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Neutronic evaluation of GCFR core diluents and reflectors

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dc.contributor.advisor Michael J. Driscoll. en_US
dc.contributor.author Yu, Kun, 1974- en_US
dc.contributor.other Massachusetts Institute of Technology. Dept. of Nuclear Engineering. en_US
dc.date.accessioned 2005-05-19T15:46:52Z
dc.date.available 2005-05-19T15:46:52Z
dc.date.copyright 2003 en_US
dc.date.issued 2003 en_US
dc.identifier.uri http://hdl.handle.net/1721.1/17045
dc.description Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2003. en_US
dc.description Includes bibliographical references (p. 67-68). en_US
dc.description This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections. en_US
dc.description.abstract Materials are evaluated for use as in-core diluents and as peripheral reflectors for Gas-Cooled Fast Reactor (GFR) service, using coupled Monte Carlo (MCNP) and isotopics (ORIGEN) codes. The principal performance indices compared were effects on beginning of irradiation multiplication factor, reactivity-lineated burnup, and coolant (here CO2) void reactivity. While low values of the macroscopic absorption cross section, [Sigma]a, and slowing down power, [xi] [Sigma]s, are qualitatively useful predictors of good performance, it was found that only full scope calculations were valid for quantitative assessment. For example, several materials (Ni, Nb) having poor performance as in-core diluents proved to be good reflectors. Many materials which reduced coolant void reactivity also proved detrimental to reactivity lifetime. Others, mostly the strong moderators, increased initial reactivity, but decreased reactivity lifetime. Cores fueled with plutonium exhibited a much larger void reactivity than those started up using U-235 as the fissile material. While there are no ideal candidates that are superior in all respects, considering only neutronic performance, the following appear worthy of further investgation: Metallic fuel diluents or matrices (eg. CERMET or METMET): Zr, Ti, V, Ba2Pb; High temperature fuel diluents or matrices (eg, CERMET, CERCER): SiC, BaS Cladding: Fe alloys with Cr, Al (eg ODS) Reflector: Zr3Si2, Pb, Ba2Pb, ZrS2, MoSi2 plus a variety of sulfides and silicides. en_US
dc.description.statementofresponsibility by Kun Yu. en_US
dc.format.extent 78 p. en_US
dc.format.extent 677231 bytes
dc.format.extent 676986 bytes
dc.format.mimetype application/pdf
dc.format.mimetype application/pdf
dc.language.iso eng en_US
dc.publisher Massachusetts Institute of Technology en_US
dc.rights M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission. en_US
dc.rights.uri http://dspace.mit.edu/handle/1721.1/7582
dc.subject Nuclear Engineering. en_US
dc.title Neutronic evaluation of GCFR core diluents and reflectors en_US
dc.title.alternative Neutronic evaluation of Gas-Cooled Fast Reactor core diluents and reflectors en_US
dc.type Thesis en_US
dc.description.degree S.M. en_US
dc.contributor.department Massachusetts Institute of Technology. Dept. of Nuclear Engineering. en_US
dc.identifier.oclc 54977617 en_US


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