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Exploiting the steady state, continuous fueling reactor model

Description: A continuously fueled reactor presents an analysis challenge, especially so when the neutron accounting is sensitive to the core design and the fuel handling. A scheme was implemented to solve the steady state, continuous fueling problem. This problem is an accurate model of the reactor for assessing performance at a point in its operating history. Available capability in a modular code system developed to treat fixed fuel reactors was extended in this effort. Parametric studies have been made … more
Date: January 1, 1979
Creator: Vondy, D.R.; Cunningham, G.W. & Fowler, T.B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Safety analysis for operating the Annular Core Research Reactor with Cintichem-type targets installed in the central region of the core

Description: Production of the molybdenum-99 isotope at the Annular Core Research Reactor requires highly enriched, uranium oxide loaded targets to be irradiated for several days in the high neutron-flux region of the core. This report presents the safety analysis for the irradiation of up to seven Cintichem-type targets in the central region of the core and compares the results to the Annular Core Research Reactor Safety Analysis Report. A 19 target grid configuration is presented that allows one to seven … more
Date: January 1, 2000
Creator: PARMA JR.,EDWARD J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Selective NOx Recirculation for Stationary Lean-Burn Natural Gas Engines

Description: Selective NOx Recirculation (SNR) involves cooling the engine exhaust gas and then adsorbing the oxides of nitrogen (NOx) from the exhaust stream, followed by the periodic desorption of NOx. By returning the desorbed, concentrated NOx into the engine intake and through the combustion chamber, a percentage of the NOx is decomposed during the combustion process. An initial study of NOx decomposition during lean-burn combustion was concluded in 2004 using a 1993 Cummins L10G 240hp natural gas engi… more
Date: December 28, 2005
Creator: Clark, Nigel; Thompson, Gregory; Atkinson, Richard; Turton, Richard; Tissera, Chamila; Tatli, Emre et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Studies of Flexible MOX/LEU Fuel Cycles

Description: 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… more
Date: March 1, 1999
Creator: Adams, M.L. & Alonso-Vargas, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiation Effect on Microstructural Stability of RERTR Fuel

Description: Three depleted uranium alloys are successfully cast for the radiation stability studies of the fuel-cladding interaction product using proton irradiation. SEM analysis indicates the presence of the phases of interest: U(Si,Al)3, (U,Mo)(Si,Al)3 and a mixture of UMo2Al20, U6Mo4Al43, and UAl4. Irradiation with 2.6 MeV protons at 200ºC to the doses of 0.1, 1.0 and 3.0 dpa are carried out.
Date: March 1, 2008
Creator: Gan, J.; Keiser, D. D. Jr.; Miller, B. D.; Allen, T. R. & Wachs, D. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Analysis of the ATW fuel cycle using the REBUS-3 code system.

Description: Partitioning and transmutation strategies are under study in several countries as a means of reducing the long-term hazards of spent fuel and other high-level nuclear waste. Various reactor and accelerator-driven system concepts have been proposed to transmute the long-lived radioactive nuclei of waste into stable or short-lived species. Among these concepts, the accelerator-driven transmutation of waste (ATW) system has been proposed by LANL for rapid destruction of transuranic actinides and l… more
Date: June 25, 1999
Creator: Khalil, H. S. & Yang, W. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Results of Recent Microstructural Characterization of Irradiated U-Mo Dispersion Fuels with Al Alloy Matrices that Contain Si

Description: RERTR U-Mo dispersion fuel plates are being developed for application in research reactors throughout the world. Of particular interest is the irradiation performance of U-Mo dispersion fuels with Si added to the Al matrix. Si is added to improve the performance of U-Mo dispersion fuels. Microstructural examinations have been performed on fuel plates with either Al-0.2Si or 4043 Al (~4.8% Si) alloy matrix in the as-fabricated and/or as-irradiated condition using optical metallography and/or sca… more
Date: March 1, 2008
Creator: Keiser, D. D. Jr.; Robinson, A. B.; Janney, D. E. & Jue, J. F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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BWR Assembly Optimization for Minor Actinide Recycling

Description: The Primary objective of the proposed project is to apply and extend the latest advancements in LWR fuel management optimization to the design of advanced boiling water reactor (BWR) fuel assemblies specifically for the recycling of minor actinides (MAs).
Date: March 22, 2010
Creator: Maldonado, G. Ivan; Christenson, John M.; Renier, J.P.; Marcille, T.F. & Casal, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Update on US High Density Fuel Fabrication Development

Description: Second generation uranium molybdenum fuel has shown excellent in-reactor irradiation performance. This metallic fuel type is capable of being fabricated at much higher loadings than any presently used research reactor fuel. Due to the broad range of fuel types this alloy system encompasses—fuel powder to monolithic foil and binary fuel systems to multiple element additions—significant amounts of research and development have been conducted on the fabrication of these fuels. This paper presents … more
Date: March 1, 2007
Creator: Clark, C. R.; Moore, G. A.; Jue, J. F.; Park, B. H.; Hallinan, N. P.; Wachs, D. M. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Three dimensional depletion analysis for the ''as built'' FSV initial core

Description: During fabrication of the initial FSV core fuel elements, some difficulties with assayed quantities of uranium and thorium were encountered. This problem became apparent when about 40 percent of the total fuel rod requirement was in some state of production and about 10 percent of the fuel elements had been assembled. As a result, some of the specified fuel blends were nearing completion and the uranium and/or thorium was 3 to 4 percent too high or low, and some of the already assembled fuel el… more
Date: November 15, 1975
Creator: Nirschl, R.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Advanced Core Design And Fuel Management For Pebble-Bed Reactors

Description: A method for designing and optimizing recirculating pebble-bed reactor cores is presented. At the heart of the method is a new reactor physics computer code, PEBBED, which accurately and efficiently computes the neutronic and material properties of the asymptotic (equilibrium) fuel cycle. This core state is shown to be unique for a given core geometry, power level, discharge burnup, and fuel circulation policy. Fuel circulation in the pebble-bed can be described in terms of a few well?defined p… more
Date: October 1, 2004
Creator: Gougar, Hans D.; Ougouag, Abderrafi M. & Terry, William K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Structural Behavior of Monolithic Fuel Plates During Hot Isostatic Pressing and Annealing

Description: This paper presents results of the stress analysis in the monolithic fuel plates during thermal transients performed using COMSOL finite element analysis software. Large difference in the thermal expansion between the U-Mo foil and Al cladding is the main load origin during heating and cooling of the fuel plates. In addition, the mechanical behavior of the plate is affected by the difference in yield points between the foil and the cladding. This is manifested by the plastic deformation and per… more
Date: March 1, 2010
Creator: Medvedev, Pavel G. & Ozaltun, Hakan
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Findings and views concerning the exemption of aviation gasoline from the mandatory petroleum allocation and price regulations

Description: Presented are DOE's findings and views with respect to its proposal to exempt aviation gasoline from the Mandatory Petroleum Allocation and Price Regulations (10 CFR, Parts 210, 211, and 212), an added section of which requires that any amendment submitted to the Congress for the purpose of exempting a petroleum product or refined product category from regulation be supported with certain findings and views on a variety of matters related to the exemption. Section 102 of the Energy Conservation… more
Date: June 1, 1978
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of Reduced Enrichment on the Fuel Cycle for Research Reactors

Description: The new fuels developed by the RERTR Program and by other international programs for application in research reactors with reduced uranium enrichment (<20% EU) are discussed. It is shown that these fuels, combined with proper fuel-element design and fuel-management strategies, can provide at least the same core residence time as high-enrichment fuels in current use, and can frequently significantly extend it. The effect of enrichment reduction on other components of the research reactor fuel cy… more
Date: 1982
Creator: Travelli, Armando
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Workshop on environmental and energy applications of neural networks

Description: This report consists of the abstracts for the papers given at the conference. Applications of neural networks in the environmental, energy and biomedical fields are discussed. Some of the topics covered are: predicting atmospheric pollutant concentrations due to fossil-fired electric power generation; hazardous waste characterization; nondestructive TRU (transuranic) waste assay; risk analysis; load forecasting for electric utilities; design of a wind power storage and generation system; nuclea… more
Date: March 1, 1995
Creator: Hashem, S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Spent fuel characteristics & disposal considerations

Description: The fuel used in commercial nuclear power reactors is uranium, generally in the form of an oxide. The gas-cooled reactors developed in England use metallic uranium enclosed in a thin layer of Magnox. Since this fuel must be processed into a more stable form before disposal, we will not consider the characteristics of the Magnox spent fuel. The vast majority of the remaining power reactors in the world use uranium dioxide pellets in Zircaloy cladding as the fuel material. Reactors that are fuele… more
Date: June 1, 1996
Creator: Oversby, V.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Retrofittable Modifications to Pressurized Water Reactors for Improved Resource Utilization

Description: This report summarizes work performed for the U.S. Arms Control and Disarmament Agency under BOA AC9NX707 (Task Order 80-02), as part of the Agency's continuing program on improved fuel utilization in light water reactors. The objective of the study was to investigate improvements in fuel management and design of water reactors (PWRs) that could potentially increase the utilization of natural uranium resources in a once-through fuel cycle (i.e., without using spent fuel reprocessing and recycle… more
Date: October 1, 1980
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HTGR spent fuel composition and fuel element block flow

Description: The High-Temperature Gas-Cooled Reactor (HTGR) utilizes the thorium-uranium fuel cycle. Fully enriched uranium fissile material and thorium fertile material are used in the initial reactor core and for makeup fuel in the recycle core loadings. Bred /sup 233/U and unburned /sup 235/U fissile materials are recovered from spent fuel elements, refabricated into recycle fuel elements, and used as part of the recycle core loading along with the makeup fuel elements. A typical HTGR employs a 4-yr fuel… more
Date: July 1, 1976
Creator: Hamilton, C. J.; Holder, N. D.; Pierce, V. H. & Robertson, M. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gas-cooled reactor programs. Fuel-management positioning and accounting module: FUELMANG Version V1. 11, September 1981

Description: This report documents the code module FUELMANG for fuel management of a reactor. This code may be used to position fuel during the calculation of a reactor history, maintain a mass balance history of the fuel movement, and calculate the unit fuel cycle component of the electrical generation cost. In addition to handling fixed feed fuel without recycle, provision has been made for fuel recycle with various options applied to the recycled fuel. A continuous fueling option is also available with t… more
Date: January 1, 1982
Creator: Medlin, T. W.; Hill, K. L.; Johnson, G. L.; Jones, J. E. & Vondy, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Estimation of Isotopic Inventories of 2000 Mwt Abr (Revision 1).

Description: The isotopic inventories of a 2000 MWt Advanced Burner Reactor (ABR) core have been estimated to support the ABR accident analysis to be reported in the Appendix D of the Programmatic Environmental Impact Statement (PEIS). Based on the Super-PRISM design, a preliminary core design of 2000 MWt ABR was developed to achieve a one-year cycle length with 3-batch fuel management scheme. For a bounding estimation of transuranics (TRU) inventory, a low TRU conversion ratio ({approx}0.3) was targeted to… more
Date: June 16, 2008
Creator: Kim, T. K. & Yang, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Utilization Improvements in a Once-Through PWR Fuel Cycle. Final Report on Task 6

Description: In studying the position of the United States Department of Energy, Non-proliferation Alternative Systems Assessment Program, this report determines the uranium saving associated with various improvement concepts applicable to a once-through fuel cycle of a standard four-loop Westinghouse Pressurized Water Reactor. Increased discharged fuel burnup from 33,000 to 45,000 MWD/MTM could achieve a 12% U/sub 3/O/sub 8/ saving by 1990. Improved fuel management schemes combined with coastdown to 60% po… more
Date: June 1, 1979
Creator: Dabby, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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