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Liquid metal fast breeder reactors, 1972--1973

Description: Reference to 1467 publications on liquid sodium fast breeder reactors cited in Nuclear Science Abstracts Volume 26 (1972) through Volume 27 (1973 through June) are contained in this citation to provide information on the contents of the document. References are arranged in order by the original NSA abstract number which approximately places them in chronological order. Sequence numbers appear beside each reference, and the personal author index refers to these sequence numbers. The subject index refers to the original abstract numbers. (auth)
Date: January 1, 1974
Partner: UNT Libraries Government Documents Department

Inhour equation in a two-region reactor with multiplication in both regions

Description: In Reference 1 (G.D. Spriggs, R.D. Busch, and John G. Williams, ``Two-Region Kinetic Model for Reflected Reactors,`` Ann. Nucl. Energy, 24, No. 3, 205, (1997)), the authors presented a two-region point kinetic model for reflected reactors based on the Avery-Cohn differential equations. The model was developed for a core region surrounded by a non-multiplying, source-free reflector region. As part of the model development, they also introduced several probability relationships that were essential to calculating the coupling parameters that linked the two regions. Furthermore, they showed how these coupling parameters could be obtained from deterministic transport solutions. In this work, they present a new model that extends the aforementioned two-region kinetic model by including neutron multiplication in both regions. This new model has practical application to any reactor system that has significantly different neutronic properties in two distinct regions of the system--such as a fast breeder reactor consisting of an inner core surrounded by a multiplying blanket of a different composition. From this new model, they derive the inhour equation that is most appropriate for this type of system.
Date: January 22, 1998
Creator: Spriggs, G.D. & Busch, R.D.
Partner: UNT Libraries Government Documents Department

Summary of the radiological assessment of the fuel cycle for a thorium-uranium carbide-fueled fast breeder reactor

Description: A large fraction of the potential fuel for nuclear power reactors employing fissionable materials exists as ores of thorium. In addition, certain characteristics of a fuel system based on breeding of the fissionable isotope {sup 233}U from thorium offer the possibility of a greater resistance to the diversion of fissionable material for the fabrication of nuclear weapons. This report consolidates into a single source the principal content of two previous reports which assess the radiological environmental impact of mining and milling of thorium ore and of the reprocessing and refabrication of spent FBR thorium-uranium carbide fuel.
Date: January 1, 1980
Creator: Tennery, V.J.; Bomar, E.S.; Bond, W.D.; Meyer, H.R.; Morse, L.E.; Till, J.E. et al.
Partner: UNT Libraries Government Documents Department

Solvent extraction studies of coprocessing flowsheets: results from Campaign 5 of the Solvent Extraction Test Facility (SETF)

Description: In Campaign 5, fast breeder reactor (FBR) fuel [average burnup {similar_to}2.6 TJ/kg ({similar_to}30,000 MWd/t)] was processed for the first time. Operations in a single extraction cycle with 30% TBP-NPH were satisfactory with low heavy-metal losses (< 0.02%) and high decontamination factors (DFs > 1000) for all fission products except {sup 95}Zr, which exhibited moderate DFs (180 and 750, respectively, in two runs). The use of a split scrub stream (0.5 M and 3 M HNO{sub 3}) vs a single scrub stream (3 M HNO{sub 3}) resulted in the higher DF. An extractant backscrubbing stream was not needed to produce partially partitioned uranium-plutonium products containing 30 to 35% plutonium when processing the core FBR fuel (22% Pu). The necessary enrichment factor ({similar_to}1.5) was attained by maintaining the temperature at 25 to 30{sup 0}C in partial partitioning and adjusting the relative flow rates of the aqueous and organic phases. The plutonium recovery in the two runs ({similar_to}400 g) was purified by anion exchange and converted to PuO{sub 2} for fuel refabrication studies. 8 references, 7 figures, 6 tables.
Date: November 1, 1983
Creator: Bond, W.D.; Benker, D.E.; Bigelow, J.E.; Chattin, F.R.; Collins, E.D.; King, L.J. et al.
Partner: UNT Libraries Government Documents Department

Solvent extraction studies of coprocessing flowsheets: results from campaigns 3 and 4 of the Solvent-Extraction Test Facility (SETF)

Description: Experiments on tri-n-butyl phosphate solvent extraction of uranium and plutonium at full activity levels (Campaigns 3 and 4) were conducted in the Solvent Extraction Test Facility (SETF), located in one of the heavily shielded cells of the Transuranium Processing Plant. The primary objectives were: (1) to demonstrate and evaluate the first two cycles of the Hot Engineering Facility flowsheets (codecontamination and partial partitioning), and (2) to investigate and evaluate the use of HNO{sub 2} as the reductant for tetravalent plutonium during reductive stripping operations. Secondary objectives were to determine the solvent extraction behavior of feed solutions prepared by dissolving fuel from a boiling water reactor (BWR) and to improve the solvent extraction feed clarification.
Date: May 1, 1982
Creator: Collins, E.D.; Benker, D.E.; Bigelow, J.E.; Chattin, F.R.; King, L.J.; Ross, R.G. et al.
Partner: UNT Libraries Government Documents Department

Fabrication technological development of the oxide dispersion strengthened alloy MA957 for fast reactor applications

Description: A significant amount of effort has been devoted to determining the properties and understanding the behavior of the alloy MA957 to define its potential usefulness as a cladding material, in the fast breeder reactor program. The numerous characterization and fabrication studies that were conducted are documented in this report. The alloy is a ferritic stainless steel developed by International Nickel Company specifically for structural reactor applications. It is strengthened by a very fine, uniformly distributed yttria dispersoid. Its fabrication involves a mechanical alloying process and subsequent extrusion, which ultimately results in a highly elongated grain structure. While the presence of the dispersoid produces a material with excellent strength, the body centered cubic structure inherent to the material coupled with the high aspect ratio that results from processing operations produces some difficulties with ductility. The alloy is very sensitive to variations in a number of processing parameters, and if the high strength is once lost during fabrication, it cannot be recovered. The microstructural evolution of the alloy under irradiation falls into two regimes. Below about 550 C, dislocation development, {alpha}{prime} precipitation and void evolution in the matrix are observed, while above about 550 C damage appears to be restricted to cavity formation within oxide particles. The thermal expansion of the alloy is very similar to that of HT9 up to the temperature where HT9 undergoes a phase transition to austenitic. Pulse magnetic welding of end caps onto MA957 tubing can be accomplished in a manner similar to that in which it is performed on HT9, although the welding parameters appear to be very sensitive to variations in the tubing that result from small changes in fabrication conditions. The tensile and stress rupture behavior of the alloy are acceptable in the unirradiated condition, being comparable to HT9 below about 700 C and ...
Date: March 27, 2000
Creator: Hamilton, ML; Gelles, DS; Lobsinger, RJ; Johnson, GD; Brown, WF; Paxton, MM et al.
Partner: UNT Libraries Government Documents Department

Experiences with fast breeder reactor education in laboratory and short course settings

Description: The breeder reactor industry throughout the world has grown impressively over the last two decades. Despite the uncertainties in some national programs, breeder reactor technology is well established on a global scale. Given the magnitude of this technological undertaking, there has been surprisingly little emphasis on general breeder reactor education - either at the university or laboratory level. Many universities assume the topic too specialized for including appropriate courses in their curriculum - thus leaving students entering the breeder reactor industry to learn almost exclusively from on-the-job experience. The evaluation of four course presentations utilizing visual aids is presented.
Date: January 17, 1983
Creator: Waltar, A.E.
Partner: UNT Libraries Government Documents Department

Gas chromatograph system for sodium cover gas service

Description: The requirements are presented for the application engineering, materials, quality asaurance, fabrication, examination acceptance testing and delivery of a gas chromatograph system (including analyzer section and control and readout section) for the continuous on-line measurement of trace impurities in the inert gas used as a cover for liquid sodium. The cover gas sample delivered to the gas chromatograph systemn shall not exceed 1 ppm of sodium vapor. (auth)
Date: November 1, 1973
Partner: UNT Libraries Government Documents Department

Heat pipe thermal control of irradiation capsules

Description: From 1st international heat pipe conference; Stuttgart, F.R. Germany (15 Oct 1973). The use of heat pipes to control the temperature of irradiation capsules containing fast breeder reactor structural materials is discussed. (TFD)
Date: April 30, 1974
Creator: Deverall, J.E.
Partner: UNT Libraries Government Documents Department

Electromagnetic self-excitation effects in liquid metal cooled reactors

Description: For Westinghouse Hanford Co., Richland, Wash. Electromagnetic self- excitation effect is a posaible problem in LMFBR's. Geometry and flow parameters may rule it out; the magnetic Reynolds number criterion does not. The components in which the electromagnetic self-excitation effect may occur in liquid metal loops are analyzed. The conditions required for the occurrence of the effect and its consequences are described. (auth)
Date: December 1, 1973
Creator: Lessor, D.L.
Partner: UNT Libraries Government Documents Department

Plutonium flowsheet development in miniature mixer-settlers

Description: Initial runs were completed in a new solvent extraction facility that has been built for testing coprocessing flowsheets with simulated LWR and FBR fuel solutions. The equipment, which is assembled in glove boxes, includes three 16-stage miniature mixer-settler banks with associated in-line monitors, pumping equipment, and sampling apparatus. Following shakedown runs with solutions containing uranium only, two flowsheet test runs were made with a simulated LWR fuel solution (U/Pu = 100). The solution was fed to an extraction-scrub bank, where 30% tributyl phosphate in normal paraffin hydrocarbon diluent was used to coextract uranium and plutonium. The extract was fed to a second mixer-settler bank, where all of the plutonium was stripped into an aqueous product stream using hydroxylamine nitrate for plutonium reduction; a controlled fraction of the uranium was simultaneously stripped to produce a U/Pu ratio of {similar_to}2. The amount of the uranium stripped with the plutonium was regulated by careful control of an organic backscrub stream. Finally, the residual uranium in the solvent was stripped in the third mixer-settler bank. The success of the experiments depended on precise control of very low liquid flow rates, and on in-line monitors which indicated the uranium or total heavy-metal concentrations. The most useful in-line device was the Mettler-Paar density meter, from which metal concentrations could be determined to within {similar_to}1 g/L. A miniature spectrophotometer also gave promising results for uranium analysis. Preliminary use of a Hewlett-Packard data acquisition system was satisfactory; recorded variables were temperature, solution density, liquid flow rates, and liquid levels.
Date: May 1, 1981
Creator: Hannaford, B.A. & Davis, G.D.
Partner: UNT Libraries Government Documents Department