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11	Performance evaluation of coprocessed light water reactor fuel Patrashakorn, Sunanta January 1979 (has links) No description available. Reactor fuel reprocessing. Nuclear fuels. Actinide elements.
12	Definition and characterization of non high-level waste in the thorium fuel cycle Parker, Steven Ray January 1979 (has links) No description available. Reactor fuel reprocessing. Nuclear fuels -- Breeding. Thorium.
13	An economic evaluation of the recovery of krypton and xenon from nuclear fuels reprocessing plants Boyum, Bruce Montgomery, 1947- January 1971 (has links) No description available. Reactor fuel reprocessing. Gases -- Liquefaction. Xenon. Krypton.
14	Acidic high-level liquid waste processing for improved management, actinide product utilization and fuel safeguards Hubert, Richard Gregory 12 1900 (has links) No description available. Nuclear fuels Extraction (Chemistry) Reactor fuel reprocessing
15	Safety characteristics of a suspended-pellet fission reactor system / Kingdon, David Ross. January 1998 (has links) Thesis (Ph.D.) -- McMaster University, 1998. / Includes bibliographical references (p. 185-197). Also available via World Wide Web.
16	Material flow simulation in a nuclear chemical process Mahgerefteh, Moussa January 1984 (has links) At a nuclear fuel reprocessing plant the special nuclear materials (SNM) are received as constituents of spent fuel assemblies, are converted to liquid form, and undergo a series of chemical processes. Uncertainties in measurements of SNM at each stage of reprocessing limit the accuracy of simple material balance accounting as a safeguards method. To be effective, a formal safeguards program must take into account all sources of measurement error yet detect any diversion of SNM. The objective of this study is to demonstrate an analytical method for assessing the accountability of selected constituent SNM. A combined discrete-continuous, time-dependent model using the GASP IV simulation language is developed to simulate mass flow, material accountability and measurement error at each stage of the reprocessing plant. The study demonstrates that the simulation method may be utilized to estimate the magnitude of SNM loss in an operating reprocessing plant which could reasonably be detected. Thus, the simulation method provides a level of confidence for effective loss/no-loss decisions. / Ph. D. LD5655.V856 1984.M333 Nuclear fuels
17	MULTIATTRIBUTE UTILITY ASSESSMENT FOR AN INTERDISCIPLINARY SYSTEM DESIGN PROJECT: EVALUATING SITES FOR NUCLEAR FUEL REPROCESSING Breddan, Joseph January 1978 (has links) No description available.
18	Development of a novel monolith froth reactor for three-phase catalytic reactions / Crynes, Lawrence Lee. January 1993 (has links) Thesis (Ph.D.)--University of Tulsa, 1993. / Five colored photographs glued in book. Includes bibliographical references.
19	Greenwood Fuel Recycle Facility preliminary feasibility study of a nuclear fuel reprocessing and MOX fuel fabrication plant at the Greenwood Energy Center : economic and technical concerns / Berg, Raymond M. January 1976 (has links) Thesis (M.S.)--University of Michigan, 1976.
20	International management of spent fuel storage : technical alternatives and constraints, topical report Miller, Marvin M. January 1978 (has links) Some of the important technical issues involved in the implementation of a spent fuel storage regime under international auspices are discussed. In particular, we consider: the state of the art as far as the different possible storage modes are concerned, the relevant accident, sabotage, and transportation considerations, and the impact of recent technical spent fuel safeguards initiatives on the nonproliferation rationale for international spent fuel management. / Prepared for the U.S. Dept. of Energy under Contract no. EN-77-S-02-4571.A000. Radioactive waste disposal

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