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in creator/contributor: "Leitz, F. J."  
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Compilation of data on composition of bismuth phosphate process metal wastes

Description: The available information on the ionic and radiochemical composition of current and aged bismuth phosphate process wastes is tabulated here for the convenience of those concerned with metal recovery. In addition to its application in the design of research and development experiments, the compilation may serve to suggest specific needs for additional analytical data. For convenience in chemical calculation, molar compositions have been calculated for the ionic constituents based on the g/1 valu… more
Date: August 15, 1949
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Ninth Quarterly Report, October-December 1963

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program. Information is reported on vented fuel production, fuel testing in TREAT, fuel performance evaluation, fast-flux irradiation of fuel, and reactor dynamics and design.
Date: January 1964
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Seventh Quarterly Report, April-June 1963

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: July 1963
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly report, January 1951--March 1951, Chemical Research Section

Description: The current Relox flowsheet proposes precipitation of plutonium peroxide from IIBP solution concentrated by evaporation to 10 g Pu/1 and ca. 5.5 M HNO{sub 3}. Such a solution might have an Al{sup +++} concentration as high as 0.02 M with stainless steel corrosion product concentrations of the order of magnitude of those found in AT solution diluted to 10 g Pu/l. Methods for the precipitation of plutonium peroxide from this type of solution, either with or without partial neutralization of the n… more
Date: April 16, 1951
Creator: Hill, O. F. & Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Core Design Study for a 500MWe Fast Oxide Reactor

Description: A 500 MWe sodium-cooled, PuO2-UO2 fuel, fast spectrum reactor design is presented, which is calculated to have a fuel cycle cost in the civinity of 1 mill/ekw hr, and to have important safety features due to an appreciably negative Doppler effect.
Date: December 28, 1961
Creator: Horst, K. M.; Hutchins, B. A.; Leitz, F. J. & Wolfe, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: August 15, 1963
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fourth Quarterly Report, July-September 1962

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: January 31, 1963
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fifth Quarterly Report, October-December 1962

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: January 1963
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Sixth Quarterly Report, January-March 1963

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: April 1963
Creator: Leitz, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Conceptual Design of a 300-Mwe Paste-Fueled Fast Breeder Power Reactor

Description: "This report describes the conceptual design of 300 Mwe fast breeder reactor power plant that utilizes a paste-fuel system consisting of small, spherical particles settled in sodium" (p. 7). It includes a discussion of the paste-fuel system, the design of the core and blanket structure with analysis, a description of the fuel-handling system, processes for fabricating and processing the fuel, and schematics.
Date: October 1961
Creator: Blessing, W. G.; Bowers, S. D.; Hennig, R. J.; Huebotter, P. R.; Jens, W. H.; Kovacic, E. C. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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