing in a large-scale tank. If shorter mixing times can be shown to support Defense Waste Processing Facility (DWPF) or other feed requirements, longer pump lifetimes can be achieved with associated operational cost and schedule savings. The focus of the present work is to establish mixing criteria associated with the waste processing at SRS and to quantify the mixing time required to suspend sludge particles with the submersible jet pump. Literature results for a turbulent jet flow are reviewed briefly, since the decay of the axial jet velocity and the evolution of the jet flow patterns are important phenomena affecting sludge suspension and mixing operations. One of the main objectives in the waste processing is to provide the DWPF a uniform slurry composition at a certain weight percentage (typically {approx}13 wt%) over an extended period of time. In preparation of the sludge for slurrying to DWPF, several important questions have been raised with regard to sludge suspension and mixing of the solid suspension in the bulk of the tank: (1) How much time is required to prepare a slurry with a uniform solid composition for DWPF? (2) How long will it take to suspend and mix the sludge for uniform composition in any particular waste tank? (3) What are good mixing indicators to answer the questions concerning sludge mixing stated above in a general fashion applicable to any waste tank/slurry pump geometry and fluid/sludge combination? Grenville and Tilton (1996) investigated the mixing process by giving a pulse of tracer (electrolyte) through the submersible jet nozzle and by monitoring the conductivity at three locations within the cylindrical tank. They proposed that the mixing process was controlled by the turbulent kinetic energy dissipation rate in the region far away from the jet entrance. They took the energy dissipation rates in the regions remote from the nozzle to be proportional to jet velocity and jet diameter at that location. The reduction in the jet velocity was taken to be proportional to the nozzle velocity and distance from the nozzle. Based on their analysis, a correlation was proposed. The proposed correlation was shown to be valid over a wide range of Reynolds numbers (50,000 to 300,000) with a relative standard deviation of {+-} 11.83%. An improved correlat

Lee, S; Richard Dimenna, R; David Tamburello, D

2008-11-13T23:59:59.000Z

230

Mixed waste: Proceedings  

SciTech Connect

This volume contains the peer-reviewed and edited versions of papers submitted for presentation a the Second International Mixed Waste Symposium. Following the tradition of the First International Mixed Waste Symposium, these proceedings were prepared in advance of the meeting for distribution to participants. The symposium was organized by the Mixed Waste Committee of the American Society of Mechanical Engineers. The topics discussed at the symposium include: stabilization technologies, alternative treatment technologies, regulatory issues, vitrification technologies, characterization of wastes, thermal technologies, laboratory and analytical issues, waste storage and disposal, organic treatment technologies, waste minimization, packaging and transportation, treatment of mercury contaminated wastes and bioprocessing, and environmental restoration. Individual abstracts are catalogued separately for the data base.

Moghissi, A.A.; Blauvelt, R.K.; Benda, G.A.; Rothermich, N.E. [eds.] [Temple Univ., Philadelphia, PA (United States). Dept. of Environmental Safety and Health

1993-12-31T23:59:59.000Z

231

In situ enhanced soil mixing. Innovative technology summary report  

Science Conference Proceedings (OSTI)

In Situ Enhanced Soil Mixing (ISESM) is a treatment technology that has been demonstrated and deployed to remediate soils contaminated with volatile organic compounds (VOCs). The technology has been developed by industry and has been demonstrated with the assistance of the U.S. Department of Energy`s Office of Science and Technology and the Office of Environmental Restoration. The technology is particularly suited to shallow applications, above the water table, but can be used at greater depths. ISESM technologies demonstrated for this project include: (1) Soil mixing with vapor extraction combined with ambient air injection. [Contaminated soil is mixed with ambient air to vaporize volatile organic compounds (VOCs). The mixing auger is moved up and down to assist in removal of contaminated vapors. The vapors are collected in a shroud covering the treatment area and run through a treatment unit containing a carbon filter or a catalytic oxidation unit with a wet scrubber system and a high efficiency particulate air (HEPA) filter.] (2) soil mixing with vapor extraction combined with hot air injection [This process is the same as the ambient air injection except that hot air or steam is injected.] (3) soil mixing with hydrogen peroxide injection [Contaminated soil is mixed with ambient air that contains a mist of diluted hydrogen peroxide (H{sub 2}O{sub 2}) solution. The H{sub 2}O{sub 2} solution chemically oxidizes the VOCs to carbon dioxide (CO{sub 2}) and water.] (4) soil mixing with grout injection for solidification/stabilization [Contaminated soil is mixed as a cement grout is injected under pressure to solidify and immobilize the contaminated soil in a concrete-like form.] The soils are mixed with a single-blade auger or with a combination of augers ranging in diameter from 3 to 12 feet.

NONE

1996-02-01T23:59:59.000Z

232

Method for hot pressing beryllium oxide articles  

DOE Patents (OSTI)

The hot pressing of beryllium oxide powder into high density compacts with little or no density gradients is achieved by employing a homogeneous blend of beryllium oxide powder with a lithium oxide sintering agent. The lithium oxide sintering agent is uniformly dispersed throughout the beryllium oxide powder by mixing lithium hydroxide in an aqueous solution with beryllium oxide powder. The lithium hydroxide is converted in situ to lithium carbonate by contacting or flooding the beryllium oxide-lithium hydroxide blend with a stream of carbon dioxide. The lithium carbonate is converted to lithium oxide while remaining fixed to the beryllium oxide particles during the hot pressing step to assure uniform density throughout the compact.

Ballard, Ambrose H. (Oak Ridge, TN); Godfrey, Jr., Thomas G. (Oak Ridge, TN); Mowery, Erb H. (Clinton, TN)

1988-01-01T23:59:59.000Z

233

Mixed Waste Characterization Guidelines  

Science Conference Proceedings (OSTI)

This report presents an overview of the process of characterizing potential mixed waste streams from nuclear power plants. Utility experts developed these guidelines to help guide utility personnel through the characterization process and provide a mechanism for properly documenting the characterization of individual waste streams.

1995-12-31T23:59:59.000Z

234

Machinable dissolved metal oxide superconductors  

DOE Patents (OSTI)

Powders of a metal oxide superconductor are mixed with sufficient amount (10--80 mol%) of In, Sn, and/or Al, to become nonbrittle, machinable. Preferred superconductors are YBa[sub 2]Cu[sub 3]O[sub 7[minus]x] and Bi-Sr-Ca-Cu-O compounds.

Chen, Chung-Hsuan.

1991-01-01T23:59:59.000Z

235

Machinable dissolved metal oxide superconductors  

DOE Patents (OSTI)

Powders of a metal oxide superconductor are mixed with sufficient amount (10--80 mol%) of In, Sn, and/or Al, to become nonbrittle, machinable. Preferred superconductors are YBa{sub 2}Cu{sub 3}O{sub 7{minus}x} and Bi-Sr-Ca-Cu-O compounds.

Chen, Chung-Hsuan

1991-12-31T23:59:59.000Z

236

PROCESS OF PRODUCING REFRACTORY URANIUM OXIDE ARTICLES  

DOE Patents (OSTI)

A method is presented for fabricating uranium oxide into a shaped refractory article by introducing a uranium halide fluxing reagent into the uranium oxide, and then mixing and compressing the materials into a shaped composite mass. The shaped mass of uranium oxide and uranium halide is then fired at an elevated temperature so as to form a refractory sintered article. It was found in the present invention that the introduction of a uraninm halide fluxing agent afforded a fluxing action with the uranium oxide particles and that excellent cohesion between these oxide particles was obtained. Approximately 90% of uranium dioxide and 10% of uranium tetrafluoride represent a preferred composition.

Hamilton, N.E.

1957-12-01T23:59:59.000Z

237

IMPROVED MAGNESIUM OXIDE SLIP CASTING METHOD  

DOE Patents (OSTI)

A process for making an aqueous magnesium oxide slip casting slurry comprising the steps of mixing finely ground fused magnesium oxide with water, milling the slurry for at least 30 hours at a temperature of 2-10 deg C (the low temperature during milling inhibiting the formation of hydrated magnesium oxide), discharging the slurry from the mill, adding hydrochloric acid as a deflocculent, and adding a scum inhibitor is presented. (AEC)

Stoddard, S.D.; Nuckolls, D.E.

1963-12-31T23:59:59.000Z

238

Mixed Seed Laboratory Proficiency Testing Program Mixed Seed  

Science Conference Proceedings (OSTI)

Laboratory Proficiency Testing service for Sunflower,Safflower, and Canola to test Oil, Clean Seed Basis, Nitrogen, Free Fatty Acids, Glucosinolates, Chlorophyll. Mixed Seed Laboratory Proficiency Testing Program Mixed Seed Laboratory Proficiency Program

239

Comparison of Methods for Estimating Mixing Height Used during the 1992 Atlanta Field Intensive  

Science Conference Proceedings (OSTI)

During the summer of 1992, measurements of the boundary layer mixing height were conducted at five locations around the city of Atlanta, Georgia, as part of the 1992 Atlanta Field Intensive of the Southern Oxidants Research Program on Ozone Non-...

Frank J. Marsik; Kenneth W. Fischer; Tracey D. McDonald; Perry J. Samson

1995-08-01T23:59:59.000Z

240

Nozzle mixing apparatus  

DOE Patents (OSTI)

This invention is comprised of a nozzle device for causing two fluids to mix together. In particular, a spray nozzle comprise two hollow, concentric housings, an inner housing and an outer housing. The inner housing has a channel formed therethrough for a first fluid. Its outer surface cooperates with the interior surface of the outer housing to define the second channel for a second fluid. The outer surface of the inner housing and the inner surface of the outer housing each carry a plurality of vanes that interleave but do not touch, each vane of one housing being between two vanes of the other housing. The vanes are curved and the inner surface of the outer housing and the outer surface of the inner housing converge to narrow the second channel. The shape of second channel results in a swirling, accelerating second fluid that will impact the first fluid just past the end of the nozzle where mixing will take place.

Mensink, D.L.

1992-12-31T23:59:59.000Z

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


241

Mixed Waste Recycling Exemption  

Science Conference Proceedings (OSTI)

As part of an ongoing integrated mixed waste program, EPRI has documented the process for obtaining state approval to apply the Resource Conservation and Recovery Act (RCRA) recycling exemption. This report examines the regulatory basis for the recycling exemption and the strategy for designing and operating a recycling facility to meet that exemption. Specifically addressed is the process of submitting an actual recycling exemption request to an RCRA authorized state and potential roadblocks utilities m...

1998-11-30T23:59:59.000Z

242

Actinide Burning in CANDU Reactors  

Science Conference Proceedings (OSTI)

Actinide burning in CANDU reactors has been studied as a method of reducing the actinide content of spent nuclear fuel from light water reactors, and thereby decreasing the associated long term decay heat load. In this work simulations were performed of actinides mixed with natural uranium to form a mixed oxide (MOX) fuel, and also mixed with silicon carbide to form an inert matrix (IMF) fuel. Both of these fuels were taken to a higher burnup than has previously been studied. The total transuranic element destruction calculated was 40% for the MOX fuel and 71% for the IMF. (authors)

Hyland, B.; Dyck, G.R. [Atomic Energy of Canada Limited, Chalk River, Ontario, K0J 1J0 (Canada)

2007-07-01T23:59:59.000Z

243

Comet whole-core solution to a stylized 3-dimensional pressurized water reactor benchmark problem with UO{sub 2}and MOX fuel  

Science Conference Proceedings (OSTI)

A stylized pressurized water reactor (PWR) benchmark problem with UO{sub 2} and MOX fuel was used to test the accuracy and efficiency of the coarse mesh radiation transport (COMET) code. The benchmark problem contains 125 fuel assemblies and 44,000 fuel pins. The COMET code was used to compute the core eigenvalue and assembly and pin power distributions for three core configurations. In these calculations, a set of tensor products of orthogonal polynomials were used to expand the neutron angular phase space distribution on the interfaces between coarse meshes. The COMET calculations were compared with the Monte Carlo code MCNP reference solutions using a recently published an 8-group material cross section library. The comparison showed both the core eigenvalues and assembly and pin power distributions predicated by COMET agree very well with the MCNP reference solution if the orders of the angular flux expansion in the two spatial variables and the polar and azimuth angles on the mesh boundaries are 4, 4, 2 and 2. The mean and maximum differences in the pin fission density distribution ranged from 0.28%-0.44% and 3.0%-5.5%, all within 3-sigma uncertainty of the MCNP solution. These comparisons indicate that COMET can achieve accuracy comparable to Monte Carlo. It was also found that COMET's computational speed is 450 times faster than MCNP. (authors)

Zhang, D.; Rahnema, F. [Georgia Inst. of Technology, 770 State Street, Atlanta, GA 30332-0745 (United States)

2012-07-01T23:59:59.000Z

244

Characterization of Cerium Oxide during Sintering  

Science Conference Proceedings (OSTI)

Because the chemical and thermodynamic properties of ceria are similar to those of plutonia, it is often used as a surrogate for plutonia in the study of MOX fuels.

245

Thermally Driven Crossover from Indirect toward Direct Bandgap in 2D Semiconductors: MoSe2 versus MoS2  

E-Print Network (OSTI)

transition may occur from the adsorbed hydroxyl radi- cals (MOx[·OH]) to the lattice of the metal oxide anode, forming the higher oxide MOx+1, and the oxygen forms oxidizing organic substance to different products [21,23]. Since MOx[·OH] favors electrochemical combustion while MOx+1 favors electrochemical conversion [23

Wu, Junqiao

246

TECHNICAL BASIS FOR DOE STANDARD 3013 EQUIVALENCY SUPPORTING REDUCED TEMPERATURE STABILIZATION OF OXALATE-DERIVED PLUTONIUM OXIDE PRODUCED BY THE HB-LINE FACILITY AT SAVANNAH RIVER SITE  

DOE Green Energy (OSTI)

The HB-Line (HBL) facility at the Savannah River Site (SRS) is designed to produce high-purity plutonium dioxide (PuO{sub 2}) which is suitable for future use in production of Mixed Oxide (MOX) fuel. The MOX Fuel Fabrication Facility (MFFF) requires PuO{sub 2} feed to be packaged per the U.S. Department of Energy (DOE) Standard 3013 (DOE-STD-3013) to comply with the facility's safety basis. The stabilization conditions imposed by DOE-STD-3013 for PuO{sub 2} (i.e., 950 C for 2 hours) preclude use of the HBL PuO{sub 2} in direct fuel fabrication and reduce the value of the HBL product as MFFF feedstock. Consequently, HBL initiated a technical evaluation to define acceptable operating conditions for production of high-purity PuO{sub 2} that fulfills the DOE-STD-3013 criteria for safe storage. The purpose of this document is to demonstrate that within the defined operating conditions, the HBL process will be equivalent for meeting the requirements of the DOE-STD-3013 stabilization process for plutonium-bearing materials from the DOE complex. The proposed 3013 equivalency reduces the prescribed stabilization temperature for high-purity PuO{sub 2} from oxalate precipitation processes from 950 C to 640 C and places a limit of 60% on the relative humidity (RH) at the lowest material temperature. The equivalency is limited to material produced using the HBL established flow sheet, for example, nitric acid anion exchange and Pu(IV) direct strike oxalate precipitation with stabilization at a minimum temperature of 640 C for four hours (h). The product purity must meet the MFFF acceptance criteria of 23,600 {micro}g/g Pu (i.e., 2.1 wt %) total impurities and chloride content less than 250 {micro}g/g of Pu. All other stabilization and packaging criteria identified by DOE-STD-3013-2012 or earlier revisions of the standard apply. Based on the evaluation of test data discussed in this document, the expert judgment of the authors supports packaging the HBL product under a 3013 equivalency. Under the defined process conditions and associated material specifications, the high-purity PuO{sub 2} produced in HBL presents no unique safety concerns for packaging or storage in the 3013 required configuration. The PuO{sub 2} produced using the HBL flow sheet conditions will have a higher specific surface area (SSA) than PuO{sub 2} stabilized at 950 C and, consequently, under identical conditions will adsorb more water from the atmosphere. The greatest challenge to HBL operators will be controlling moisture content below 0.5 wt %. However, even at the 0.5 wt % moisture limit, the maximum acceptable pressure of a stoichiometric mixture of hydrogen and oxygen in the 3013 container is greater than the maximum possible pressure for the HBL PuO{sub 2} product.

Duffey, J.; Livingston, R.; Berg, J.; Veirs, D.

2012-07-02T23:59:59.000Z

247

Available Technologies: Mixed Bioenergy Feedstock ...  

APPLICATIONS OF TECHNOLOGY: Biomass pretreatment to extract 6C sugars from mixed feedstocks for . Lignocellulosic biofuel production; High value ...

248

Multifunctional Oxides  

Science Conference Proceedings (OSTI)

3) Electric, ferroelectric, magnetic and photonic properties of oxides 4) Theoretical modeling of epitaxial growth, interfaces and microstructures 5) Composition ...

249

Regenerable Mixed Copper-Iron-Inert Support Oxygen Carriers  

NLE Websites -- All DOE Office Websites (Extended Search)

Mixed Copper-Iron-Inert Support Oxygen Carriers Mixed Copper-Iron-Inert Support Oxygen Carriers for Solid Fuel Chemical Looping Combustion Process Contact NETL Technology Transfer Group techtransfer@netl.doe.gov December 2012 This patent-pending technology, "Regenerable Mixed Copper-Iron-Inert Support Oxygen Carriers for Solid Fuel Chemical Looping Combustion Process," provides a metal-oxide oxygen carrier for application in fuel combustion processes that use oxygen. This technology is available for licensing and/or further collaborative research with the U.S. Department of Energy's National Energy Technology Laboratory. Overview Patent Details U.S. Non-Provisional Patent Application No. 13/159,553; titled "Regenerable Mixed Copper-Iron-Inert Support Oxygen Carriers for Solid

250

B Lifetimes and Mixing  

SciTech Connect

The Tevatron experiments, CDF and D0, have produced a wealth of new B-physics results since the start of Run II in 2001. We've observed new B-hadrons, seen new effects, and increased many-fold the precision with which we know the properties of b-quark systems. In these proceedings, we will discuss two of the most fruitful areas in the Tevatron B-physics program: lifetimes and mixing. We'll examine the experimental issues driving these analyses, present a summary of the latest results, and discuss prospects for the future.

Evans, Harold G.; /Indiana U.

2009-05-01T23:59:59.000Z

251

Pre-Oxidized and Nitrided Stainless Steel Foil for Proton Exchange ...  

Science Conference Proceedings (OSTI)

Post-test analyses of the membrane electrode assemblies (MEAs) by x-ray ... Simulation of Oxygen Ion Transport in Mixed-Conducting Solid Oxide Fuel Cell ... Sintering Performance of YSZ Ceramics with Transition Metal Oxide Sintering Aid

252

Disposition of Weapons-Grade Plutonium in Westinghouse Reactors  

E-Print Network (OSTI)

Disposition of Weapons-Grade Plutonium in Westinghouse Reactors Abdelhalim Ali Alsaed and Marvin Adams We have studied the feasibility of using weapons-grade plutonium in the form of mixed-oxide (MOX) fuel in existing Westinghouse reactors. We have designed three transition cycles from an all LEU core to a partial MOX core. We found that four-loop Westinghouse reactors such as the Vogtle power plant are capable of handling up to 45 percent weapons-grade MOX loading without any modifications. We have also designed two kinds of weapons-grade MOX assemblies with three enrichments per assembly and four total enrichments. Wet annular burnable absorber (WABA) rods were used in all the MOX feed assemblies, some burned MOX assemblies, and some LEU feed assemblies. Integral fuel burnable absorber (IFBA) was used in the rest of the LEU feed assemblies. The average discharge burnup of MOX assemblies was over 47,000 MWD/MTM, which is more than enough to meet the "spent fuel standard." One unit is ...

No. De-fc-al; Abdelhalim Ali Alsaed; Abdelhalim Ali Alsaed; Marvin Adams; Marvin Adams

1998-01-01T23:59:59.000Z

253

fuel mix | OpenEI  

Open Energy Info (EERE)

mix mix Dataset Summary Description The UK Department of Energy and Climate Change (DECC) publishes an annual "fuel mix disclosure data table" as defined in the Electricity (Fuel Mix Disclosure) Regulations 2005. This dataset represents April 1, 2009 - March 31, 2010. Source UK Department of Energy and Climate Change (DECC) Date Released March 31st, 2010 (4 years ago) Date Updated Unknown Keywords fuel mix UK Data application/vnd.openxmlformats-officedocument.spreadsheetml.sheet icon UK.fuel_.mix_.disclosure.4.2009.4.2010.xlsx (xlsx, 38.2 KiB) Quality Metrics Level of Review Some Review Comment Temporal and Spatial Coverage Frequency Time Period License License Other or unspecified, see optional comment below Comment UK Open Government License (OGL)

254

Compendium and synthesis of bacterial manganese reduction rates  

E-Print Network (OSTI)

generically as Mox ? Mred we can formulate a rate equation that mimics all three of these features as follows: d½Mred dt ¼ 0 t Mox K1=2þ½Mox t P tlag ( ð1� ½Mox þ ½Mred ¼ ½Mox0 þ ½Mred 0 ¼ ½Mtot ð2� where [Mred] and [Mox] are, respectively, concentrations of the reduced and oxidized metal over

Burgos, William

255

Mixing Properties in Oxide Solid Solutions Relevant to Nuclear Fuels  

Science Conference Proceedings (OSTI)

The work focuses on urania-ceria solid solutions, a surrogate system for ... Model for Hardness Uniformity of Multi-Pass Laser Heat Treatment Using Direct Diode Laser ... The Li-Graphite System and Surface Reactions from First-Principles.

256

LANL disassembles "pits," makes mixed-oxide fuel  

NLE Websites -- All DOE Office Websites (Extended Search)

Environment Feature Stories Public Reading Room: Environmental Documents, Reports LANL Home Phonebook Calendar Video Newsroom News Releases News Releases - 2011 ...

257

UO 2 Mixed Oxide System Using Atomic Level Simulations  

Science Conference Proceedings (OSTI)

Thorium-based nuclear materials offer the promise of increased proliferation resistance, longer fuel cycles, higher burnup and improved wasteform ...

258

Manufacturer's Mixed Pallet Design Problem  

E-Print Network (OSTI)

fore, the company decided to design a number of mixed or “rainbow” pallets so that its customers can order ...... Squeezing out waste of space. 62, 5, page 112.

259

Fuel Mix and Emissions Disclosure  

Energy.gov (U.S. Department of Energy (DOE))

As part of the state's 1997 electric utility restructuring legislation, Illinois established provisions for the disclosure of fuel mix and emissions data. All electric utilities and alternative...

260

Fuel Mix and Emissions Disclosure  

Energy.gov (U.S. Department of Energy (DOE))

Oregon's 1999 electric utility restructuring legislation requires electricity companies and electric service suppliers to disclose details regarding their fuel mix and emissions of electric...

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


261

Audit Report: IG-0713 | Department of Energy  

NLE Websites -- All DOE Office Websites (Extended Search)

3 3 Audit Report: IG-0713 December 21, 2005 Status of the Mixed Oxide Fuel Fabrication Facility The audit disclosed that the cost of the Mixed Oxide Fuel Facility (MOX) will significantly exceed the amounts reported to Congress. As of July 2005, the National Nuclear Security Administration's (NNSA's) unvalidated estimate for the design and construction of the MOX Facility was about $3.5 billion, which is $2.5 billion more than reported to Congress in 2002. NNSA's previous estimate of $1 billion for the facility's design and construction was reported in the February 2002 plutonium disposition plan presented to Congress. NNSA reported that it had a high degree of confidence in the estimate because the MOX technology was well-established and based on proven processes used in Europe since the 1960s, and it

262

Mixing in Symmetric Holmboe Waves  

Science Conference Proceedings (OSTI)

Direct simulations are used to study turbulence and mixing in Holmboe waves. Previous results showing that mixing in Holmboe waves is comparable to that found in the better-known Kelvin–Helmholtz (KH) billows are extended to cover a range of ...

W. D. Smyth; J. R. Carpenter; G. A. Lawrence

2007-06-01T23:59:59.000Z

263

ADVANCED OXIDATION PROCESS  

DOE Green Energy (OSTI)

The design of new, high efficiency and cleaner burning engines is strongly coupled with the removal of recalcitrant sulfur species, dibenzothiophene and its derivatives, from fuels. Oxidative desulfurization (ODS) wherein these dibenzothiophene derivatives are oxidized to their corresponding sulfoxides and sulfones is an approach that has gained significant attention. Fe-TAML{reg_sign} activators of hydrogen peroxide (TAML is Tetra-Amido-Macrocyclic-Ligand) convert in a catalytic process dibenzothiophene and its derivatives to the corresponding sulfoxides and sulfones rapidly at moderate temperatures (60 C) and ambient pressure. The reaction can be performed in both an aqueous system containing an alcohol (methanol, ethanol, or t-butanol) to solubilize the DBT and in a two-phase hydrocarbon/aqueous system where the alcohol is present in both phases and facilitates the oxidation. Under a consistent set of conditions using the FeBF{sub 2} TAML activator, the degree of conversion was found to be t-butanol > methanol > ethanol. In the cases of methanol and ethanol, both the sulfoxide and sulfone were observed while for t-butanol only the sulfone was detected. In the two-phase system, the alcohol may function as an inverse phase transfer agent. The oxidation was carried out using two different TAML activators. In homogeneous solution, approximately 90% oxidation of the DBT could be achieved using the prototype TAML activator, FeB*, by sonicating the solution at near room temperature. In bi-phasic systems conversions as high as 50% were achieved using the FeB* TAML activator and hydrogen peroxide at 100 C. The sonication method yielded only {approx}6% conversion but this may have been due to mixing.

Colin P. Horwitz; Terrence J. Collins

2003-10-22T23:59:59.000Z

264

Billiards with polynomial mixing rates  

E-Print Network (OSTI)

While many dynamical systems of mechanical origin, in particular billiards, are strongly chaotic -- enjoy exponential mixing, the rates of mixing in many other models are slow (algebraic, or polynomial). The dynamics in the latter are intermittent between regular and chaotic, which makes them particularly interesting in physical studies. However, mathematical methods for the analysis of systems with slow mixing rates were developed just recently and are still difficult to apply to realistic models. Here we reduce those methods to a practical scheme that allows us to obtain a nearly optimal bound on mixing rates. We demonstrate how the method works by applying it to several classes of chaotic billiards with slow mixing as well as discuss a few examples where the method, in its present form, fails.

Nikolai Chernov; Hong-Kun Zhang

2004-09-12T23:59:59.000Z

265

Treatment of Radioactive Reactive Mixed Waste  

Science Conference Proceedings (OSTI)

PacificEcoSolutions, Inc. (PEcoS) has installed a plasma gasification system that was recently modified and used to destroy a trimethyl-aluminum mixed waste stream from Los Alamos National Laboratory (LANL.) The unique challenge in handling reactive wastes like trimethyl-aluminum is their propensity to flame instantly on contact with air and to react violently with water. To safely address this issue, PacificEcoSolutions has developed a new feed system to ensure the safe containment of these radioactive reactive wastes during transfer to the gasification unit. The plasma gasification system safely processed the radioactively contaminated trimethyl-metal compounds into metal oxides. The waste stream came from LANL research operations, and had been in storage for seven years, pending treatment options. (authors)

Colby, S.; Turner, Z.; Utley, D. [Pacific EcoSolutions, Inc., 2025 Battelle Boulevard, Richland, Washington 99354 (United States); Duy, C. [Los Alamos National Laboratory - LA-UR-05-8410, Post Office Box 1663 MS J595, Los Alamos, New Mexico 97545 (United States)

2006-07-01T23:59:59.000Z

266

Implementation of deep soil mixing at the Kansas City Plant  

Science Conference Proceedings (OSTI)

In July 1996, the US Department of Energy (DOE) Kansas City Plant (KCP), AlliedSignal Federal Manufacturing and Technologies, and Oak Ridge National Laboratory (ORNL), conducted field-scale tests of in situ soil mixing and treatment technologies within the Northeast Area (NEA) of the KCP at the Former Ponds site. This demonstration, testing, and evaluation effort was conducted as part of the implementation of a deep soil mixing (DSM) innovative remedial technology demonstration project designed to test DSM in the low-permeability clay soils at the KCP. The clay soils and groundwater beneath this area are contaminated by volatile organic compounds (VOCs), primarily trichloroethene (TCE) and 1,2-dichloroethene (1,2-DCE). The demonstration project was originally designed to evaluate TCE and 1,2-DCE removal efficiency using soil mixing coupled with vapor stripping. Treatability study results, however, indicated that mixed region vapor stripping (MRVS) coupled with calcium oxide (dry lime powder) injection would improve TCE and 1,2-DCE removal efficiency in saturated soils. The scope of the KCP DSM demonstration evolved to implement DSM with the following in situ treatment methodologies for contaminant source reduction in soil and groundwater: DSM/MRVS coupled with calcium oxide injection; DSM/bioaugmentation; and DSM/chemical oxidation using potassium permanganate. Laboratory treatability studies were started in 1995 following collection of undisturbed soil cores from the KCP. These studies were conducted at ORNL, and the results provided information on optimum reagent concentrations and mixing ratios for the three in situ treatment agents to be implemented in the field demonstration.

Gardner, F.G.; Korte, N. [Oak Ridge National Lab., Grand Junction, CO (United States); Strong-Gunderson, J.; Siegrist, R.L.; West, O.R.; Cline, S.R. [Oak Ridge National Lab., TN (United States). Environmental Sciences Div.; Baker, J. [AlliedSignal, Inc., Kansas City, MO (United States)

1998-11-01T23:59:59.000Z

267

The Mixed Waste Management Facility. Preliminary design review  

Science Conference Proceedings (OSTI)

This document presents information about the Mixed Waste Management Facility. Topics discussed include: cost and schedule baseline for the completion of the project; evaluation of alternative options; transportation of radioactive wastes to the facility; capital risk associated with incineration; radioactive waste processing; scaling of the pilot-scale system; waste streams to be processed; molten salt oxidation; feed preparation; initial operation to demonstrate selected technologies; floorplans; baseline revisions; preliminary design baseline; cost reduction; and project mission and milestones.

NONE

1995-12-31T23:59:59.000Z

268

Fuel cycle stewardship in a nuclear renaissance 5 Recommendation 1  

E-Print Network (OSTI)

of fuel, thereby decreasing the attractiveness of plutonium in spent fuel for use in nuclear weapons plan for its reuse. This plan should seek to: · Minimise the amount of separated plutonium produced and the time for which it needs to be stored. · Convert separated plutonium into Mixed Oxide (MOX) fuel as soon

Rambaut, Andrew

269

Development of mixed-conducting ceramics for gas separation applications.  

DOE Green Energy (OSTI)

Mixed-conducting oxides are used in many applications, including fuel cells, gas separation membranes, sensors, and electrocatalysis. This paper describes mixed-conducting ceramic membranes that are being developed to selectively remove oxygen and hydrogen from gas streams in a nongalvanic mode of operation (i.e., with no electrodes or external power supply). Because of its high combined electronic/ionic conductivity and significant oxygen permeability, the mixed-conducting Sr-Fe-Co oxide (SFC) has been developed for high-purity oxygen separation and/or partial oxidation of methane to synthesis gas, i.e., syngas, a mixture of carbon monoxide and hydrogen. The electronic and ionic conductivities of SFC were found to be comparable in magnitude and are presented as a function of temperature. The oxygen flux through dense SFC tubes during separation of oxygen from air is compared with the oxygen flux during methane conversion. Unlike SFC, in which the ionic and electronic conductivities are nearly equivalent, BaCe{sub 0.80}Y{sub 0.20}O{sub 3} (BCY) exhibits protonic conductivity that is significantly higher than its electronic conductivity. To enhance the electronic conductivity and increase hydrogen permeation, metal powder was combined with the BCY to form a cermet membrane. Nongalvanic permeation of hydrogen through the cermet membrane was demonstrated and characterized as a function of membrane thickness. A sintering aid was developed to avoid interconnected porosity in and improve the mechanical properties of the cermet membrane.

Balachandran, U.

1998-12-02T23:59:59.000Z

270

A rational minor actinide (MA) recycling concept based on innovative oxide fuel with high AM content  

Science Conference Proceedings (OSTI)

A rational MA recycle concept based on high Am content fuel has been proposed. A design study of an Am- MOX fabrication plant, which is a key facility for the MA recycle concept, has been done and the facility concept was clarified from the viewpoint of basic process viability. Preliminary cost estimation suggested that the total construction cost of the MA recycle facilities including Am-MOX, Np-MOX and MA recovery could be comparable with that of the large scale LWR-MOX fabrication plant required for plutonium in LWR fuel cycle. (authors)

Tanaka, Kenya; Sato, Isamu; Ishii, Tetsuya; Yoshimochi, Hiroshi; Asaga, Takeo [Japan Atomic Energy Agency, 4002 Narita-cho, O-arai-machi, Higasiibaraki-gun, Ibaraki-ken, 311-1393 (Japan); Kurosaki, Ken [Osaka University, 2-1 Yamadaoka, Suita-shi, Osaka 565-0871 (Japan)

2007-07-01T23:59:59.000Z

271

Mixed Layer Instabilities and Restratification  

Science Conference Proceedings (OSTI)

The restratification of the oceanic surface mixed layer that results from lateral gradients in the surface density field is studied. The lateral gradients are shown to be unstable to ageostrophic baroclinic instabilities and slump from the ...

Giulio Boccaletti; Raffaele Ferrari; Baylor Fox-Kemper

2007-09-01T23:59:59.000Z

272

Fuel Mix and Emissions Disclosure  

Energy.gov (U.S. Department of Energy (DOE))

Iowa adopted regulations in 2003 that generally require rate-regulated electric utilities to disclose to customers the fuel mix and estimated emissions, in pounds per megawatt-hour (MWh), of...

273

Fuel Mix and Emissions Disclosure  

Energy.gov (U.S. Department of Energy (DOE))

Rhode Island requires all entities that sell electricity in the state to disclose details regarding the fuel mix and emissions of their electric generation to end-use customers. This information...

274

The Subinertial Mixed Layer Approximation  

Science Conference Proceedings (OSTI)

The density of the mixed layer is approximately uniform in the vertical but has dynamically important horizontal gradients. These nonuniformities in density result in a vertically sheared horizontal pressure gradient. Subinertial motions balance ...

W. R. Young

1994-08-01T23:59:59.000Z

275

Meridional Motion of Mixing Eddies  

Science Conference Proceedings (OSTI)

A two-layer model of anticyclonic eddy propagation including the effects of diapycnal mixing is presented. The lower layer is assumed to be of finite volume, whereas the upper layer is infinite in horizontal extent, and its dynamics are ...

N. Robb McDonald; David N. Straub

1995-05-01T23:59:59.000Z

276

Density Coordinate Mixed Layer Models  

Science Conference Proceedings (OSTI)

The development of mixed layer models in so-called density coordinates is discussed. Density coordinates, or isopycnal coordinates as they are sometimes called, are becoming increasingly popular for use in ocean models due to their highly ...

William K. Dewar

2001-02-01T23:59:59.000Z

277

A Characteristics-Based Approach to Radioactive Waste Classification in Advanced Nuclear Fuel Cycles  

E-Print Network (OSTI)

water  reactor   mixed  low-­?level  waste   viii   MOX  includes   mixed   low-­?level   waste   (MLLW)   and  These  include  mixed  low-­?level  wastes  (MLLW),  for  

Djokic, Denia

2013-01-01T23:59:59.000Z

278

Independent Oversight Review, Advanced Mixed Waste Treatment...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Review, Advanced Mixed Waste Treatment Project - April 2013 Independent Oversight Review, Advanced Mixed Waste Treatment Project - April 2013 April 2013 Review of Radiation...

279

Occupant satisfaction in mixed-mode buildings  

E-Print Network (OSTI)

Environmental Quality in Green Buildings”. Indoor Air; 14 (Strategies for Mixed-Mode Buildings, Summary Report, CenterCBE). 2006. Website: Mixed-Mode Building Case Studies.

Brager, Gail; Baker, Lindsay

2009-01-01T23:59:59.000Z

280

Occupant satisfaction in mixed-mode buildings.  

E-Print Network (OSTI)

Strategies for Mixed-Mode Buildings, Summary Report, CenterCBE). 2006. Website: Mixed-Mode Building Case Studies.Department of Environmental Building Research Establishment

Brager, Gail; Baker, Lindsay

2008-01-01T23:59:59.000Z

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


281

Mixed-Mode Ventilation and Building Retrofits  

E-Print Network (OSTI)

November 1994, ENTPE, Lyon. [CIBSE] Chartered Institution ofMixed-mode ventilation. CIBSE Applications Manual AM13.incorporated by the design. CIBSE, 2000 Mixed-mode

Brager, Gail; Ackerly, Katie

2010-01-01T23:59:59.000Z

282

Does Mixing Make Residential Ventilation More Effective?  

E-Print Network (OSTI)

Does Mixing Make Residential Ventilation More Effective? Maxmanufacturer, or otherwise, does not necessarily constitutethe University of California. Does Mixing Make Residential

Sherman, Max

2011-01-01T23:59:59.000Z

283

Sensors and Actuators B 119 (2006) 384391 Fine-tuning of ceramic-based chemical sensors  

E-Print Network (OSTI)

energy of formation of the oxide, MOx. A plot of 2Op or 2 ln Op vs. temperature, gives the contour of the path of the M/MOx coexistence. Using reliable Gibbs energy data [2-3], the loci of 210log Op that established by virtue of thermodynamic equilibrium between M and MOx or between MOx and MOy, this allows

Azad, Abdul-Majeed

284

Published by Blackwell Publishing for the American Ceramic Society www.ceramics.org  

E-Print Network (OSTI)

of the oxide, MOx. A plot of 2Op or 2 ln Op vs. temperature, gives the contour of the path of the M/MOx by virtue of thermodynamic equilibrium between M and MOx or between MOx and MOy, this allows the formation

Azad, Abdul-Majeed

285

Disposition of weapons-grade plutonium in Westinghouse reactors  

E-Print Network (OSTI)

We have studied the feasibility of using weapons-grade plutonium in the form of mixed-oxide (MOX) fuel in existing Westinghouse reactors. We have designed three transition cycles from an all LEU core to a partial MOX core. We found that four-loop Westinghouse reactors such as the Vogtle power plant are capable of handling up to 45 percent weapons-grade MOX loading without any modifications. We have also designed two kinds of weapons-grade MOX assemblies with three enrichments per assembly and four enrichments total. Wet annular burnable absorber (WABA) rods were used in all the feed and some burned MOX assemblies and some LEU feed assemblies. Integral fuel burnable absorber (IFBA) was used in the rest of the LEU feed assemblies. The average discharge burnup of MOX assemblies was over 47,000 MWD/MTM, which is more than enough to meet the "spent fuel standard." One unit is capable of consuming 0.462 MT of weapons-grade plutonium a year. Preliminary analyses showed that important reactor physics parameters for the three transitions cycles are comparable to those of LEU cores including boron levels, reactivity coefficients, peaking factors, and shutdown margins. Further transient analyses need to be performed.

Alsaed, Abdelhalim Ali

1996-01-01T23:59:59.000Z

286

Oxidation catalyst  

DOE Patents (OSTI)

The present invention generally relates to catalyst systems and methods for oxidation of carbon monoxide. The invention involves catalyst compositions which may be advantageously altered by, for example, modification of the catalyst surface to enhance catalyst performance. Catalyst systems of the present invention may be capable of performing the oxidation of carbon monoxide at relatively lower temperatures (e.g., 200 K and below) and at relatively higher reaction rates than known catalysts. Additionally, catalyst systems disclosed herein may be substantially lower in cost than current commercial catalysts. Such catalyst systems may be useful in, for example, catalytic converters, fuel cells, sensors, and the like.

Ceyer, Sylvia T. (Cambridge, MA); Lahr, David L. (Cambridge, MA)

2010-11-09T23:59:59.000Z

287

Nuclear Utility Mixed Waste Stream Characterization Study  

Science Conference Proceedings (OSTI)

This report presents industry experience at nuclear utilities in characterizing the hazardous component of potential mixed waste streams. It identifies key considerations for characterizing mixed waste; provides background information, including actual sample results, on the majority of plant processes with a potential to generate mixed waste; and presents a methodology for characterizing mixed waste.

1994-12-31T23:59:59.000Z

288

Hanford Small Scale Mixing Demonstration Program  

Hanford Small Scale Mixing Demonstration Program EM Waste Processing Technical Exchange November 17, 2010 Mike Thien

289

Mixed ternary heterojunction solar cell  

SciTech Connect

A thin film heterojunction solar cell and a method of making it has a p-type layer of mixed ternary I-III-VI.sub.2 semiconductor material in contact with an n-type layer of mixed binary II-VI semiconductor material. The p-type semiconductor material includes a low resistivity copper-rich region adjacent the back metal contact of the cell and a composition gradient providing a minority carrier mirror that improves the photovoltaic performance of the cell. The p-type semiconductor material preferably is CuInGaSe.sub.2 or CuIn(SSe).sub.2.

Chen, Wen S. (Seattle, WA); Stewart, John M. (Seattle, WA)

1992-08-25T23:59:59.000Z

290

The Mixed Waste Management Facility monthly report and revised FY95 plan, May 1995  

Science Conference Proceedings (OSTI)

This report contains the project summary, as well as the financial summary for the Mixed Waste Management Facility at Lawrence Livermore National Laboratory. Detailed accomplishments and milestone status are reported in the Task Summaries. The major accomplishments during this reporting period are included the following areas: preliminary design; systems integration; briefings for the Environmental Programs Scientific Advisory Committee; integrated cost/scheduling estimating system; feed preparation; mediated electrochemical oxidation; and molten salt oxidation.

Streit, R.D.

1995-06-01T23:59:59.000Z

291

ROLE OF CONSTITUENT ELEMENTS IN PROPANE OXIDATION OVER MIXED METAL OXIDES.  

E-Print Network (OSTI)

??Recently discovered multi-component Mo-V-Te-Nb-O catalysts contain so-called “M1” and “M2” phases with orthorhombic and hexagonal structures, respectively, proposed to be active and selective in propane… (more)

BHANDARI, RISHABH

2005-01-01T23:59:59.000Z

292

Mixed-conducting ceramic membranes for partial oxygenation of methane  

DOE Green Energy (OSTI)

The most significant cost associated with the conventional partial oxidation of methane is that of an oxygen plant. Our new technology offers a way to lower this cost, and in this paper we explore the technology that is based on dense ceramic membranes and that uses air as the oxidant for methane-conversion reactions. Mixed-conducting ceramic materials have been produced from mixed-oxide systems of the La-Sr-Fe-Co-O (SFC) type, in the form of tubes and bars. Thermodynamic stability of the tubes was studied as a function of oxygen partial pressure by high-temperature XRD. Mechanical properties were measured and found to be adequate for a reactor in the case of SFC-2: Electronic and ionic conductivities were measured; SFC-2 is unique in the sense that the ratio of ionic to electronic conductance is close to unity. Performance of the membrane tubes was good only with SFC-2. Fracture of other SFC tubes was the consequence of an oxygen gradient that introduced a volumetric lattice difference between the inner and outer walls. SFC-2 tubes provided methane conversion efficiencies of >99% in a reactor. These tubes have operated for >1000 h.

Balachandran, U.; Dusek, J.T.; Maiya, P.S.; Mieville, R.L. [Argonne National Lab., IL (United States); Kleefisch, M.S.; Udovich, C.A. [Amoco Corp., Naperville, IL (United States); Bose, A.C. [USDOE Pittsburgh Energy Technology Center, PA (United States)

1995-05-01T23:59:59.000Z

293

Dark energy and particle mixing  

E-Print Network (OSTI)

We show that the vacuum condensate due to particle mixing is responsible of a dynamically evolving dark energy. In particular, we show that values of the adiabatic index close to -1 for vacuum condensates of neutrinos and quarks imply, at the present epoch, contributions to the vacuum energy compatible with the estimated upper bound on the dark energy.

A. Capolupo; S. Capozziello; G. Vitiello

2008-08-30T23:59:59.000Z

294

Advances in compressible turbulent mixing  

Science Conference Proceedings (OSTI)

This volume includes some recent additions to original material prepared for the Princeton International Workshop on the Physics of Compressible Turbulent Mixing, held in 1988. Workshop participants were asked to emphasize the physics of the compressible mixing process rather than measurement techniques or computational methods. Actual experimental results and their meaning were given precedence over discussions of new diagnostic developments. Theoretical interpretations and understanding were stressed rather than the exposition of new analytical model developments or advances in numerical procedures. By design, compressibility influences on turbulent mixing were discussed--almost exclusively--from the perspective of supersonic flow field studies. The papers are arranged in three topical categories: Foundations, Vortical Domination, and Strongly Coupled Compressibility. The Foundations category is a collection of seminal studies that connect current study in compressible turbulent mixing with compressible, high-speed turbulent flow research that almost vanished about two decades ago. A number of contributions are included on flow instability initiation, evolution, and transition between the states of unstable flow onset through those descriptive of fully developed turbulence. The Vortical Domination category includes theoretical and experimental studies of coherent structures, vortex pairing, vortex-dynamics-influenced pressure focusing. In the Strongly Coupled Compressibility category the organizers included the high-speed turbulent flow investigations in which the interaction of shock waves could be considered an important source for production of new turbulence or for the enhancement of pre-existing turbulence. Individual papers are processed separately.

Dannevik, W.P.; Buckingham, A.C.; Leith, C.E. [eds.

1992-01-01T23:59:59.000Z

295

Ceramic-based fuel technologies: scope and status  

SciTech Connect

This presentation is an overview of the approach, status and path forward for ongoing tasks under the ceramic fuel development part of the program. Experimental work is focused on fundamental studies employing depleted urania-based compositions and mixed oxide (MOX) and minor actinide-bearing MOX. Contributions are included from researchers at LANL, ORNL and BNL. The audience for this presentation consists of the various participants in the FCRD program. Those participants include representatives from: DOE-NE, other national laboratories, DOE funded university researchers, DOE funded industry teams, FCRD funded advisors, and occasionally NRC.

Mcclellan, Kenneth J [Los Alamos National Laboratory

2010-12-16T23:59:59.000Z

296

Nuclear Fuel Cycle Cost Comparison Between Once-Through and Plutonium Multi-Recycling in Fast Reactors  

Science Conference Proceedings (OSTI)

This report presents results from a parametric study of equilibrium fuel cycle costs for a closed fuel cycle with multi-recycling of plutonium in fast reactors (FRs) compared to an open, once-through fuel cycle using PWRs. The study examines the impact on fuel cycle costs from changes in the unit costs of uranium, advanced PUREX reprocessing of discharged uranium dioxide (UO2) fuel and fast-reactor mixed-oxide (FR-MOX) fuel, and FR-MOX fuel fabrication. In addition, the impact associated with changes in ...

2010-03-15T23:59:59.000Z

297

Power Production in MFCs Inoculated With Shewanella oneidensis MR-1 or Mixed Cultures  

E-Print Network (OSTI)

.1002/bit.22556 ABSTRACT: Power densities and oxidation­reduction potentials (ORPs) of MFCs containing. Power was a direct function of ohmic resistance for the mixed culture, but not for strain MR-1. ORP maximum power production but it did not vary in proportion to power output. The ORP varied primarily

298

AP-XPS Measures MIEC Oxides in Action  

NLE Websites -- All DOE Office Websites (Extended Search)

AP-XPS Measures MIEC Oxides in AP-XPS Measures MIEC Oxides in Action AP-XPS Measures MIEC Oxides in Action Print Wednesday, 25 May 2011 00:00 Oxide materials with mixed ionic-electronic conductivity (MIEC) can conduct both electrons and oxygen ions. MIEC oxides have broad applications, including use in solid-oxide fuel cells, high-temperature electrolysis for synthetic fuel production, and oxygen-separating membranes for chemical processes or NOx-free combustion; however, their surface activity under reaction conditions has been difficult, if not impossible, to ascertain, until recently. A team from the University of Maryland and Sandia National Laboratories joined ALS scientists on Beamlines 9.3.2 and 11.0.2 to overcome the vacuum limitations of conventional XPS instruments using ambient-pressure x-ray photoelectron spectroscopy (AP-XPS), providing the first in situ measurements of local surface oxidation states and electric potential in active MIEC electrodes.

299

Mixed Alcohol Synthesis Catalyst Screening  

DOE Green Energy (OSTI)

National Renewable Energy Laboratory (NREL) and Pacific Northwest National Laboratory (PNNL) are conducting research to investigate the feasibility of producing mixed alcohols from biomass-derived synthesis gas (syngas). PNNL is tasked with obtaining commercially available or preparing promising mixed-alcohol catalysts and screening them in a laboratory-scale reactor system. Commercially available catalysts and the most promising experimental catalysts are provided to NREL for testing using a slipstream from a pilot-scale biomass gasifier. From the standpoint of producing C2+ alcohols as the major product, it appears that the rhodium catalyst is the best choice in terms of both selectivity and space-time yield (STY). However, unless the rhodium catalyst can be improved to provide minimally acceptable STYs for commercial operation, mixed alcohol synthesis will involve significant production of other liquid coproducts. The modified Fischer-Tropsch catalyst shows the most promise for providing both an acceptable selectivity to C2+ alcohols and total liquid STY. However, further optimization of the Fischer-Tropsch catalysts to improve selectivity to higher alcohols is highly desired. Selection of a preferred catalyst will likely entail a decision on the preferred coproduct slate. No other catalysts tested appear amenable to the significant improvements needed for acceptable STYs.

Gerber, Mark A.; White, James F.; Stevens, Don J.

2007-09-03T23:59:59.000Z

300

Smooth mixed-resolution GPU volume rendering  

Science Conference Proceedings (OSTI)

We propose a mixed-resolution volume ray-casting approach that enables more flexibility in the choice of downsampling positions and filter kernels, allows freely mixing volume bricks of different resolutions during rendering, and does not require modifying ...

Johanna Beyer; Markus Hadwiger; Torsten Möller; Laura Fritz

2008-08-01T23:59:59.000Z

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


301

Neutrino mixing, flavor states and dark energy  

E-Print Network (OSTI)

We shortly summarize the quantum field theory formalism for the neutrino mixing and report on recent results showing that the vacuum condensate induced by neutrino mixing can be interpreted as a dark energy component of the Universe.

M. Blasone; A. Capolupo; S. Capozziello; G. Vitiello

2007-11-06T23:59:59.000Z

302

Tidal Mixing Signatures in the Indonesian Seas  

Science Conference Proceedings (OSTI)

Expressions of low-frequency tidal periods are found throughout the Indonesian Seas' temperature field, supporting the hypothesis that vertical mixing is enhanced within the Indonesian Seas by the tides. The thermal signatures of tidal mixing ...

Amy Ffield; Arnold L. Gordon

1996-09-01T23:59:59.000Z

303

XPS Determination of Uranium Oxidations States  

SciTech Connect

This contribution is both a review of different aspects of the XPS spectra that can help one determine U oxidation states and a personal perspective on how to effectively model the XPS of complicated mixed valence U phases. After a discussion of the valence band, the focus lingers on the U4f region, where the use of binding energies, satellite structures, and peak shapes is discussed in some detail. Binding energies were shown to be very dependent on composition/structure and consequently unreliable guides to oxidation state, particularly where assignment of composition is difficult. Likewise, the spin orbit split 4f7/2 and 4f5/2 peak shapes do not carry significant information on oxidation states. In contrast, both satellite-primary peak binding energy separations, as well as intensities too lesser extent, are relatively insensitive to composition/structure within the oxide-hydroxide-hydrate system and can be used to both identify and help quantify U oxidation states in mixed valence phases. An example of the usefulness of the satellite structure in constraining the interpretation of a complex multivalence U compound is given.

Ilton, Eugene S.; Bagus, Paul S.

2011-12-01T23:59:59.000Z

304

Scanned Treatment of Mixed Incin. Waste  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Treatment of Mixed Incinerable Treatment of Mixed Incinerable Waste DOE/IG-0588 March 2003 Page 17 Page 18 Use of Treatment Resources Details of Finding ........................................................................1 Recommendations and Comments ............................................6 Appendices Prior Reports ...............................................................................8 Objective, Scope, and Methodology ...........................................9 Management Comments ...........................................................11 TREATMENT OF MIXED INCINERABLE WASTE TABLE OF CONTENTS Page 1 Waste Stored Rather Than Treated We found the Department of Energy (Department) was not treating its mixed incinerable solid waste expeditiously or cost-effectively.

305

Dark energy induced by neutrino mixing  

E-Print Network (OSTI)

The energy content of the vacuum condensate induced by the neutrino mixing is interpreted as dynamically evolving dark energy.

Antonio Capolupo; Salvatore Capozziello; Giuseppe Vitiello

2006-12-05T23:59:59.000Z

306

Optimization Online - Solving mixed integer nonlinear programming ...  

E-Print Network (OSTI)

Nov 8, 2012 ... Solving mixed integer nonlinear programming problems for mine production planning with stockpiling. Andreas Bley(bley ***at*** ...

307

Mixed wasted integrated program: Logic diagram  

SciTech Connect

The Mixed Waste Integrated Program Logic Diagram was developed to provide technical alternative for mixed wastes projects for the Office of Technology Development`s Mixed Waste Integrated Program (MWIP). Technical solutions in the areas of characterization, treatment, and disposal were matched to a select number of US Department of Energy (DOE) treatability groups represented by waste streams found in the Mixed Waste Inventory Report (MWIR).

Mayberry, J.; Stelle, S. [Science Applications International Corp., Idaho Falls, ID (United States); O`Brien, M. [Univ. of Arizona, Tucson, AZ (United States); Rudin, M. [Univ. of Nevada, Las Vegas, NV (United States); Ferguson, J. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); McFee, J. [I.T. Corp., Albuquerque, NM (United States)

1994-11-30T23:59:59.000Z

308

Salad Mixes for the Home Garden  

E-Print Network (OSTI)

Gardener Salad Mixes for the Home Garden owever you assesssalads. (Note: For the home gardener, the use of edible ?

Martin, Orin

2008-01-01T23:59:59.000Z

309

Planar ceramic membrane assembly and oxidation reactor system  

DOE Patents (OSTI)

Planar ceramic membrane assembly comprising a dense layer of mixed-conducting multi-component metal oxide material, wherein the dense layer has a first side and a second side, a porous layer of mixed-conducting multi-component metal oxide material in contact with the first side of the dense layer, and a ceramic channeled support layer in contact with the second side of the dense layer. The planar ceramic membrane assembly can be used in a ceramic wafer assembly comprising a planar ceramic channeled support layer having a first side and a second side; a first dense layer of mixed-conducting multi-component metal oxide material having an inner side and an outer side, wherein the inner side is in contact with the first side of the ceramic channeled support layer; a first outer support layer comprising porous mixed-conducting multi-component metal oxide material and having an inner side and an outer side, wherein the inner side is in contact with the outer side of the first dense layer; a second dense layer of mixed-conducting multi-component metal oxide material having an inner side and an outer side, wherein the inner side is in contact with the second side of the ceramic channeled layer; and a second outer support layer comprising porous mixed-conducting multi-component metal oxide material and having an inner side and an outer side, wherein the inner side is in contact with the outer side of the second dense layer.

Carolan, Michael Francis (Allentown, PA); Dyer, legal representative, Kathryn Beverly (Allentown, PA); Wilson, Merrill Anderson (West Jordan, UT); Ohm, Ted R. (Alliance, OH); Kneidel, Kurt E. (Alliance, OH); Peterson, David (Uniontown, OH); Chen, Christopher M. (Allentown, PA); Rackers, Keith Gerard (Louisville, OH); Dyer, deceased, Paul Nigel (Allentown, PA)

2007-10-09T23:59:59.000Z

310

Planar ceramic membrane assembly and oxidation reactor system  

DOE Patents (OSTI)

Planar ceramic membrane assembly comprising a dense layer of mixed-conducting multi-component metal oxide material, wherein the dense layer has a first side and a second side, a porous layer of mixed-conducting multi-component metal oxide material in contact with the first side of the dense layer, and a ceramic channeled support layer in contact with the second side of the dense layer. The planar ceramic membrane assembly can be used in a ceramic wafer assembly comprising a planar ceramic channeled support layer having a first side and a second side; a first dense layer of mixed-conducting multi-component metal oxide material having an inner side and an outer side, wherein the inner side is in contact with the first side of the ceramic channeled support layer; a first outer support layer comprising porous mixed-conducting multi-component metal oxide material and having an inner side and an outer side, wherein the inner side is in contact with the outer side of the first dense layer; a second dense layer of mixed-conducting multi-component metal oxide material having an inner side and an outer side, wherein the inner side is in contact with the second side of the ceramic channeled layer; and a second outer support layer comprising porous mixed-conducting multi-component metal oxide material and having an inner side and an outer side, wherein the inner side is in contact with the outer side of the second dense layer.

Carolan, Michael Francis (Allentown, PA); Dyer, legal representative, Kathryn Beverly (Allentown, PA); Wilson, Merrill Anderson (West Jordan, UT); Ohrn, Ted R. (Alliance, OH); Kneidel, Kurt E. (Alliance, OH); Peterson, David (Uniontown, OH); Chen, Christopher M. (Allentown, PA); Rackers, Keith Gerard (Louisville, OH); Dyer, Paul Nigel (Allentown, PA)

2009-04-07T23:59:59.000Z

311

Multi-stage, isothermal CO preferential oxidation reactor  

DOE Patents (OSTI)

A multi-stage, isothermal, carbon monoxide preferential oxidation (PrOx) reactor comprising a plurality of serially arranged, catalyzed heat exchangers, each separated from the next by a mixing chamber for homogenizing the gases exiting one heat exchanger and entering the next. In a preferred embodiment, at least some of the air used in the PrOx reaction is injected directly into the mixing chamber between the catalyzed heat exchangers.

Skala, Glenn William (Churchville, NY); Brundage, Mark A. (Pittsford, NY); Borup, Rodney Lynn (East Rochester, NY); Pettit, William Henry (Rochester, NY); Stukey, Kevin (W. Henrietta, NY); Hart-Predmore, David James (Rochester, NY); Fairchok, Joel (Alexander, NY)

2000-01-01T23:59:59.000Z

312

Photocatalytic Oxidation of Aqueous Organic Contaminants by Semiconductors using Visible Light Radiation  

E-Print Network (OSTI)

· Continuously mixed Light Source · T5 8 watt florescent bulbs · "Daylight Spectrum" · Color Rendering Index 75Photocatalytic Oxidation of Aqueous Organic Contaminants by Semiconductors using Visible Light

Meyers, Steven D.

313

Advanced materials for solid oxide fuel cells: Hafnium-Praseodymium-Indium Oxide System  

DOE Green Energy (OSTI)

The HfO/sub 2/-PrO/sub 1.83/-In/sub 2/O/sub 3/ system has been studied at the Pacific Northwest Laboratory to develop alternative, highly electrically conducting oxides as electrode and interconnection materials for solid oxide fuel cells. A coprecipitation process was developed for synthesizing single-phase, mixed oxide powders necessary to fabricate powders and dense oxides. A ternary phase diagram was developed, and the phases and structures were related to electrical transport properties. Two new phases, an orthorhombic PrInO/sub 3/ and a rhombohedral Hf/sub 2/In/sub 2/O/sub 7/ phase, were identified. The highest electronic conductivity is related to the presence of a bcc, In/sub 2/O/sub 3/ solid solution (ss) containing HfO/sub 2/ and PrO/sub 1.83/. Compositions containing more than 35 mol % of the In/sub 2/O/sub 3/ ss have electrical conductivities greater than 10/sup /minus/1/ (ohm-cm)/sup /minus/1/, and the two or three phase structures that contain this phase appear to exhibit mixed electronic-ionic conduction. The high electrical conductivities and structures similar to the Y/sub 2/O/sub 3/-stabilized ZrO/sub 2/(HfO/sub 2/) electrolyte give these oxides potential for use as cathodes in solid oxide fuel cells. 21 refs.

Bates, J.L.; Griffin, C.W.; Weber, W.J.

1988-06-01T23:59:59.000Z

314

RADIOLOGICAL HEALTH AND RELATED STANDARDS FOR NUCLEAR POWER PLANTS. VOLUME 2 OF HEALTH AND SAFETY IMPACTS OF NUCLEAR, GEOTHERMAL, AND FOSSIL-FUEL ELECTRIC GENERATION IN CALIFORNIA  

E-Print Network (OSTI)

2000. Total fuel mix is 11% MOX + 89% U0 fuel with PuRadionuclide H U0 Fuel U0 + MOX Fuel 14C Kr I llO Other

Nero, A.V.

2010-01-01T23:59:59.000Z

315

Science and applications of mixed conductors for lithium batteries.  

DOE Green Energy (OSTI)

Mixed conductors show significant mobility of both electronic and ionic species and were the subject of an earlier review in MRS Bulletin. The current review is restricted to those mixed conductors of interest for use in lithium batteries, with an emphasis on commercialization. The first lithium batteries were primary cells using pure lithium anodes and carbon monofluoride or manganese oxide as the cathode. Both were developed in Japan, the former for use in fishing floats and the latter for calculators and similar small devices. Such primary cells based mainly on MnO{sub 2} or FeS{sub 2} cathodes are still extensively used in watches, cameras, and so on. Lithium primary cells are also the main power source for many medical devices, such as pacemakers. In some of these applications, silver vanadate is the cathode. The recognition of the role of intercalation/ insertion reactions in battery electrodes just over 25 years ago allowed significant progress to be made in secondary (rechargeable) lithium batteries. From the first prototypical titanium disulfide cells, the technology has more recently been commercialized by Sony Corp. in the Li-ion cell, using a cobalt oxide insertion cathode and a carbon insertion anode. In the former, commercialized by Exxon, the reaction is the simple intercalation of lithium ions between sheets of TiS{sub 2}.

Thackeray, M. M.; Thomas, J.; Whittingham, M. S.; Chemical Engineering

2000-03-01T23:59:59.000Z

316

Mixed Manual/Semi-Automated Traffic: A Macroscopic Analysis  

E-Print Network (OSTI)

of Traffic Flow with Mixed Manual and Semi- Automatedof Mixed Semi-Automated/Manual Traffic”, SAE Technical Paperof traffic flow with mixed manual and semi- automated

Bose, Arnab; Ioannou, Petros

2001-01-01T23:59:59.000Z

317

Fuel Mix Disclosure | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Fuel Mix Disclosure Fuel Mix Disclosure Fuel Mix Disclosure < Back Eligibility Utility Program Info State Colorado Program Type Generation Disclosure Provider Colorado Public Utilities Commission In January 1999, the Colorado Public Utility Commission (PUC) adopted regulations requiring the state's utilities to disclose information regarding their fuel mix to retail customers. Utilities are required to provide this information as a bill insert or as a separate mailing twice annually, in April and October of every year. The PUC provides a suggested format for the disclosure. Fuel mix percentages are to be based on the power supply mix for the previous calendar year. Supporting documentation concerning the calculations used to determine the power supply mix percentages must be submitted to the PUC for approval.

318

Expandable mixing section gravel and cobble eductor  

DOE Patents (OSTI)

In a hydraulically powered pump for excavating and transporting slurries in hich it is immersed, the improvement of a gravel and cobble eductor including an expandable mixing section, comprising: a primary flow conduit that terminates in a nozzle that creates a water jet internal to a tubular mixing section of the pump when water pressure is applied from a primary supply flow; a tubular mixing section having a center line in alignment with the nozzle that creates a water jet; a mixing section/exit diffuser column that envelopes the flexible liner; and a secondary inlet conduit that forms an opening at a bas portion of the column and adjacent to the nozzle and water jet to receive water saturated gravel as a secondary flow that mixes with the primary flow inside of the mixing section to form a combined total flow that exits the mixing section and decelerates in the exit diffuser.

Miller, Arthur L. (Kenyon, MN); Krawza, Kenneth I. (Lakeville, MN)

1997-01-01T23:59:59.000Z

319

Device for staged carbon monoxide oxidation  

DOE Patents (OSTI)

A method and apparatus for selectively oxidizing carbon monoxide in a hydrogen rich feed stream. The method comprises mixing a feed stream consisting essentially of hydrogen, carbon dioxide, water and carbon monoxide with a first predetermined quantity of oxygen (air). The temperature of the mixed feed/oxygen stream is adjusted in a first the heat exchanger assembly (20) to a first temperature. The mixed feed/oxygen stream is sent to reaction chambers (30,32) having an oxidation catalyst contained therein. The carbon monoxide of the feed stream preferentially absorbs on the catalyst at the first temperature to react with the oxygen in the chambers (30,32) with minimal simultaneous reaction of the hydrogen to form an intermediate hydrogen rich process stream having a lower carbon monoxide content than the feed stream. The elevated outlet temperature of the process stream is carefully controlled in a second heat exchanger assembly (42) to a second temperature above the first temperature. The process stream is then mixed with a second predetermined quantity of oxygen (air). The carbon monoxide of the process stream preferentially reacts with the second quantity of oxygen in a second stage reaction chamber (56) with minimal simultaneous reaction of the hydrogen in the process stream. The reaction produces a hydrogen rich product stream having a lower carbon monoxide content than the process stream. The product stream is then cooled in a third heat exchanger assembly (72) to a third predetermined temperature. Three or more stages may be desirable, each with metered oxygen injection.

Vanderborgh, Nicholas E. (Los Alamos, NM); Nguyen, Trung V. (College Station, TX); Guante, Jr., Joseph (Denver, CO)

1993-01-01T23:59:59.000Z

320

Lipid Oxidation Pathways  

Science Conference Proceedings (OSTI)

This book reviews state-of-the-art developments in the understanding of the oxidation of lipids and its connection with the oxidation of other biological molecules such as proteins and starch. Lipid Oxidation Pathways Hardback Books Health - Nutrition -

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


321

Delivery system for molten salt oxidation of solid waste  

DOE Patents (OSTI)

The present invention is a delivery system for safety injecting solid waste particles, including mixed wastes, into a molten salt bath for destruction by the process of molten salt oxidation. The delivery system includes a feeder system and an injector that allow the solid waste stream to be accurately metered, evenly dispersed in the oxidant gas, and maintained at a temperature below incineration temperature while entering the molten salt reactor.

Brummond, William A. (Livermore, CA); Squire, Dwight V. (Livermore, CA); Robinson, Jeffrey A. (Manteca, CA); House, Palmer A. (Walnut Creek, CA)

2002-01-01T23:59:59.000Z

322

AP-XPS Measures MIEC Oxides in Action  

NLE Websites -- All DOE Office Websites (Extended Search)

AP-XPS Measures MIEC Oxides in Action Print AP-XPS Measures MIEC Oxides in Action Print Oxide materials with mixed ionic-electronic conductivity (MIEC) can conduct both electrons and oxygen ions. MIEC oxides have broad applications, including use in solid-oxide fuel cells, high-temperature electrolysis for synthetic fuel production, and oxygen-separating membranes for chemical processes or NOx-free combustion; however, their surface activity under reaction conditions has been difficult, if not impossible, to ascertain, until recently. A team from the University of Maryland and Sandia National Laboratories joined ALS scientists on Beamlines 9.3.2 and 11.0.2 to overcome the vacuum limitations of conventional XPS instruments using ambient-pressure x-ray photoelectron spectroscopy (AP-XPS), providing the first in situ measurements of local surface oxidation states and electric potential in active MIEC electrodes.

323

AP-XPS Measures MIEC Oxides in Action  

NLE Websites -- All DOE Office Websites (Extended Search)

AP-XPS Measures MIEC Oxides in Action Print AP-XPS Measures MIEC Oxides in Action Print Oxide materials with mixed ionic-electronic conductivity (MIEC) can conduct both electrons and oxygen ions. MIEC oxides have broad applications, including use in solid-oxide fuel cells, high-temperature electrolysis for synthetic fuel production, and oxygen-separating membranes for chemical processes or NOx-free combustion; however, their surface activity under reaction conditions has been difficult, if not impossible, to ascertain, until recently. A team from the University of Maryland and Sandia National Laboratories joined ALS scientists on Beamlines 9.3.2 and 11.0.2 to overcome the vacuum limitations of conventional XPS instruments using ambient-pressure x-ray photoelectron spectroscopy (AP-XPS), providing the first in situ measurements of local surface oxidation states and electric potential in active MIEC electrodes.

324

AP-XPS Measures MIEC Oxides in Action  

NLE Websites -- All DOE Office Websites (Extended Search)

AP-XPS Measures MIEC Oxides in Action Print AP-XPS Measures MIEC Oxides in Action Print Oxide materials with mixed ionic-electronic conductivity (MIEC) can conduct both electrons and oxygen ions. MIEC oxides have broad applications, including use in solid-oxide fuel cells, high-temperature electrolysis for synthetic fuel production, and oxygen-separating membranes for chemical processes or NOx-free combustion; however, their surface activity under reaction conditions has been difficult, if not impossible, to ascertain, until recently. A team from the University of Maryland and Sandia National Laboratories joined ALS scientists on Beamlines 9.3.2 and 11.0.2 to overcome the vacuum limitations of conventional XPS instruments using ambient-pressure x-ray photoelectron spectroscopy (AP-XPS), providing the first in situ measurements of local surface oxidation states and electric potential in active MIEC electrodes.

325

Selective methane oxidation over promoted oxide catalysts  

DOE Green Energy (OSTI)

Objective was to selectively oxidize methane to C{sub 2} hydrocarbons and to oxygenates, in particular formaldehyde and methanol, in high space time yields under relatively mild reaction conditions. Results in this document are reported under the headings: methane oxidation over silica, methane oxidation over Sr/La{sub 2}O{sub 3} catalysts, and oxidative coupling of methane over sulfate-doped Sr/La{sub 2}O{sub 3} catalysts. 24 refs, 10 figs, 4 tabs.

Klier, K.; Herman, R.G.

1993-12-31T23:59:59.000Z

326

Presented at: 4th ASM International Surface Engineering Congress & 19th  

E-Print Network (OSTI)

oxidation reaction: M(s) + x 2 O2(g) MOx(s) (1) for which K1 = aMOx aMp x/2 O2 (2a) and GR(1) = -RT ln K1, respectively, for reaction (1). Eqs. (2a) and (2b) can be combined and simplified to give: pO2(M/MOx) = exp 2 of the oxide, MOx. A plot of pO2 or ln pO2 versus temperature, gives the contour of the path of the M/MOx

Azad, Abdul-Majeed

327

Model catalytic oxidation studies using supported monometallic and heterobimetallic oxides. Progress report, August 1, 1991--January 31, 1992  

DOE Green Energy (OSTI)

This research program is directed toward a more fundamental understanding of the effects of catalyst composition and structure on the catalytic properties of metal oxides. Metal oxide catalysts play an important role in many reactions bearing on the chemical aspects of energy processes. Metal oxides are the catalysts for water-gas shift reactions, methanol and higher alcohol synthesis, isosynthesis, selective catalytic reduction of nitric oxides, and oxidation of hydrocarbons. A key limitation to developing insight into how oxides function in catalytic reactions is in not having precise information of the surface composition under reaction conditions. To address this problem we have prepared oxide systems that can be used to study cation-cation effects and the role of bridging (-O-) and/or terminal (=O) surface oxygen anion ligands in a systematic fashion. Since many oxide catalyst systems involve mixtures of oxides, we selected a model system that would permit us to examine the role of each cation separately and in pairwise combinations. Organometallic molybdenum and tungsten complexes were proposed for use, to prepare model systems consisting of isolated monomeric cations, isolated monometallic dimers and isolated bimetallic dimers supported on silica and alumina. The monometallic and bimetallic dimers were to be used as models of more complex mixed- oxide catalysts. Our current program was to develop the systems and use them in model oxidation reactions.

Ekerdt, J.G.

1992-02-03T23:59:59.000Z

328

Mercury removal from solid mixed waste  

SciTech Connect

The removal of mercury from mixed wastes is an essential step in eliminating the temporary storage of large inventories of mixed waste throughout the Department of Energy (DOE) complex. Currently thermal treatment has been identified as a baseline technology and is being developed as part of the DOE Mixed Waste Integrated Program (MWIP). Since thermal treatment will not be applicable to all mercury containing mixed waste and the removal of mercury prior to thermal treatment may be desirable, laboratory studies have been initiated at Oak Ridge National Laboratory (ORNL) to develop alternative remediation technologies capable of removing mercury from certain mixed waste. This paper describes laboratory investigations of the KI/I{sub 2} leaching processes to determine the applicability of this process to mercury containing solid mixed waste.

Gates, D.D.; Morrissey, M.; Chava, K.K.; Chao, K.

1994-12-31T23:59:59.000Z

329

Radwaste Desk Reference: Volume 4: Mixed Waste  

Science Conference Proceedings (OSTI)

Mixed waste management has been a significant concern to nuclear utilities due to the lack of available treatment and disposal capacity. This volume of the Radwaste Desk Reference contains fundamental practical and regulatory information on the management of mixed low level waste. Because its information is based entirely on industry practice, the work can serve as an extensive "how-to" manual for both the newcomer and the experienced radwaste professional responsible for mixed waste.

1995-12-31T23:59:59.000Z

330

Addressing mixed waste in plutonium processing  

SciTech Connect

The overall goal is the minimization of all waste generated in actinide processing facilities. Current emphasis is directed toward reducing and managing mixed waste in plutonium processing facilities. More specifically, the focus is on prioritizing plutonium processing technologies for development that will address major problems in mixed waste management. A five step methodological approach to identify, analyze, solve, and initiate corrective action for mixed waste problems in plutonium processing facilities has been developed.

Christensen, D.C.; Sohn, C.L. (Los Alamos National Lab., NM (United States)); Reid, R.A. (New Mexico Univ., Albuquerque, NM (United States). Anderson Schools of Management)

1991-01-01T23:59:59.000Z

331

Behavior of Zircaloy Cladding in the Presence of Gallium  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy has established a dual-track approach to the disposition of plutonium arising from the dismantling of nuclear weapons. Both immobilization and reactor-based mixed-oxide (MOX) fuel technologies are being evaluated. The reactor-based MOX fuel option requires assessment of the potential impact of concentrations of gallium (on the order of 1 to 10 ppm), not present in conventional MOX fuel, on cladding material performance. An experimental program was designed to evaluate the performance of prototypic Zircaloy cladding materials against (1) liquid gallium, and (2) various concentrations of G~03. Three types of tests were performed: (1) corrosion, (2) liquid metal embrittlement, and (3) corrosion-mechanical. These tests were to determine corrosion mechanisms, thresholds for temperature and concentration of gallium that delineate behavioral regimes, and changes in the mechanical properties of Zircaloy. Results have generally been favorable for the use of weapons-grade (WG) MOX fhel. The Zircaloy cladding does react with gallium to form intermetallic compounds at >3000 C; however, this reaction is limited by the mass of gallium and is therefore not expected to be significant with a low level (parts per million) of gallium in the MOX fuel. Furthermore, no evidence for grain boundary penetration by gallium or liquid metal embrittlement was observed.

DiStefano, J.R.; King, J.F.; Manneschmidt, E.T.; Strizak, J.P.; Wilson, D.F.

1998-09-28T23:59:59.000Z

332

Mechanical Behavior of Melt Mixing Polypropylene Organoclay ...  

Science Conference Proceedings (OSTI)

To study the effect of the nanocomposite dispersion and morphology, another nanocomposite was prepared by melt mixing of polypropylene and a modified ...

333

Lanthanide doped strontium barium mixed halide scintillators  

DOE Patents (OSTI)

The present invention provides for a composition comprising an inorganic scintillator comprising a lanthanide-doped strontium barium mixed halide useful for detecting nuclear material.

Gundiah, Gautam; Bizarri, Gregory; Hanrahan, Stephen M; Bourret-Courchesne, Edith; Derenzo, Stephen E

2013-07-16T23:59:59.000Z

334

Two Row Mixed Integer Cuts Via Lifting?  

E-Print Network (OSTI)

Jun 22, 2008 ... the two-row mixed integer infinite-group problem), and to develop lifting ..... The next lemma analyzes the standard triangles with each side ...

335

Dry Barrier Mix in Reduction Cell Cathodes  

Science Conference Proceedings (OSTI)

Presentation Title, Dry Barrier Mix in Reduction Cell Cathodes ... successfully tested as a replacement for barrier bricks in several reduction cell technology types ...

336

INSTRUCTOR TECHNOLOGY USE: A MIXED METHODS INVESTIGATION.  

E-Print Network (OSTI)

??This mixed methods concurrent triangulation study was designed to examine instructional leaders’ descriptions of their experience with integrating technology into their teaching. Seminal studies from… (more)

Becking, Suzanne K

2011-01-01T23:59:59.000Z

337

ADVANCED MIXED WASTE TREATMENT PROJECT (AMWTP)  

NLE Websites -- All DOE Office Websites (Extended Search)

ADVANCED MIXED WASTE TREATMENT PROJECT Idaho Treatment Group, LLC (ITG) Contract No. DE-EM0001467 You are here: DOE-ID Home > Contracts, Financial Assistance & Solicitations >...

338

Mixed metal ?lms with switchable optical properties  

The electrochemical hydro-gen loading behavior of these mixed metal ?lms was similar ... Energy Ef?ciency and Renewable Energy, Of?ce of Building

339

Photoelectrochemical Hydrogen Production Using New Combinatorial Chemistry Derived Materials  

E-Print Network (OSTI)

red ox (6) where mox and mred are the mass of the oxygen carrier in fully oxidized and reduced state, respectively. The mass-based conversion of the oxygen carrier, , is defined as: = m mox (7) where m

340

Photo-oxidation catalysts  

DOE Patents (OSTI)

Photo-oxidation catalysts and methods for cleaning a metal-based catalyst are disclosed. An exemplary catalyst system implementing a photo-oxidation catalyst may comprise a metal-based catalyst, and a photo-oxidation catalyst for cleaning the metal-based catalyst in the presence of light. The exposure to light enables the photo-oxidation catalyst to substantially oxidize absorbed contaminants and reduce accumulation of the contaminants on the metal-based catalyst. Applications are also disclosed.

Pitts, J. Roland (Lakewood, CO); Liu, Ping (Irvine, CA); Smith, R. Davis (Golden, CO)

2009-07-14T23:59:59.000Z

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


341

Inference of ICF Implosion Core Mix using Experimental Data and Theoretical Mix Modeling  

Science Conference Proceedings (OSTI)

The mixing between fuel and shell materials in Inertial Confinement Fusion (ICF) implosion cores is a current topic of interest. The goal of this work was to design direct-drive ICF experiments which have varying levels of mix, and subsequently to extract information on mixing directly from the experimental data using spectroscopic techniques. The experimental design was accomplished using hydrodynamic simulations in conjunction with Haan's saturation model, which was used to predict the mix levels of candidate experimental configurations. These theoretical predictions were then compared to the mixing information which was extracted from the experimental data, and it was found that Haan's mix model performed well in predicting trends in the width of the mix layer. With these results, we have contributed to an assessment of the range of validity and predictive capability of the Haan saturation model, as well as increased our confidence in the methods used to extract mixing information from experimental data.

Welser-Sherrill, L; Haynes, D A; Mancini, R C; Cooley, J H; Tommasini, R; Golovkin, I E; Sherrill, M E; Haan, S W

2008-04-30T23:59:59.000Z

342

Inference of ICF implosion core mix using experimental data and theoretical mix modeling  

Science Conference Proceedings (OSTI)

The mixing between fuel and shell materials in Inertial Confinement Fusion (lCF) implosion cores is a current topic of interest. The goal of this work was to design direct-drive ICF experiments which have varying levels of mix, and subsequently to extract information on mixing directly from the experimental data using spectroscopic techniques. The experimental design was accomplished using hydrodynamic simulations in conjunction with Haan's saturation model, which was used to predict the mix levels of candidate experimental configurations. These theoretical predictions were then compared to the mixing information which was extracted from the experimental data, and it was found that Haan's mix model predicted trends in the width of the mix layer as a function of initial shell thickness. These results contribute to an assessment of the range of validity and predictive capability of the Haan saturation model, as well as increasing confidence in the methods used to extract mixing information from experimental data.

Sherrill, Leslie Welser [Los Alamos National Laboratory; Haynes, Donald A [Los Alamos National Laboratory; Cooley, James H [Los Alamos National Laboratory; Sherrill, Manolo E [Los Alamos National Laboratory; Mancini, Roberto C [UNR; Tommasini, Riccardo [LLNL; Golovkin, Igor E [PRISM COMP. SCIENCES; Haan, Steven W [LLNL

2009-01-01T23:59:59.000Z

343

Lidar Observations of Mixed Layer Dynamics: Tests of Parameterized Entrainment Models of Mixed Layer Growth Rate  

Science Conference Proceedings (OSTI)

Ground based lidar measurements of the atmospheric mixed layer depth, the entrainment zone depth and the wind speed and wind direction were used to test various parameterized entrainment models of mixed layer growth rate. Six case studies under ...

R. Boers; E. W. Eloranta; R. L. Coulter

1984-02-01T23:59:59.000Z

344

Iron-Phosphate Ceramics for Solidification of Mixed Low-Level Waste  

DOE Patents (OSTI)

A method of immobilizing mixed low-level waste is provided which uses low cost materials and has a relatively long hardening period. The method includes: forming a mixture of iron oxide powders having ratios, in mass %, of FeO: Fe{sub 2}O{sub 3}: Fe{sub 3}O{sub 4} equal to 25-40: 40-10: 35-50, or weighing a definite amount of magnitite powder. Metallurgical cinder can also be used as the source of iron oxides. A solution of the orthophosphoric acid, or a solution of the orthophosphoric acid and ferric oxide, is formed and a powder phase of low-level waste and the mixture of iron oxide powders or cinder (or magnetite powder) is also formed. The acid solution is mixed with the powder phase to form a slurry with the ratio of components (mass %) of waste: iron oxide powders or magnitite: acid solution = 30-60: 15-10: 55-30. The slurry is blended to form a homogeneous mixture which is cured at room temperature to form the final product.

Aloy, Albert S.; Kovarskaya, Elena N.; Koltsova, Tatiana I.; Macheret, Yevgeny; Medvedev, Pavel G.; Todd, Terry

1998-08-07T23:59:59.000Z

345

Iron-phosphate ceramics for solidification of mixed low-level waste  

DOE Patents (OSTI)

A method of immobilizing mixed low-level waste is provided which uses low cost materials and has a relatively long hardening period. The method includes: forming a mixture of iron oxide powders having ratios, in mass %, of FeO:Fe.sub.2 O.sub.3 :Fe.sub.3 O.sub.4 equal to 25-40:40-10:35-50, or weighing a definite amount of magnetite powder. Metallurgical cinder can also be used as the source of iron oxides. A solution of the orthophosphoric acid, or a solution of the orthophosphoric acid and ferric oxide, is formed and a powder phase of low-level waste and the mixture of iron oxide powders or cinder (or magnetite powder) is also formed. The acid solution is mixed with the powder phase to form a slurry with the ratio of components (mass %) of waste:iron oxide powders or magnetite:acid solution=30-60:15-10:55-30. The slurry is blended to form a homogeneous mixture which is cured at room temperature to form the final product.

Aloy, Albert S. (St. Petersburg, RU); Kovarskaya, Elena N. (St. Petersburg, RU); Koltsova, Tatiana I. (St. Petersburg, RU); Macheret, Yevgeny (Idaho Falls, ID); Medvedev, Pavel G. (Ozersk, RU); Todd, Terry (Aberdeen, ID)

2000-01-01T23:59:59.000Z

346

`Mixed' Jordan-Lie Superalgebra  

E-Print Network (OSTI)

An algebra A not encountered in either the usual algebraic varieties or supervarieties is introduced. A is a graded and deformed version of the quaternions, with structure similar to that of a Jordan-Lie superalgebra as defined by Okubo and Kamiya, but it is shown to be neither that of a purely associative Lie superalgebra, nor that of a purely antiassociative Jordan-Lie superalgebra. Rather, it exhibits a novel kind of associativity, here called `ordered graded associativity', that is somewhat `in between' pure associativity and pure antiassociativity. In addition to graded associativity, the generators of A obey graded commutation relations encountered in both the usual Lie superalgebras and in graded Jordan-Lie algebras. They also satisfy new graded Jacobi identities that combine characteristics of the Jacobis obeyed by the generators of ungraded Lie, graded Lie and graded Jordan-Lie algebras. Mainly due to these three features, A is called a `mixed' Jordan-Lie superalgebra. The present paper defines A and compares it with the Jordan-Lie superalgebra defined by Okubo and Kamiya.

Ioannis Raptis

2001-10-25T23:59:59.000Z

347

On entanglement in neutrino mixing and oscillations  

E-Print Network (OSTI)

We report on recent results about entanglement in the context of particle mixing and oscillations. We study in detail single-particle entanglement arising in two-flavor neutrino mixing. The analysis is performed first in the context of Quantum Mechanics, and then for the case of Quantum Field Theory.

Blasone, M; De Siena, S; Illuminati, F

2010-01-01T23:59:59.000Z

348

Algorithmic parameterization of mixed treatment comparisons  

Science Conference Proceedings (OSTI)

Mixed Treatment Comparisons (MTCs) enable the simultaneous meta-analysis (data pooling) of networks of clinical trials comparing ¿2 alternative treatments. Inconsistency models are critical in MTC to assess the overall consistency between evidence sources. ... Keywords: Algorithm, Evidence consistency, Indirect comparisons, Mixed treatment comparison, Model generation, Network meta-analysis

Gert Valkenhoef; Tommi Tervonen; Bert Brock; Hans Hillege

2012-09-01T23:59:59.000Z

349

An algorithm for underdetermined mixing matrix estimation  

Science Conference Proceedings (OSTI)

This paper considers the problem of mixing matrix estimation in underdetermined blind source separation (UBSS). We propose a simple and effective detection algorithm which detects the time-frequency (TF) points occupied by only a single source for each ... Keywords: Mixing matrix estimation, Robust clustering, Sparse component analysis, Underdetermined blind source separation

Tianbao Dong; Yingke Lei; Jingshu Yang

2013-03-01T23:59:59.000Z

350

Milestone M4900: Simulant Mixing Analytical Results  

SciTech Connect

This report addresses Milestone M4900, ''Simulant Mixing Sample Analysis Results,'' and contains the data generated during the ''Mixing of Process Heels, Process Solutions, and Recycle Streams: Small-Scale Simulant'' task. The Task Technical and Quality Assurance Plan for this task is BNF-003-98-0079A. A report with a narrative description and discussion of the data will be issued separately.

Kaplan, D.I.

2001-07-26T23:59:59.000Z

351

8, 1175511819, 2008 mixed-phase Arctic  

E-Print Network (OSTI)

, process of ice phase initiation due to freezing of25 supercooled water in both saturatedACPD 8, 11755­11819, 2008 Simulating mixed-phase Arctic stratus clouds I. Sednev et al. Title Page.0 License. Atmospheric Chemistry and Physics Discussions Simulating mixed-phase Arctic stratus clouds

Paris-Sud XI, Université de

352

Contaminated Variance-Mean mixing model  

Science Conference Proceedings (OSTI)

The Generalised Normal Variance-Mean (GNVM) model in which the mixing random variable is Gamma distributed is considered. This model generalises the popular Variance-Gamma (VG) distribution. This GNVM model can be interpreted as the addition of noise ... Keywords: DIC, JAGS, Maximum likelihood estimation, Mixing representation, Normal Variance-Mean distribution, Variance-Gamma distribution

Thomas Fung, Joanna J. J. Wang, Eugene Seneta

2013-11-01T23:59:59.000Z

353

Thin films of mixed metal compounds  

DOE Patents (OSTI)

A compositionally uniform thin film of a mixed metal compound is formed by simultaneously evaporating a first metal compound and a second metal compound from independent sources. The mean free path between the vapor particles is reduced by a gas and the mixed vapors are deposited uniformly. The invention finds particular utility in forming thin film heterojunction solar cells.

Mickelsen, Reid A. (Bellevue, WA); Chen, Wen S. (Seattle, WA)

1985-01-01T23:59:59.000Z

354

On entanglement in neutrino mixing and oscillations  

E-Print Network (OSTI)

We report on recent results about entanglement in the context of particle mixing and oscillations. We study in detail single-particle entanglement arising in two-flavor neutrino mixing. The analysis is performed first in the context of Quantum Mechanics, and then for the case of Quantum Field Theory.

M. Blasone; F. Dell'Anno; S. De Siena; F. Illuminati

2010-03-29T23:59:59.000Z

355

Mixed-Technology System-Level Simulation  

Science Conference Proceedings (OSTI)

This paper describes a computationally efficient method to simulate mixed-domain systems under the requirements of a system-level framework. The approach is the combined use of Modified Nodal Analysis (MNA) for the representation of a mixed-technology ... Keywords: MEM simulation, microsystem modeling and simulation, modified nodal analysis (MNA), optical MEM CAD tool, optoelectronic simulation, piecewise linear simulation (PWL)

J. A. Martinez; T. P. Kurzweg; S. P. Levitan; P. J. Marchand; D. M. Chiarulli

2001-10-01T23:59:59.000Z

356

Multifunctional Oxides: Multifunctional Oxides: Synthesis and ...  

Science Conference Proceedings (OSTI)

Using Ultrafast Optical Spectroscopy to Explore Magneoelectric Coupling in Multiferroic Oxide Heterostructures: Y-M Sheu1; S. Trugman1; L Yan1; C-P Chuu 1; ...

357

Asphalt Oxidation Kinetics and Pavement Oxidation Modeling  

E-Print Network (OSTI)

Most paved roads in the United States are surfaced with asphalt. These asphalt pavements suffer from fatigue cracking and thermal cracking, aggravated by the oxidation and hardening of asphalt. This negative impact of asphalt oxidation on pavement performance has not been considered adequately in pavement design. Part of the reason is that the process of asphalt oxidation in pavement is not well understood. This work focused on understanding the asphalt oxidation kinetics and on developing pavement oxidation model that predicts asphalt oxidation and hardening in pavement under environmental conditions. A number of asphalts were studied in laboratory condition. Based on kinetics data, a fast-rate ? constant-rate asphalt oxidation kinetics model was developed to describe the early nonlinear fast-rate aging period and the later constant-rate period of asphalt oxidation. Furthermore, reaction kinetics parameters for the fast-rate and constant-rate reactions were empirically correlated, leading to a simplified model. And the experimental effort and time to obtain these kinetics parameters were significantly reduced. Furthermore, to investigate the mechanism of asphalt oxidation, two antioxidants were studied on their effectiveness. Asphalt oxidation was not significantly affected. It was found that evaluation of antioxidant effectiveness based on viscosity only is not reliable. The asphalt oxidation kinetics model was incorporated into the pavement oxidation model that predicts asphalt oxidation in pavement. The pavement oxidation model mimics the oxidation process of asphalt in real mixture at pavement temperatures. A new parameter, diffusion depth, defined the oxygen diffusion region in the mastic. A field calibration factor accounted for the factors not considered in the model such as the effect of small aggregate particles on oxygen diffusion. Carbonyl area and viscosity of binders recovered from field cores of three pavements in Texas were measured and were used for model calibration and validation. Results demonstrated that the proposed model estimates carbonyl growth over time in pavement, layer-by-layer, quite well. Finally, this work can be useful for incorporating asphalt oxidation into a pavement design method that can predict pavement performance with time and for making strategic decisions such as optimal time for maintenance treatments.

Jin, Xin

2012-05-01T23:59:59.000Z

358

Argonne CNM Highlight: Mixing up surface properties  

NLE Websites -- All DOE Office Websites (Extended Search)

Mixing up surface properties Mixing up surface properties Mixed self-assembled monolayers This image was selected for the "Back Scatter" back cover feature of Physics Today, Vol. 62, No. 2 (Feb. 2009) Mixed self-assembled monolayers (SAMs) offer the intriguing possibility of tailoring wetting properties, surface energy, and other interfacial characteristics by combining suitable molecular constituents. This atomic force micrograph, 800 nm tall, shows the onset of nanoscopic phase separation in an ideally mixed two-component SAM. The small domains of each material can be distinguished with topographic contrast because of their 2-Å length difference. The larger domains are due to atomic terracing of the underlying gold surface. Seth Darling (CNM) and Steven Sibener (University of Chicago) are working

359

Fuel Mix Disclosure | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Fuel Mix Disclosure Fuel Mix Disclosure Fuel Mix Disclosure < Back Eligibility Utility Program Info State Delaware Program Type Generation Disclosure Provider Delaware Public Service Commission Delaware's 1999 restructuring law (HB 10) authorized the state Public Service Commission (PSC) to develop environmental disclosure requirements and consumer protection standards for green power marketing. The PSC's rules require all electric suppliers to disclose to the commission aggregate proportions of fuel resource mix for the electricity supplied to customers in Delaware for each quarter. In addition, electric suppliers must disclose their fuel resource mix to retail electric customers annually via bill inserts and "each other quarter' on the supplier's web site or by customer request. A standard label is not required; however, the reports

360

Thin films of mixed metal compounds  

DOE Patents (OSTI)

Disclosed is a thin film heterojunction solar cell, said heterojunction comprising a p-type I-III-IV[sub 2] chalcopyrite substrate and an overlying layer of an n-type ternary mixed metal compound wherein said ternary mixed metal compound is applied to said substrate by introducing the vapor of a first metal compound to a vessel containing said substrate from a first vapor source while simultaneously introducing a vapor of a second metal compound from a second vapor source of said vessel, said first and second metals comprising the metal components of said mixed metal compound; independently controlling the vaporization rate of said first and second vapor sources; reducing the mean free path between vapor particles in said vessel, said gas being present in an amount sufficient to induce homogeneity of said vapor mixture; and depositing said mixed metal compound on said substrate in the form of a uniform composition polycrystalline mixed metal compound. 5 figs.

Mickelsen, R.A.; Chen, W.S.

1985-06-11T23:59:59.000Z

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


361

Mixed waste characterization, treatment & disposal focus area  

Science Conference Proceedings (OSTI)

The mission of the Mixed Waste Characterization, Treatment, and Disposal Focus Area (referred to as the Mixed Waste Focus Area or MWFA) is to provide treatment systems capable of treating DOE`s mixed waste in partnership with users, and with continual participation of stakeholders, tribal governments, and regulators. The MWFA deals with the problem of eliminating mixed waste from current and future storage in the DOE complex. Mixed waste is waste that contains both hazardous chemical components, subject to the requirements of the Resource Conservation and Recovery Act (RCRA), and radioactive components, subject to the requirements of the Atomic Energy Act. The radioactive components include transuranic (TRU) and low-level waste (LLW). TRU waste primarily comes from the reprocessing of spent fuel and the use of plutonium in the fabrication of nuclear weapons. LLW includes radioactive waste other than uranium mill tailings, TRU, and high-level waste, including spent fuel.

NONE

1996-08-01T23:59:59.000Z

362

Robertsons Ready Mix | Open Energy Information  

Open Energy Info (EERE)

Robertsons Ready Mix Robertsons Ready Mix Jump to: navigation, search Name Robertsons Ready Mix Facility Robertsons Ready Mix Sector Wind energy Facility Type Community Wind Facility Status In Service Owner Foundation Windpower Developer Foundation Windpower Energy Purchaser Robertsons Ready Mix Location Cabazon CA Coordinates 33.915842°, -116.81325° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":33.915842,"lon":-116.81325,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

363

Lignite slime as activator in production of oxidized asphalts  

Science Conference Proceedings (OSTI)

The possibility of activation of the oxidation of straight-run resids to asphalts by the addition of lignite slimes obtained in the liquefaction of coals of the Kansk-Achinsk basin was studied on the basis of a hypothesis formulated with due regard for the principles of physicochemical mechanics of petroleum disperse systems. A reduction of the air bubble size in the oxidizing vessel should lead to an increase in the total surface of oxidation and hence to a shortening of the time required for oxidation of the feed. A straight-run vacuum resid from mixed West Siberian and Ukhta crudes was used. The resid was oxidized with and without the addition of slime.

Gureev, A.A.; Gorlov, E.G.; Leont'eva, O.B.; Zotova, O.V.

1988-03-01T23:59:59.000Z

364

SRS - Programs - Nonproliferation Programs  

NLE Websites -- All DOE Office Websites (Extended Search)

3/2012 3/2012 SEARCH GO spacer SRS Home Nonproliferation Programs In the crucial field of nuclear nonproliferation, SRS employee contributions helped to advance all three of the planned plutonium disposition facilities at the Savannah River Site: the Pit Disassembly and Conversion Facility (PDCF); Waste Solidification Building (WSB); and the Mixed Oxide (MOX) Fuel Fabrication Facility. A $345 million project, the WSB will process liquid waste from the MOX facility. After material is processed at the WSB, transuranic waste will be packaged and sent to the Waste Isolation Pilot Plant in New Mexico, and low-level waste will be packaged and sent to onsite or commercial off-site low-level waste disposal facilities. The mixed oxide fuel fabrication facility will be a major component in the United States' program to dispose of excess weapons grade plutonium.

365

CX-007663: Categorical Exclusion Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

63: Categorical Exclusion Determination 63: Categorical Exclusion Determination CX-007663: Categorical Exclusion Determination Construction of a Connector Road Between the Construction Administration Complex (CAC) and the Mixed Oxide Administration Complex (MAC) Parking Lots CX(s) Applied: B1.13 Date: 11/21/2011 Location(s): South Carolina Offices(s): Savannah River Operations Office Mixed Oxide (MOX) Services proposes the construction of a road connecting the Construction Administration Complex (CAC) and the MOX Administration Complex (MAC) parking lots. The approximate dimensions of the proposed connector road are 160 feet in length and 17 feet in width, with a construction limits footprint of 0.4 acre. CX-007663.pdf More Documents & Publications CX-010852: Categorical Exclusion Determination

366

CX-007663: Categorical Exclusion Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

7663: Categorical Exclusion Determination 7663: Categorical Exclusion Determination CX-007663: Categorical Exclusion Determination Construction of a Connector Road Between the Construction Administration Complex (CAC) and the Mixed Oxide Administration Complex (MAC) Parking Lots CX(s) Applied: B1.13 Date: 11/21/2011 Location(s): South Carolina Offices(s): Savannah River Operations Office Mixed Oxide (MOX) Services proposes the construction of a road connecting the Construction Administration Complex (CAC) and the MOX Administration Complex (MAC) parking lots. The approximate dimensions of the proposed connector road are 160 feet in length and 17 feet in width, with a construction limits footprint of 0.4 acre. CX-007663.pdf More Documents & Publications CX-010852: Categorical Exclusion Determination

367

Chemical evolution with radial mixing  

E-Print Network (OSTI)

Models of the chemical evolution of our Galaxy are extended to include radial migration of stars and flow of gas through the disc. The models track the production of both iron and alpha elements. A model is chosen that provides an excellent fit to the metallicity distribution of stars in the Geneva-Copenhagen survey (GCS) of the solar neighbourhood, and a good fit to the local Hess diagram. The model provides a good fit to the distribution of GCS stars in the age-metallicity plane although this plane was not used in the fitting process. Although this model's star-formation rate is monotonic declining, its disc naturally splits into an alpha-enhanced thick disc and a normal thin disc. In particular the model's distribution of stars in the ([O/Fe],[Fe/H]) plane resembles that of Galactic stars in displaying a ridge line for each disc. The thin-disc's ridge line is entirely due to stellar migration and there is the characteristic variation of stellar angular momentum along it that has been noted by Haywood in survey data. Radial mixing of stellar populations with high sigma_z from inner regions of the disc to the solar neighbourhood provides a natural explanation of why measurements yield a steeper increase of sigma_z with age than predicted by theory. The metallicity gradient in the ISM is predicted to be steeper than in earlier models, but appears to be in good agreement with data for both our Galaxy and external galaxies. The models are inconsistent with a cutoff in the star-formation rate at low gas surface densities. The absolute magnitude of the disc is given as a function of time in several photometric bands, and radial colour profiles are plotted for representative times.

Ralph Schoenrich; James Binney

2008-09-17T23:59:59.000Z

368

Physics calculations for mixed PuO{sub 2}-UO{sub 2} NPR loadings  

SciTech Connect

At the request of NRD (NPR Physics Subsection) a study was initiated to determine the physics characteristics of various plutonium-uranium composites as fuel for the NPR. From this study, the PuO{sub 2}-UO{sub 2} fuel system was selected to receive major attention. The effect of adding a burnable poison, B-10, in intimate contact with the mixed oxide fuel was also is to be considered. The present report summarizes the results of these investigations.

Bennett, C.L.

1964-06-30T23:59:59.000Z

369

Method for stabilizing low-level mixed wastes at room temperature  

DOE Patents (OSTI)

A method to stabilize solid and liquid waste at room temperature is provided comprising combining solid waste with a starter oxide to obtain a powder, contacting the powder with an acid solution to create a slurry, said acid solution containing the liquid waste, shaping the now-mixed slurry into a predetermined form, and allowing the now-formed slurry to set. The invention also provides for a method to encapsulate and stabilize waste containing cesium comprising combining the waste with Zr(OH).sub.4 to create a solid-phase mixture, mixing phosphoric acid with the solid-phase mixture to create a slurry, subjecting the slurry to pressure; and allowing the now pressurized slurry to set. Lastly, the invention provides for a method to stabilize liquid waste, comprising supplying a powder containing magnesium, sodium and phosphate in predetermined proportions, mixing said powder with the liquid waste, such as tritium, and allowing the resulting slurry to set.

Wagh, Arun S. (Joliet, IL); Singh, Dileep (Westmont, IL)

1997-01-01T23:59:59.000Z

370

Method for stabilizing low-level mixed wastes at room temperature  

DOE Patents (OSTI)

A method to stabilize solid and liquid waste at room temperature is provided comprising combining solid waste with a starter oxide to obtain a powder, contacting the powder with an acid solution to create a slurry, said acid solution containing the liquid waste, shaping the now-mixed slurry into a predetermined form, and allowing the now-formed slurry to set. The invention also provides for a method to encapsulate and stabilize waste containing cesium comprising combining the waste with Zr(OH){sub 4} to create a solid-phase mixture, mixing phosphoric acid with the solid-phase mixture to create a slurry, subjecting the slurry to pressure; and allowing the now pressurized slurry to set. Lastly, the invention provides for a method to stabilize liquid waste, comprising supplying a powder containing magnesium, sodium and phosphate in predetermined proportions, mixing said powder with the liquid waste, such as tritium, and allowing the resulting slurry to set. 4 figs.

Wagh, A.S.; Singh, D.

1997-07-08T23:59:59.000Z

371

Microsoft Word - Poster Abstract_2010_GATech_Mixed Ionic-Electronic Conductors.docx  

NLE Websites -- All DOE Office Websites (Extended Search)

Investigation of Oxygen Reduction Activity on Mixed Ionic-Electronic Conductors for Investigation of Oxygen Reduction Activity on Mixed Ionic-Electronic Conductors for SOFC Cathodes Matthew E. Lynch, Lei Yang, Meilin Liu Center for Innovative Fuel Cell and Battery Technologies School of Materials Science and Engineering Georgia Institute of Technology 771 Ferst Dr., Atlanta, GA 30332-0245 Telephone: 404-894-6114 Email: meilin.liu@mse.gatech.edu Porous cathodes are of primary importance to the electrochemical operation of a solid oxide fuel cell (SOFC). The compound La 1-x Sr x Co 1-y Fe y O 3-δ (LSCF) is a candidate material for the cathode, and shows good mixed ionic-electronic conductivity as well as good activity toward the oxygen reduction

372

Mixed Waste Integrated Program: A technology assessment for mercury-containing mixed wastes  

SciTech Connect

The treatment of mixed wastes must meet US Environmental Protection Agency (EPA) standards for chemically hazardous species and also must provide adequate control of the radioactive species. The US Department of Energy (DOE) Office of Technology Development established the Mixed Waste Integrated Program (MWIP) to develop mixed-waste treatment technology in support of the Mixed Low-Level Waste Program. Many DOE mixed-waste streams contain mercury. This report is an assessment of current state-of-the-art technologies for mercury separations from solids, liquids, and gases. A total of 19 technologies were assessed. This project is funded through the Chemical-Physical Technology Support Group of the MWIP.

Perona, J.J.; Brown, C.H.

1993-03-01T23:59:59.000Z

373

Porous desulfurization sorbent pellets containing a reactive metal oxide and an inert zirconium compound  

DOE Patents (OSTI)

Sorbent pellets for removing hydrogen sulfide from coal gas are prepared by combining a reactive oxide, in particular zinc oxide, with a zirconium compound such as an oxide, silicate, or aluminate of zirconium, and an inorganic binder and pelletizing and calcining the mixture. Alternately, the zinc oxide may be replaced by copper oxide or a combination of copper, molybdenum, and manganese oxides. The pellet components may be mixed in dry form, moistened to produce a paste, and converted to pellets by forming an aqueous slurry of the components and spray drying the slurry, or the reactive oxide may be formed on existing zirconium-containing catalyst-carrier pellets by infusing a solution of a salt of the active metal onto the existing pellets and firing at a high temperature to produce the oxide. Pellets made according to this invention show a high reactivity with hydrogen sulfide and durability such as to be useful over repeated cycles of sorption and regeneration.

Gardner, Todd H.; Gasper-Galvin, Lee D.

1996-12-01T23:59:59.000Z

374

Interactions of Zircaloy cladding with gallium: 1998 midyear status  

Science Conference Proceedings (OSTI)

A program has been implemented to evaluate the effect of gallium in mixed-oxide (MOX) fuel derived from weapons-grade (WG) plutonium on Zircaloy cladding performance. The objective is to demonstrate that low levels of gallium will not compromise the performance of the MOX fuel system in a light-water reactor. The graded, four-phase experimental program was designed to evaluate the performance of prototypic Zircaloy cladding materials against (1) liquid gallium (Phase 1), (2) various concentrations of Ga{sub 2}O{sub 3} (Phase 2), (3) centrally heated surrogate fuel pellets with expected levels of gallium (Phase 3), and (4) centrally heated prototypic MOX fuel pellets (Phase 4). This status report describes the results of a series of tests for Phases 1 and 2. Three types of tests are being performed: (1) corrosion, (2) liquid metal embrittlement, and (3) corrosion-mechanical. These tests will determine corrosion mechanisms, thresholds for temperature and concentration of gallium that may delineate behavioral regimes, and changes in the mechanical properties of Zircaloy. Initial results have generally been favorable for the use of WG-MOX fuel. The MOX fuel cladding, Zircaloy, does react with gallium to form intermetallic compounds at {ge}300 C; however, this reaction is limited by the mass of gallium and is therefore not expected to be significant with a low level (parts per million) of gallium in the MOX fuel. Although continued migration of gallium into the initially formed intermetallic compound can result in large stresses that may lead to distortion, this was shown to be extremely unlikely because of the low mass of gallium or gallium oxide present and expected clad temperatures below 400 C. Furthermore, no evidence for grain boundary penetration by gallium has been observed.

Wilson, D.F.; DiStefano, J.R.; Strizak, J.P.; King, J.F.; Manneschmidt, E.T.

1998-06-01T23:59:59.000Z

375

Interactions of zircaloy cladding with gallium -- 1997 status  

SciTech Connect

A four phase program has been implemented to evaluate the effect of gallium in mixed oxide (MOX) fuel derived from weapons grade (WG) plutonium on Zircaloy cladding performance. The objective is to demonstrate that low levels of gallium will not compromise the performance of the MOX fuel system in LWR. This graded, four phase experimental program will evaluate the performance of prototypic Zircaloy cladding materials against: (1) liquid gallium (Phase 1), (2) various concentrations of Ga{sub 2}O{sub 3} (Phase 2), (3) centrally heated surrogate fuel pellets with expected levels of gallium (Phase 3), and (4) centrally heated prototypic MOX fuel pellets (Phase 4). This status report describes the results of an initial series of tests for phases 1 and 2. Three types of tests are being performed: (1) corrosion, (2) liquid metal embrittlement (LME), and (3) corrosion mechanical. These tests are designed to determine the corrosion mechanisms, thresholds for temperature and concentration of gallium that may delineate behavioral regimes, and changes in mechanical properties of Zircaloy. Initial results have generally been favorable for the use of WG-MOX fuel. The MOX fuel cladding, Zircaloy, does react with gallium to form intermetallic compounds at {ge} 300 C; however, this reaction is limited by the mass of gallium and is therefore not expected to be significant with a low level (in parts per million) of gallium in the MOX fuel. While continued migration of gallium into the initially formed intermetallic compound results in large stresses that can lead to distortion, this is also highly unlikely because of the low mass of gallium or gallium oxide present and expected clad temperatures below 400 C. Furthermore, no evidence for grain boundary penetration by gallium has been observed.

Wilson, D.F.; DiStefano, J.R.; King, J.F.; Manneschmidt, E.T.; Strizak, J.P.

1997-11-01T23:59:59.000Z

376

Fast Mix Table Construction for Material Discretization  

Science Conference Proceedings (OSTI)

An effective hybrid Monte Carlo--deterministic implementation typically requires the approximation of a continuous geometry description with a discretized piecewise-constant material field. The inherent geometry discretization error can be reduced somewhat by using material mixing, where multiple materials inside a discrete mesh voxel are homogenized. Material mixing requires the construction of a ``mix table,'' which stores the volume fractions in every mixture so that multiple voxels with similar compositions can reference the same mixture. Mix table construction is a potentially expensive serial operation for large problems with many materials and voxels. We formulate an efficient algorithm to construct a sparse mix table in $O(\\text{number of voxels}\\times \\log \\text{number of mixtures})$ time. The new algorithm is implemented in ADVANTG and used to discretize continuous geometries onto a structured Cartesian grid. When applied to an end-of-life MCNP model of the High Flux Isotope Reactor with 270 distinct materials, the new method improves the material mixing time by a factor of 100 compared to a naive mix table implementation.

Johnson, Seth R [ORNL

2013-01-01T23:59:59.000Z

377

CHAPTER 4 (Addendum re Corrosion Kinetics) Corrosion Kinetics, WTE Emissions and the Effects of HCl and SO2 to Corrosion  

E-Print Network (OSTI)

: ( )( ) ( )soxoxcon P RT D MZK = (65b) where: Mox = the molar mass of the oxide ox = density of the oxide 4

Columbia University

378

Depleted uranium valuation  

SciTech Connect

The following uses for depleted uranium were examined to determine its value: a substitute for lead in shielding applications, feed material in gaseous diffusion enrichment facilities, feed material for an advanced enrichment concept, Mixed Oxide (MOx) diluent and blanket material in LMFBRs, and fertile material in LMFBR systems. A range of depleted uranium values was calculated for each of these applications. The sensitivity of these values to analysis assumptions is discussed. 9 tables.

Lewallen, M.A.; White, M.K.; Jenquin, U.P.

1979-04-01T23:59:59.000Z

379

Mixed Waste Focus Area program management plan  

SciTech Connect

This plan describes the program management principles and functions to be implemented in the Mixed Waste Focus Area (MWFA). The mission of the MWFA is to provide acceptable technologies that enable implementation of mixed waste treatment systems developed in partnership with end-users, stakeholders, tribal governments and regulators. The MWFA will develop, demonstrate and deliver implementable technologies for treatment of mixed waste within the DOE Complex. Treatment refers to all post waste-generation activities including sampling and analysis, characterization, storage, processing, packaging, transportation and disposal.

Beitel, G.A.

1996-10-01T23:59:59.000Z

380

Mixed Conduction in Rare-Earth Phosphates  

E-Print Network (OSTI)

5   A  comparison  of  the  PEM,  SOFC,  and  PCFC  fuel  solid   oxide   fuel   cells   (SOFC).    The  electrolyte  immobilized)   OH -­?   MCFC   SOFC   Molten   Ceramic  

Ray, Hannah Leung

2012-01-01T23:59:59.000Z

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


381

Production of Dry Air by Isentropic Mixing  

Science Conference Proceedings (OSTI)

The authors have explored the factors governing upper-tropospheric relative humidity with a simple model based on isentropic mixing and condensation. Our analysis has focused on the Northern Hemisphere winter season and on the 315-K (dry) ...

H. Yang; R. T. Pierrehumbert

1994-12-01T23:59:59.000Z

382

Mixing Processes within the Polar Night Jet  

Science Conference Proceedings (OSTI)

Lagrangian material line simulations are performed using U.K. Meteorological Office assimilated winds and temperatures to examine mixing processes in the middle- and lower-stratospheric polar night jet during the 1992 Southern Hemisphere spring ...

R. Bradley Pierce; T. Duncan Fairlie; William L. Grose; Richard Swinbank; Alan O'Neill

1994-10-01T23:59:59.000Z

383

Multipartite entangled states in particle mixing  

E-Print Network (OSTI)

In the physics of flavor mixing, the flavor states are expressed as superpositions of mass eigenstates. By using the occupation number to define a multiqubit space, the flavor states can be interpreted as multipartite mode-entangled states. By exploiting a suitable global measure of entanglement, based on the entropies related to all possible bipartitions of the system, we analyze the correlation properties of such states in the instances of three- and four-flavor mixing. Depending on the mixing parameters, and, in particular, on the values taken by the free phases, responsible for the CP-violation, entanglement concentrates in certain bipartitions. We quantify in detail the amount and the distribution of entanglement in the physically relevant cases of flavor mixing in quark and neutrino systems.

Blasone, M; De Siena, S; Di Mauro, M; Illuminati, F

2007-01-01T23:59:59.000Z

384

Abyssal Mixing in the Brazil Basin  

Science Conference Proceedings (OSTI)

One of the major objectives of the Deep Basin Experiment, a component of the World Ocean Circulation Experiment, was to quantify the intensity and spatial distribution of deep vertical mixing within the Brazil Basin. In this study, basin-averaged ...

Michele Y. Morris; Melinda M. Hall; Louis C. St. Laurent; Nelson G. Hogg

2001-11-01T23:59:59.000Z

385

Ocean Boundary Mixing during Ekman Layer Arrest  

Science Conference Proceedings (OSTI)

As a water parcel comes into contact with an ocean boundary, energy is dissipated within the boundary layer with some fraction directed into vertical mixing. In a stratified flow this increases the potential energy associated with the density ...

Scott A. Condie

1999-12-01T23:59:59.000Z

386

The properties of mixed reality boundaries  

Science Conference Proceedings (OSTI)

Mixed reality boundaries establish transparent windows between physical and virtual spaces. We introduce a set of properties that allow such boundaries to be configured to support different styles of co-operative activity. These properties are grouped ...

Boriana Koleva; Steve Benford; Chris Greenhalgh

1999-09-01T23:59:59.000Z

387

Relating River Plume Structure to Vertical Mixing  

Science Conference Proceedings (OSTI)

The structure of a river plume is related to the vertical mixing using an isohaline-based coordinate system. Salinity coordinates offer the advantage of translating with the plume as it moves or expanding as the plume grows. This coordinate ...

Robert D. Hetland

2005-09-01T23:59:59.000Z

388

Mixed mode execution with context threading  

Science Conference Proceedings (OSTI)

Interpreters are widely used to implement portable language runtime environments. Programs written in these languages may benefit from performance beyond that obtainable by optimizing interpretation alone. A modern high-performance mixed-mode virtual ...

Mathew Zaleski; Marc Berndl; Angela Demke Brown

2005-10-01T23:59:59.000Z

389

Mixing and Spreading of the Mediterranean Outflow  

Science Conference Proceedings (OSTI)

Hydrographic and current profiler data taken during the 1988 Gulf of Cadiz Expedition have been analyzed to diagnose the mixing, spreading, and descent of the Mediterranean outflow. The ?–S properties and the thickness and width of the outflow ...

Molly O’Neil Baringer; James F. Price

1997-08-01T23:59:59.000Z

390

Determining Velocities and Mixing Coefficients from Tracers  

Science Conference Proceedings (OSTI)

The effort to determine oceanic velocities from tracer distributions relies on a knowledge of the effects of mixing. However, the macroscopic diffusion coefficient, K, is generally not known and must be calculated along with the velocity. The ...

Jae Hak Lee; George Veronis

1989-04-01T23:59:59.000Z

391

The Mixed-Phase Arctic Cloud Experiment  

Science Conference Proceedings (OSTI)

The Mixed-Phase Arctic Cloud Experiment (M-PACE) was conducted from 27 September through 22 October 2004 over the Department of Energy's Atmospheric Radiation Measurement (ARM) Climate Research Facility (ACRF) on the North Slope of Alaska. The ...

J. Verlinde; J. Y. Harrington; V. T. Yannuzzi; A. Avramov; S. Greenberg; S. J. Richardson; C. P. Bahrmann; G. M. McFarquhar; G. Zhang; N. Johnson; M. R. Poellot; J. H. Mather; D. D. Turner; E. W. Eloranta; D. C. Tobin; R. Holz; B. D. Zak; M. D. Ivey; A. J. Prenni; P. J. DeMott; J. S. Daniel; G. L. Kok; K. Sassen; D. Spangenberg; P. Minnis; T. P. Tooman; M. Shupe; A. J. Heymsfield; R. Schofield

2007-02-01T23:59:59.000Z

392

Particle mixing, flavor condensate and dark energy  

E-Print Network (OSTI)

The mixing of neutrinos and quarks generate a vacuum condensate that, at the present epoch, behaves as a cosmological constant. The value of the dark energy is constrained today by the very small breaking of the Lorentz invariance.

Massimo Blasone; Antonio Capolupo; Giuseppe Vitiello

2009-12-08T23:59:59.000Z

393

Hydrogen transport, mixing, and combustion studies  

DOE Green Energy (OSTI)

The transport, mixing, and burning of hydrogen inside containments are receiving a great deal of attention. We present detailed models describing this important phenomena and provide several example calculations to show the versatility and accuracy of the methods.

Travis, J.R.

1984-01-01T23:59:59.000Z

394

Turbulent Mixing in Stably Stratified Shear Flows  

Science Conference Proceedings (OSTI)

Vertical mixing of momentum and heat is investigated in turbulent stratified shear flows. It is assumed that the flow has uniform shear and stratification with homogeneous turbulence and that an equilibrium is reached between kinetic and ...

U. Schumann; T. Gerz

1995-01-01T23:59:59.000Z

395

Mixed Layer Deepening Due to Langmuir Circulation  

Science Conference Proceedings (OSTI)

The interaction between wind-driven Langmuir circulation and preexisting stratification is examined in order to elucidate its role in the deepening of the ocean surface mixed layer. For linear stratification, a numerical model suggests that ...

Ming Li; Chris Garrett

1997-01-01T23:59:59.000Z

396

Treatment of Mixed Incinerable Waste, IG-0588  

Energy.gov (U.S. Department of Energy (DOE))

We found the Department of Energy (Department) was not treating its mixed incinerable solid waste expeditiously or cost-effectively. Specifically, the Department: • Did not fully utilize the Toxic...

397

Turbulent Mixing at the Pacific Subtropical Front  

Science Conference Proceedings (OSTI)

Some advection of water across the North Pacific subtropical front occurs by the subduction of surface mixed layers from the north side of the front underneath surface waters on the south side. Cross-frontal advection in the thermocline is ...

Rolf G. Lueck

1988-12-01T23:59:59.000Z

398

Solar neutrinos with three flavor mixings  

SciTech Connect

The recent{sup 71}Ga solar neutrino observation is combined with the {sup 37}Cl and Kamiokande-II observations in an analysis for neutrino masses and mixings. The allowed parameter region is found for matter enhanced mixings among all three neutrino flavors. Distortions of the solar neutrino spectrum unique to three flavors are possible and may be observed in continuing and next generation experiments.

Harley, D.; Pantaleone, J. [Washington Univ., Seattle, WA (United States). Inst. for Nuclear Theory; Kuo, T.K. [Purdue Univ., Lafayette, IN (United States). Dept. of Physics

1992-12-31T23:59:59.000Z

399

Solar neutrinos with three flavor mixings  

SciTech Connect

The recent[sup 71]Ga solar neutrino observation is combined with the [sup 37]Cl and Kamiokande-II observations in an analysis for neutrino masses and mixings. The allowed parameter region is found for matter enhanced mixings among all three neutrino flavors. Distortions of the solar neutrino spectrum unique to three flavors are possible and may be observed in continuing and next generation experiments.

Harley, D.; Pantaleone, J. (Washington Univ., Seattle, WA (United States). Inst. for Nuclear Theory); Kuo, T.K. (Purdue Univ., Lafayette, IN (United States). Dept. of Physics)

1992-01-01T23:59:59.000Z

400

Turbulent Mixing with Chemical Reaction in the Planetary Boundary Layer  

Science Conference Proceedings (OSTI)

Detailed statistics of the fluctuating concentration field produced by large-eddy simulations (LES) of the chemically reactive mixing of two species in a convectively driven mixed layer are presented. The effect of the turbulent mixing on the ...

R. I. Sykes; S. F. Parker; D. S. Henn; W. S. Lewellen

1994-07-01T23:59:59.000Z

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


401

Neutrino Mass and Mixing with Discrete Symmetry  

E-Print Network (OSTI)

This is a review article about neutrino mass and mixing and flavour model building strategies based on discrete family symmetry. After a pedagogical introduction and overview of the whole of neutrino physics, we focus on the PMNS mixing matrix and the latest global fits following the Daya Bay and RENO experiments which measure the reactor angle. We then describe the simple bimaximal, tri-bimaximal and golden ratio patterns of lepton mixing and the deviations required for a non-zero reactor angle, with solar or atmospheric mixing sum rules resulting from charged lepton corrections or residual trimaximal mixing. The different types of see-saw mechanism are then reviewed as well as the sequential dominance mechanism. We then give a mini-review of finite group theory, which may be used as a discrete family symmetry broken by flavons either completely, or with different subgroups preserved in the neutrino and charged lepton sectors. These two approaches are then reviewed in detail in separate chapters including mechanisms for flavon vacuum alignment and different model building strategies that have been proposed to generate the reactor angle. We then briefly review grand unified theories (GUTs) and how they may be combined with discrete family symmetry to describe all quark and lepton masses and mixing. Finally we discuss three model examples which combine an SU(5) GUT with the discrete family symmetries A4, S4 and Delta(96).

Stephen F. King; Christoph Luhn

2013-01-07T23:59:59.000Z

402

Partial oxidation catalyst  

DOE Patents (OSTI)

A two-part catalyst comprising a dehydrogenation portion and an oxide-ion conducting portion. The dehydrogenation portion is a group VIII metal and the oxide-ion conducting portion is selected from a ceramic oxide crystallizing in the fluorite or perovskite structure. There is also disclosed a method of forming a hydrogen rich gas from a source of hydrocarbon fuel in which the hydrocarbon fuel contacts a two-part catalyst comprising a dehydrogenation portion and an oxide-ion conducting portion at a temperature not less than about 400.degree. C. for a time sufficient to generate the hydrogen rich gas while maintaining CO content less than about 5 volume percent. There is also disclosed a method of forming partially oxidized hydrocarbons from ethanes in which ethane gas contacts a two-part catalyst comprising a dehydrogenation portion and an oxide-ion conducting portion for a time and at a temperature sufficient to form an oxide.

Krumpelt, Michael (Naperville, IL); Ahmed, Shabbir (Bolingbrook, IL); Kumar, Romesh (Naperville, IL); Doshi, Rajiv (Downers Grove, IL)

2000-01-01T23:59:59.000Z

403

Why sequence carbon monoxide oxidizing thermophiles?  

NLE Websites -- All DOE Office Websites (Extended Search)

carbon monoxide oxidizing thermophiles? carbon monoxide oxidizing thermophiles? Many microbes that use carbon monoxide as an energy source are found in high temperature environments such as geothermal areas. Researchers think that these carboxydotrophs may be involved in reducing potentially toxic carbon monoxide hotspots by combine with water to form hydrogen, carbon dioxide and acetate, which are in turn used for thermophilic energy conservation and carbon sequestration mechanisms. The project focuses on sequencing two closely related microbes, one of which is Carboxydothermus hydrogenformans. A strain of C. hydrogenformans has been grown in hydrogen-enriched synthesis gas (syngas), which contains a mix of hydrogen and carbon monoxide. Researchers are interested in sequencing both microbial strains to track the genome's evolution and

404

Helium Behavior in Oxide Nuclear Fuels: First Principles Modeling  

Science Conference Proceedings (OSTI)

UO2 and (U, Pu)O2 solid solutions (the so-called MOX) nowadays are used as commercial nuclear fuels in many countries. One of the safety issues during the storage of these fuels is related to their self-irradiation that produces and accumulates point defects and helium therein. We present density functional theory (DFT) calculations for UO2, PuO2 and MOX containing He atoms in octahedral interstitial positions. In particular, we calculated basic MOX properties and He incorporation energies as functions of Pu concentration within the spin-polarized, generalized gradient approximation (GGA) DFT calculations. We also included the on-site electron correlation corrections using the Hubbard model (in the framework of the so-called DFT + U approach). We found that PuO2 remains semiconducting with He in the octahedral position while UO2 requires a specific lattice distortion. Both materials reveal a positive energy for He incorporation, which, therefore, is an exothermic process. The He incorporation energy increases with the Pu concentration in the MOX fuel.

Gryaznov, D.; Rashkeev, Sergey N.; Kotomin, E. A.; Heifets, Eugene; Zhukovskii, Yuri F.

2010-10-01T23:59:59.000Z

405

Advanced Mixed Waste Treatment Project Achieves Impressive Safety...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Advanced Mixed Waste Treatment Project Achieves Impressive Safety and Production Marks Advanced Mixed Waste Treatment Project Achieves Impressive Safety and Production Marks June...

406

DOE intends to extend the Advanced Mixed Waste Treatment Project...  

NLE Websites -- All DOE Office Websites (Extended Search)

DOE intends to extend the Advanced Mixed Waste Treatment Project contract for four months as competition for long-term contract continues. Scene from inside the Advanced Mixed...

407

Fuel Mix and Emissions Disclosure | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Fuel Mix and Emissions Disclosure Fuel Mix and Emissions Disclosure Eligibility Utility Program Information Maine Program Type Generation Disclosure Maine's 1997 restructuring...

408

Fuel Mix and Emissions Disclosure | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Fuel Mix and Emissions Disclosure Fuel Mix and Emissions Disclosure Eligibility Utility Program Information Nevada Program Type Generation Disclosure In 2001, Nevada enacted...

409

Influence of indoor transport and mixing times scales on the...  

NLE Websites -- All DOE Office Websites (Extended Search)

Influence of indoor transport and mixing times scales on the performance of sensor systems for characterizing contaminant releases Title Influence of indoor transport and mixing...

410

Oxide Melt Solution Calorimetry of Fe2+ -bearing Oxides and Application to the Magnetite - Maghemite (Fe3O4-Fe8/3O4) system  

Science Conference Proceedings (OSTI)

A consistent methodology for obtaining enthalpy of formation of Fe{sup 2+}-containing binary and multicomponent oxides using high temperature oxide melt solution calorimetry has been developed. The enthalpies of wuestite (FeO) and magnetite (Fe{sub 3}O{sub 4}) oxidation to hematite (Fe{sub 2}O{sub 3}) were measured using oxidative drop solution calorimetry in which the final product is dissolved ferric oxide. Two methods were applied: drop solution calorimetry at 1073 K in lead borate solvent and at 973 K in sodium molybdate, each under both oxygen flowing over and bubbling through the solvent, giving consistent results in agreement with literature values. The enthalpies of formation of all three iron oxides from the elements were obtained using a thermodynamic cycle involving the directly measured oxidative dissolution enthalpy of iron metal in sodium molybdate at 973 K and gave excellent consistency with literature data. The methodology was then applied to the magnetite - maghemite system. The enthalpy of mixing of the Fe{sub 3}O{sub 4}-Fe{sub 8/3}O{sub 4} spinel solid solution is exothermic and, 2 represented by a subregular (Margules) formalism, {Delta}H{sub mix} = x(1-x)(-63.36 {+-} 8.60(1-x) + 17.65 {+-} 6.40x) kJ/mol, where x is the mole fraction of magnetite. The entropies of mixing of the solid solution were calculated for different assumptions about the distribution of cations, charges, and vacancies in these defect spinels. The different models lead to only small differences in the entropy of mixing. Calculated free energies of mixing show no evidence for a solvus in the magnetite - maghemite system.

Lilova, Kristina I.; Xu, Fen; Rosso, Kevin M.; Pearce, Carolyn I.; Kamali, Saeed; Navrotsky, Alexandra

2012-01-01T23:59:59.000Z

411

Independent Oversight Inspection, Savannah River Site - December 2009 |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

December December 2009 Independent Oversight Inspection, Savannah River Site - December 2009 December 2009 Inspection of Reinforced Concrete Construction at the Savannah River Site Mixed Oxide Fuel Fabrication Facility The U.S. Department of Energy (DOE) Office of Independent Oversight conducted a nuclear safety inspection at the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF) construction project, focusing on construction quality, specifically for reinforced concrete, at the MFFF construction project. This purpose of the inspection was to provide mission support to site management in determining whether the facility structure is constructed in accordance with the applicable requirements. The overall quality of concrete that has been placed in the MFFF to date is

412

Mixed n-Step MIR Inequalities: Facets for the n-Mixing Set  

E-Print Network (OSTI)

Sep 29, 2011 ... Mathematical Programming 120(2009) 313-346] introduced the n-step MIR inequalities for the mixed integer knapsack set through a ...

413

Oak Ridge National Laboratory The SCALE development team is putting the final touches on  

E-Print Network (OSTI)

Oxide (MOX) Fuel Fabrication Facility DOE's Office of Nuclear Energy and funding for the related Pit not reflect funding for the MOX Project or the PDCF/WSB project. These shifts do not change or diminish in any for the MOX Facility program from NNSA to the Office of Nuclear Energy starting in FY 2008. Page 6 #12

414

Flammability Analysis For Actinide Oxides Packaged In 9975 Shipping Containers  

SciTech Connect

Packaging options are evaluated for compliance with safety requirements for shipment of mixed actinide oxides packaged in a 9975 Primary Containment Vessel (PCV). Radiolytic gas generation rates, PCV internal gas pressures, and shipping windows (times to reach unacceptable gas compositions or pressures after closure of the PCV) are calculated for shipment of a 9975 PCV containing a plastic bottle filled with plutonium and uranium oxides with a selected isotopic composition. G-values for radiolytic hydrogen generation from adsorbed moisture are estimated from the results of gas generation tests for plutonium oxide and uranium oxide doped with curium-244. The radiolytic generation of hydrogen from the plastic bottle is calculated using a geometric model for alpha particle deposition in the bottle wall. The temperature of the PCV during shipment is estimated from the results of finite element heat transfer analyses.

2013-03-21T23:59:59.000Z

415

Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report, December 1,1978--February 28, 1979  

SciTech Connect

Information is presented concerning coolant mixing in bundle geometry and subchannel geometry; outlet plenum flow mixing; and theoretical determination of local temperature fields in LMFBR fuel rod bundles.

Todreas, N.E.; Golay, M.W.; Wolf, L.

1979-01-01T23:59:59.000Z

416

Biofilter for removal of nitrogen oxides from contaminated gases under aerobic conditions  

DOE Patents (OSTI)

A biofilter is described for reducing concentrations of gaseous nitrogen oxides in a polluted gas comprises a porous organic filter bed medium disposed in a housing, the filter bed medium including a mixed culture of naturally occurring denitrifying bacteria for converting the nitrogen oxides to nitrogen gas, carbon dioxide, and water. A method is described of reducing concentrations of nitrogen oxides in polluted gas comprises conducting the polluted gas through the biofilter so that the denitrifying bacteria can degrade the nitrogen oxides. A preferred filter medium is wood compost, however composts of other organic materials are functional. Regulation of pH, moisture content, exogenous carbon sources, and temperature are described. 6 figs.

Apel, W.A.

1998-08-18T23:59:59.000Z

417

Biofilter for removal of nitrogen oxides from contaminated gases under aerobic conditions  

DOE Patents (OSTI)

A biofilter for reducing concentrations of gaseous nitrogen oxides in a polluted gas comprises a porous organic filter bed medium disposed in a housing, the filter bed medium including a mixed culture of naturally occurring denitrifying bacteria for converting the nitrogen oxides to nitrogen gas, carbon dioxide, and water. A method of reducing concentrations of nitrogen oxides in polluted gas comprises conducting the polluted gas through the biofilter so that the denitrifying bacteria can degrade the nitrogen oxides. A preferred filter medium is wood compost, however composts of other organic materials are functional. Regulation of pH, moisture content, exogenous carbon sources, and temperature are described.

Apel, William A. (Idaho Falls, ID)

1998-01-01T23:59:59.000Z

418

Neutrino Mass and Mixing with Discrete Symmetry  

E-Print Network (OSTI)

This is a review article about neutrino mass and mixing and flavour model building strategies based on discrete family symmetry. After a pedagogical introduction and overview of the whole of neutrino physics, we focus on the PMNS mixing matrix and the latest global fits following the Daya Bay and RENO experiments which measure the reactor angle. We then describe the simple bimaximal, tri-bimaximal and golden ratio patterns of lepton mixing and the deviations required for a non-zero reactor angle, with solar or atmospheric mixing sum rules resulting from charged lepton corrections or residual trimaximal mixing. The different types of seesaw mechanism are then reviewed as well as the sequential dominance mechanism. We then give a mini-review of finite group theory, which may be used as a discrete family symmetry broken by flavons either completely, or with different subgroups preserved in the neutrino and charged lepton sectors. These two approaches are then reviewed in detail in separate chapters including mec...

King, Stephen F

2013-01-01T23:59:59.000Z

419

Multipartite entangled states in particle mixing  

Science Conference Proceedings (OSTI)

In the physics of flavor mixing, the flavor states are given by superpositions of mass eigenstates. By using the occupation number to define a multiqubit space, the flavor states can be interpreted as multipartite mode-entangled states. By exploiting a suitable global measure of entanglement, based on the entropies related to all possible bipartitions of the system, we analyze the correlation properties of such states in the instances of three- and four-flavor mixing. Depending on the mixing parameters, and, in particular, on the values taken by the free phases, responsible for the CP-violation, entanglement concentrates in certain bipartitions. We quantify in detail the amount and the distribution of entanglement in the physically relevant cases of flavor mixing in quark and neutrino systems. By using the wave packet description for localized particles, we use the global measure of entanglement, suitably adapted for the instance of multipartite mixed states, to analyze the decoherence, induced by the free evolution dynamics, on the quantum correlations of stationary neutrino beams. We define a decoherence length as the distance associated with the vanishing of the coherent interference effects among massive neutrino states. We investigate the role of the CP-violating phase in the decoherence process.

Blasone, M. [Dipartimento di Matematica e Informatica, Universita degli Studi di Salerno, Via Ponte don Melillo, I-84084 Fisciano (Italy); INFN Sezione di Napoli, Gruppo collegato di Salerno, Baronissi (Italy); Dell'Anno, F.; De Siena, S. [Dipartimento di Matematica e Informatica, Universita degli Studi di Salerno, Via Ponte don Melillo, I-84084 Fisciano (Italy); INFN Sezione di Napoli, Gruppo collegato di Salerno, Baronissi (Italy); CNR-INFM Coherentia, Napoli (Italy); Di Mauro, M. [INFN Sezione di Napoli, Gruppo collegato di Salerno, Baronissi (Italy); Illuminati, F. [Dipartimento di Matematica e Informatica, Universita degli Studi di Salerno, Via Ponte don Melillo, I-84084 Fisciano (Italy); INFN Sezione di Napoli, Gruppo collegato di Salerno, Baronissi (Italy); CNR-INFM Coherentia, Napoli (Italy); ISI Foundation for Scientific Interchange, Viale Settimio Severo 65, 00173 Torino (Italy)

2008-05-01T23:59:59.000Z

420

Multipartite entangled states in particle mixing  

E-Print Network (OSTI)

In the physics of flavor mixing, the flavor states are given by superpositions of mass eigenstates. By using the occupation number to define a multiqubit space, the flavor states can be interpreted as multipartite mode-entangled states. By exploiting a suitable global measure of entanglement, based on the entropies related to all possible bipartitions of the system, we analyze the correlation properties of such states in the instances of three- and four-flavor mixing. Depending on the mixing parameters, and, in particular, on the values taken by the free phases, responsible for the CP-violation, entanglement concentrates in preferred bipartitions. We quantify in detail the amount and the distribution of entanglement in the physically relevant cases of flavor mixing in quark and neutrino systems. By using the wave packet description for localized particles, we use the global measure of entanglement, suitably adapted for the instance of multipartite mixed states, to analyze the decoherence induced by the free evolution dynamics on the quantum correlations of stationary neutrino beams. We define a decoherence length as the distance associated with the vanishing of the coherent interference effects among massive neutrino states. We investigate the role of the CP-violating phase in the decoherence process.

M. Blasone; F. Dell'Anno; S. De Siena; M. Di Mauro; F. Illuminati

2007-11-14T23:59:59.000Z

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


421

Barium oxide, calcium oxide, magnesia, and alkali oxide free glass  

DOE Patents (OSTI)

A glass composition consisting essentially of about 10-45 mole percent of SrO; about 35-75 mole percent SiO.sub.2; one or more compounds from the group of compounds consisting of La.sub.2O.sub.3, Al.sub.2O.sub.3, B.sub.2O.sub.3, and Ni; the La.sub.2O.sub.3 less than about 20 mole percent; the Al.sub.2O.sub.3 less than about 25 mole percent; the B.sub.2O.sub.3 less than about 15 mole percent; and the Ni less than about 5 mole percent. Preferably, the glass is substantially free of barium oxide, calcium oxide, magnesia, and alkali oxide. Preferably, the glass is used as a seal in a solid oxide fuel/electrolyzer cell (SOFC) stack. The SOFC stack comprises a plurality of SOFCs connected by one or more interconnect and manifold materials and sealed by the glass. Preferably, each SOFC comprises an anode, a cathode, and a solid electrolyte.

Lu, Peizhen Kathy; Mahapatra, Manoj Kumar

2013-09-24T23:59:59.000Z

422

Advanced Mixed Waste Treatment: Results of Mixed Waste Treatment at the M-4 Facility  

Science Conference Proceedings (OSTI)

Processing alternatives for commercial nuclear plant mixed wastes are limited. In order to expand potential treatment options, EPRI entered a collaborative research agreement to process mixed wastes at an environmental facility. This report documents the success of that effort to date.

1997-12-31T23:59:59.000Z

423

Multifunctional Oxide Heterostructures  

Science Conference Proceedings (OSTI)

This book is devoted to the rapidly developing field of oxide thin-films and heterostructures. Oxide materials combined with atomic-scale precision in a heterostructure exhibit an abundance of macroscopic physical properties involving the strong coupling between the electronic, spin, and structural degrees of freedom, and the interplay between magnetism, ferroelectricity, and conductivity. Recent advances in thin-film deposition and characterization techniques made possible the experimental realization of such oxide heterostructures, promising novel functionalities and device concepts.

Tsymbal, E Y [University of Nebraska, Lincoln; Dagotto, Elbio R [ORNL; Eom, Professor Chang-Beom [University of Wisconsin, Madison; Ramesh, Ramamoorthy [University of California, Berkeley

2012-01-01T23:59:59.000Z

424

METAL OXIDE NANOPARTICLES  

SciTech Connect

This chapter covers the fundamental science, synthesis, characterization, physicochemical properties and applications of oxide nanomaterials. Explains fundamental aspects that determine the growth and behavior of these systems, briefly examines synthetic procedures using bottom-up and top-down fabrication technologies, discusses the sophisticated experimental techniques and state of the art theory results used to characterize the physico-chemical properties of oxide solids and describe the current knowledge concerning key oxide materials with important technological applications.

FERNANDEZ-GARCIA,M.; RODGRIGUEZ, J.A.

2007-10-01T23:59:59.000Z

425

Dry powder mixes comprising phase change materials  

DOE Patents (OSTI)

A free flowing, conformable powder-like mix of silica particles and a phase change material (p.c.m.) is disclosed. The silica particles have a critical size of about 7 [times] 10[sup [minus]3] to about 7 [times] 10[sup [minus]2] microns and the pcm must be added to the silica in an amount of 80 wt. % or less pcm per combined weight of silica and pcm. The powder-like mix can be used in tableware items, medical wraps, tree wraps, garments, quilts and blankets, and in cementitious compositions of the type in which it is beneficial to use a pcm material. The silica-pcm mix can also be admixed with soil to provide a soil warming effect and placed about a tree, flower, or shrub. 9 figs.

Salyer, I.O.

1992-04-21T23:59:59.000Z

426

Dry powder mixes comprising phase change materials  

DOE Patents (OSTI)

Free flowing, conformable powder-like mix of silica particles and a phase change material (p.c.m.) is disclosed. The silica particles have a critical size of about 7[times]10[sup [minus]3] to about 7[times]10[sup [minus]2] microns and the p.c.m. must be added to the silica in an amount of 80 wt. % or less p.c.m. per combined weight of silica and p.c.m. The powder-like mix can be used in tableware items, medical wraps, tree wraps, garments, quilts and blankets, and in cementitious compositions of the type in which it is beneficial to use a p.c.m. material. The silica-p.c.m. mix can also be admixed with soil to provide a soil warming effect and placed about a tree, flower, or shrub.

Salyer, I.O.

1993-05-18T23:59:59.000Z

427

Dry powder mixes comprising phase change materials  

DOE Patents (OSTI)

Free flowing, conformable powder-like mix of silica particles and a phase change material (p.c.m.) is disclosed. The silica particles have a critical size of about 7.times.10.sup.-3 to about 7.times.10.sup.-2 microns and the pcm must be added to the silica in an amount of 80 wt. % or less pcm per combined weight of silica and pcm. The powder-like mix can be used in tableware items, medical wraps, tree wraps, garments, quilts and blankets, and in cementitious compositions of the type in which it is beneficial to use a pcm material. The silica-pcm mix can also be admixed with soil to provide a soil warming effect and placed about a tree, flower, or shrub.

Salyer, Ival O. (Dayton, OH)

1993-01-01T23:59:59.000Z

428

Dry powder mixes comprising phase change materials  

DOE Patents (OSTI)

Free flowing, conformable powder-like mix of silica particles and a phase change material (p.c.m.) is disclosed. The silica particles have a critical size of about 7.times.10.sup.-3 to about 7.times.10.sup.-2 microns and the pcm must be added to the silica in an amount of 80 wt. % or less pcm per combined weight of silica and pcm. The powder-like mix can be used in tableware items, medical wraps, tree wraps, garments, quilts and blankets, and in cementitious compositions of the type in which it is beneficial to use a pcm material. The silica-pcm mix can also be admixed with soil to provide a soil warming effect and placed about a tree, flower, or shrub.

Salyer, Ival O. (Dayton, OH)

1992-01-01T23:59:59.000Z

429

Dry powder mixes comprising phase change materials  

DOE Patents (OSTI)

Free flowing, conformable powder-like mix of silica particles and a phase change material (p.c.m.) is disclosed. The silica particles have a critical size of about 7.times.10.sup.-3 to about 7.times.10.sup.-2 microns and the pcm must be added to the silica in an amount of 80 wt. % or less pcm per combined weight of silica and pcm. The powder-like mix can be used in tableware items, medical wraps, tree wraps, garmets, quilts and blankets, and in cementitious compositions of the type in which it is beneficial to use a pcm material. The silica-pcm mix can also be admixed with soil to provide a soil warming effect and placed about a tree, flower, or shrub.

Salyer, Ival O. (Dayton, OH)

1993-01-01T23:59:59.000Z

430

Unified Graphical Summary of Neutrino Mixing Parameters  

E-Print Network (OSTI)

The neutrino mixing parameters are presented in a number of different ways by the various experiments, e.g. SuperKamiokande, K2K, SNO, KamLAND and Chooz and also by the Particle Data Group. In this paper, we argue that presenting the data in terms of $\\sin^2 \\theta$, where $\\theta$ is the mixing angle appropriate for a given experiment has a direct physical interpretation. For current atmospheric, solar and reactor neutrino experiments, the $\\sin^2 \\theta$'s are effectively the probability of finding a given flavor in a particular neutrino mass eigenstate. The given flavor and particular mass eigenstate varies from experiment to experiment, however, the use of $\\sin^2 \\theta$ provides a unified picture of all the data. Using this unified picture we present a graphical way to represent these neutrino mixing parameters which includes the uncertainties. All of this is performed in the context of the present experimental status of three neutrino oscillations.

Olga Mena; Stephen Parke

2003-12-10T23:59:59.000Z

431

Dry powder mixes comprising phase change materials  

DOE Patents (OSTI)

Free flowing, conformable powder-like mix of silica particles and a phase change material (PCM) is provided. The silica particles have a critical size of about 0.005 to about 0.025 microns and the PCM must be added to the silica in an amount of 75% or less PCM per combined weight of silica and PCM. The powder-like mix can be used in tableware items, medical wraps, tree wraps, garments, quilts and blankets, and in cementitious compositions of the type in which it is beneficial to use a PCM material. The silica-PCM mix can also be admixed with soil to provide a soil warming effect and placed about a tree, flower, or shrub.

Salyer, Ival O. (Dayton, OH)

1994-01-01T23:59:59.000Z

432

Dry powder mixes comprising phase change materials  

DOE Patents (OSTI)

Free flowing, conformable powder-like mix of silica particles and a phase change material (PCM) is provided. The silica particles have a critical size of about 0.005 to about 0.025 microns and the PCM must be added to the silica in an amount of 75% or less PCM per combined weight of silica and PCM. The powder-like mix can be used in tableware items, medical wraps, tree wraps, garments, quilts and blankets, and in cementitious compositions of the type in which it is beneficial to use a PCM material. The silica-PCM mix can also be admixed with soil to provide a soil warming effect and placed about a tree, flower, or shrub. 2 figures.

Salyer, I.O.

1994-02-01T23:59:59.000Z

433

Durable zinc oxide-containing sorbents for coal gas desulfurization  

DOE Patents (OSTI)

Durable zinc-oxide containing sorbent pellets for removing hydrogen sulfide from a gas stream at an elevated temperature are made up to contain titania as a diluent, high-surface-area silica gel as a matrix material, and a binder. These materials are mixed, moistened, and formed into pellets, which are then dried and calcined. The resulting pellets undergo repeated cycles of sulfidation and regeneration without loss of reactivity and without mechanical degradation. Regeneration of the pellets is carried out by contacting the bed with an oxidizing gas mixture.

Siriwardane, R.V.

1994-12-31T23:59:59.000Z

434

Defect Structure of Oxides  

Science Conference Proceedings (OSTI)

Table 1   Classification of electrical conductors: oxides, sulfides, and nitrides...2 O 4 , NiAl 2 O 4 , (Tl 2 O),

435

Oxidation of gallium arsenide  

DOE Patents (OSTI)

This invention relates to gallium arsenide semiconductors and, more particularly, to the oxidation of surface layers of gallium arsenide semiconductors for semiconductor device fabrication.

Hoffbauer, M.A.; Cross, J.B.

1991-11-16T23:59:59.000Z

436

Oxidation/Coatings  

Science Conference Proceedings (OSTI)

Oct 28, 2009 ... International Symposium on Ceramic Matrix Composites: Oxidation/ ... on combustor liners of a Solar Turbines' industrial gas turbine engine, ...

437

Pulse Jet Mixing Tests With Noncohesive Solids  

SciTech Connect

This report summarizes results from pulse jet mixing (PJM) tests with noncohesive solids in Newtonian liquid. The tests were conducted during FY 2007 and 2008 to support the design of mixing systems for the Hanford Waste Treatment and Immobilization Plant (WTP). Tests were conducted at three geometric scales using noncohesive simulants, and the test data were used to develop models predicting two measures of mixing performance for full-scale WTP vessels. The models predict the cloud height (the height to which solids will be lifted by the PJM action) and the critical suspension velocity (the minimum velocity needed to ensure all solids are suspended off the floor, though not fully mixed). From the cloud height, the concentration of solids at the pump inlet can be estimated. The predicted critical suspension velocity for lifting all solids is not precisely the same as the mixing requirement for 'disturbing' a sufficient volume of solids, but the values will be similar and closely related. These predictive models were successfully benchmarked against larger scale tests and compared well with results from computational fluid dynamics simulations. The application of the models to assess mixing in WTP vessels is illustrated in examples for 13 distinct designs and selected operational conditions. The values selected for these examples are not final; thus, the estimates of performance should not be interpreted as final conclusions of design adequacy or inadequacy. However, this work does reveal that several vessels may require adjustments to design, operating features, or waste feed properties to ensure confidence in operation. The models described in this report will prove to be valuable engineering tools to evaluate options as designs are finalized for the WTP. Revision 1 refines data sets used for model development and summarizes models developed since the completion of Revision 0.

Meyer, Perry A.; Bamberger, Judith A.; Enderlin, Carl W.; Fort, James A.; Wells, Beric E.; Sundaram, S. K.; Scott, Paul A.; Minette, Michael J.; Smith, Gary L.; Burns, Carolyn A.; Greenwood, Margaret S.; Morgen, Gerald P.; Baer, Ellen BK; Snyder, Sandra F.; White, Michael K.; Piepel, Gregory F.; Amidan, Brett G.; Heredia-Langner, Alejandro

2012-02-17T23:59:59.000Z

438

Mixed-hybrid discretization methods for the P1 equations  

Science Conference Proceedings (OSTI)

We consider mixed-hybrid discretization methods for the linear Boltzmann transport equation which is extensively used in computational neutron transport. Mixed-hybrid methods combine attractive features of both mixed and hybrid methods, namely the simultaneous ... Keywords: 02.60.Cb, 02.70.Dh, 65N12, 65N30, Linear Boltzmann transport equation, Mixed-hybrid discretization methods, P1 approximation

S. Van Criekingen; R. Beauwens

2007-02-01T23:59:59.000Z

439

Mixed waste paper to ethanol fuel  

DOE Green Energy (OSTI)

The objectives of this study were to evaluate the use of mixed waste paper for the production of ethanol fuels and to review the available conversion technologies, and assess developmental status, current and future cost of production and economics, and the market potential. This report is based on the results of literature reviews, telephone conversations, and interviews. Mixed waste paper samples from residential and commercial recycling programs and pulp mill sludge provided by Weyerhauser were analyzed to determine the potential ethanol yields. The markets for ethanol fuel and the economics of converting paper into ethanol were investigated.

Not Available

1991-01-01T23:59:59.000Z

440

Model Independent Bounds on Kinetic Mixing  

SciTech Connect

New Abelian vector bosons can kinetically mix with the hypercharge gauge boson of the Standard Model. This letter computes the model independent limits on vector bosons with masses from 1 GeV to 1 TeV. The limits arise from the numerous e{sup +}e{sup -} experiments that have been performed in this energy range and bound the kinetic mixing by {epsilon} {approx}< 0.03 for most of the mass range studied, regardless of any additional interactions that the new vector boson may have.

Hook, Anson; Izaguirre, Eder; Wacker, Jay G.; /SLAC

2011-08-22T23:59:59.000Z

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


441

Shape Coexistence and Mixing in 152Sm  

E-Print Network (OSTI)

Experimental studies of 152Sm using multiple-step Coulomb excitation and inelastic neutron scattering provide key data that clarify the low-energy collective structure of this nucleus. No candidates for two-phonon beta-vibrational states are found. Experimental level energies of the ground-state and first excited (0+ state) rotational bands, electric monopole transition rates, reduced quadrupole transition rates, and the isomer shift of the first excited 2+ state are all described within ~10% precision using two-band mixing calculations. The basic collective structure of 152Sm is described using strong mixing of near-degenerate coexisting quasi-rotational bands with different deformations.

Kulp, W D; Garrett, P E; Wu, C Y; Cline, D; Allmond, J M; Bandyopadhyay, D; Dashdorj, D; Choudry, S N; Hayes, A B; Hua, H; Lesher, S; Mynk, M; McEllistrem, M T; McKay, C J; Orce, J C; Teng, R; Yates, S W

2007-01-01T23:59:59.000Z

442

Shape Coexistence and Mixing in 152Sm  

E-Print Network (OSTI)

Experimental studies of 152Sm using multiple-step Coulomb excitation and inelastic neutron scattering provide key data that clarify the low-energy collective structure of this nucleus. No candidates for two-phonon beta-vibrational states are found. Experimental level energies of the ground-state and first excited (0+ state) rotational bands, electric monopole transition rates, reduced quadrupole transition rates, and the isomer shift of the first excited 2+ state are all described within ~10% precision using two-band mixing calculations. The basic collective structure of 152Sm is described using strong mixing of near-degenerate coexisting quasi-rotational bands with different deformations.

W. D. Kulp; J. L. Wood; P. E. Garrett; C. Y. Wu; D. Cline; J. M. Allmond; D. Bandyopadhyay; D. Dashdorj; S. N. Choudry; A. B. Hayes; H. Hua; S. R. Lesher; M. Mynk; M. T. McEllistrem; C. J. McKay; J. N. Orce; R. Teng; S. W. Yates

2007-06-28T23:59:59.000Z

443

Dry powder mixes comprising phase change materials  

DOE Green Energy (OSTI)

A free flowing, conformable powder-like mix of silica particles and a phase change material (PCM) is provided. The silica particles have a critical size of about 0.005 to about 0.025 microns and the PCM must be added to the silica in an amount of 75% or less PCM per combined weight of silica and PCM. The powder-like mix can be used in tableware items, medical wraps, tree wraps, garments, quilts and blankets, and particularly in applications for heat protection for heat sensitive items, such as aircraft flight recorders, and for preventing brake fade in automobiles, buses, trucks and aircraft. 3 figs.

Salyer, I.O.

1995-12-26T23:59:59.000Z

444

Rating of Mixed Split Residential Air Conditioners  

E-Print Network (OSTI)

A methodology is presented for rating the performance of mixed, split residential air conditioners. The method accounts for the impact on system performance of the indoor evaporator, expansion device and fan; three major components that are likely to be substituted for the matched components in a mixed system. The method allows calculation of capacity at 95°F rating point and seasonal energy efficiency ratio, SEER, without performing laboratory test of the complete system. Limitations of the procedure, present work, and anticipated improvements are also discussed.

Domanski, P. A.

1988-01-01T23:59:59.000Z

445

Dry powder mixes comprising phase change materials  

DOE Patents (OSTI)

A free flowing, conformable powder-like mix of silica particles and a phase change material (PCM) is provided. The silica particles have a critical size of about 0.005 to about 0.025 microns and the PCM must be added to the silica in an amount of 75% or less PCM per combined weight of silica and PCM. The powder-like mix can be used in tableware items, medical wraps, tree wraps, garments, quilts and blankets, and particularly in applications for heat protection for heat sensitive items, such as aircraft flight recorders, and for preventing brake fade in automobiles, buses, trucks and aircraft. 3 figures.

Salyer, I.O.

1994-12-06T23:59:59.000Z

446

Dry powder mixes comprising phase change materials  

DOE Patents (OSTI)

A free flowing, conformable powder-like mix of silica particles and a phase change material (PCM) is provided. The silica particles have a critical size of about 0.005 to about 0.025 microns and the PCM must be added to the silica in an amount of 75% or less PCM per combined weight of silica and PCM. The powder-like mix can be us