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  • About
  • 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.
1

The role of plutonium-238 in nuclear fuel cycles

Massey, John Victor 05 1900 (has links)
No description available.
2

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.
3

The irradiation effects on the solvent extraction system of tributyl phosphate-dodecane

Holland, Joe Paschal January 2011 (has links)
Typescript. / Digitized by Kansas Correctional Industries
4

Nuclear fuel reprocessing plant radioactive airborne effluents sources and treatment

Roles, Gary William January 1978 (has links)
No description available.
5

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 LMFBRs

Lee, Chung-Chiang Patrick 12 1900 (has links)
No description available.
6

The use of organophosphorus extractants in f-element separations

Braley, 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).
7

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.
8

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.
9

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.
10

Criticality safety analysis of the design of spent fuel cask, its manipulation and placement in a long-term storage

Leotlela, 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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