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The Global ETD Search service is a free service for researchers
to find electronic theses and dissertations. This service is
provided by the
Networked Digital Library of Theses and Dissertations.
Our metadata is collected from universities around the world. If you manage a university/consortium/country archive and want to be added, details can be found on the NDLTD website.
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Showing 11 to 20 of 46 (0.075 seconds)Spelling suggestions: "subject:"fuel preprocessing"" "subject:"quel preprocessing""
| 11 |
An optimal withdrawal policy for spent nuclear fuel from on-site storage /Swindle, David Wesley, January 1977 (has links)
Thesis (M.S.)--Virginia Polytechnic Institute and State University, 1977. / Vita. Abstract. Includes bibliographical references (leaves 122-124). Also available via the Internet.
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| 12 |
A dynamic multi-criteria analysis of spent-nuclear-fuel alternatives /Langham, Robert William, January 1978 (has links)
Thesis (Ph. D.)--Virginia Polytechnic Institute and State University, 1978. / Vita. Abstract. Includes bibliographical references (leaves 193-197). Also available via the Internet.
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| 13 |
PERFORMANCE CONSIDERATIONS OF NUCLEAR REACTOR ACTINIDE RECYCLE AS A WASTE MANAGEMENT ALTERNATIVEMurphy, Daniel John, 1944- January 1978 (has links)
No description available.
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| 14 |
Performance evaluation of coprocessed light water reactor fuelPatrashakorn, Sunanta January 1979 (has links)
No description available.
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| 15 |
Definition and characterization of non high-level waste in the thorium fuel cycleParker, Steven Ray January 1979 (has links)
No description available.
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| 16 |
An economic evaluation of the recovery of krypton and xenon from nuclear fuels reprocessing plantsBoyum, Bruce Montgomery, 1947- January 1971 (has links)
No description available.
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| 17 |
Acidic high-level liquid waste processing for improved management, actinide product utilization and fuel safeguardsHubert, Richard Gregory 12 1900 (has links)
No description available.
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| 18 |
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.
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| 19 |
Material flow simulation in a nuclear chemical processMahgerefteh, 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.
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| 20 |
MULTIATTRIBUTE UTILITY ASSESSMENT FOR AN INTERDISCIPLINARY SYSTEM DESIGN PROJECT: EVALUATING SITES FOR NUCLEAR FUEL REPROCESSINGBreddan, Joseph January 1978 (has links)
No description available.
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