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The role of plutonium-238 in nuclear fuel cyclesMassey, John Victor 05 1900 (has links)
No description available.
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Influence of temperature on the extraction of Pu(IV) by tri-n-butyl phosphate from acidic nitrate solutions /Brown, M. Alex. January 1900 (has links)
Thesis (M.S.)--Oregon State University, 2010. / Printout. Includes bibliographical references (leaves 43-45). Also available on the World Wide Web.
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The irradiation effects on the solvent extraction system of tributyl phosphate-dodecaneHolland, Joe Paschal January 2011 (has links)
Typescript. / Digitized by Kansas Correctional Industries
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Nuclear fuel reprocessing plant radioactive airborne effluents sources and treatmentRoles, Gary William January 1978 (has links)
No description available.
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Optimization of breeding performance for metallic Pu-Th, U[superscript]233-Th, U[superscript]233-U[superscript]238 and for (Pu-U)0[subscript]2 fuels in LMFBRsLee, Chung-Chiang Patrick 12 1900 (has links)
No description available.
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The use of organophosphorus extractants in f-element separationsBraley, Jenifer Claire. January 2010 (has links) (PDF)
Thesis (Ph. D.)--Washington State University, August 2010. / Title from PDF title page (viewed on July 21, 2010). "Department of Chemistry." Includes bibliographical references (p. 217-218).
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The chemistry of acetohydroxamic acid related to nuclear fuel reprocessing /Matteson, Brent Searle. January 1900 (has links)
Thesis (Ph. D.)--Oregon State University, 2011. / Printout. Includes bibliographical references (leaves 119-132). Also available on the World Wide Web.
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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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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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Criticality safety analysis of the design of spent fuel cask, its manipulation and placement in a long-term storageLeotlela, Mosebetsi Johannes 19 September 2016 (has links)
A thesis submitted to the Faculty of Science, University of the Witwatersrand, Johannesburg
in fulfilment of the requirements for the degree of Doctor of Philosophy. Johannesburg, 2015 / Spent nuclear fuel storage is gradually becoming a nightmare for nuclear reactors which were
commissioned in the 1980s. This leaves the nuclear facility management with the dilemma of
having to choose between pursuing the cask storage option to relieve the demand pressure on
the spent fuel pool, or to opt for the more radical but unpopular option of shutting down the
reactor compromising the energy supply, and South Africa is no exception. In a bid to
minimise the risk of reactor shut down, the Nuclear Analysis Section (NAS) of Eskom
launched the present study of investigating the design requirements of spent fuel casks
suitable for the storage and transportation of spent fuel assemblies that have an initial
enrichment of up to 5 wt% and much higher burnup of between 50 and 60 GWD/MTU.
The aim of the present study is to investigate the suitability of the existing casks for use in 5
wt% enriched fuel, given that they are licensed for a maximum enrichment of 3.5 wt%. As a
result of the huge number of casks required, there is potentially a risk of shortage of cask
storage space and, therefore, it was prudent that the study also investigates the most optimum
storage array that will maximise the storage space, while keeping the effective neutron
multiplication factor (keff) below the internationally recommended value of 0.95 [IAEA,
2014]. As such, it is also necessary to identify parameters which have the greatest effect on
the neutron multiplication factor. These include determining the effect of changes in
moderator and fuel temperature on the neutron multiplication factor and also what the effect
of an increase in the concentration in 10B of the boral plate will have on the neutron
multiplication factor. / M T 2016
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