Neutronic evaluation of GCFR core diluents and reflectors

Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2003.

Bibliographic Details
Main Author: Yu, Kun, 1974-
Other Authors: Michael J. Driscoll.
Format: Thesis
Language:eng
Published: Massachusetts Institute of Technology 2005
Subjects:
Online Access:http://hdl.handle.net/1721.1/17045
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author Yu, Kun, 1974-
author2 Michael J. Driscoll.
author_facet Michael J. Driscoll.
Yu, Kun, 1974-
author_sort Yu, Kun, 1974-
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description Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2003.
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spelling mit-1721.1/170452022-01-25T21:15:57Z Neutronic evaluation of GCFR core diluents and reflectors Neutronic evaluation of Gas-Cooled Fast Reactor core diluents and reflectors Yu, Kun, 1974- Michael J. Driscoll. Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Massachusetts Institute of Technology. Department of Nuclear Engineering Massachusetts Institute of Technology. Department of Nuclear Science and Engineering Nuclear Engineering. Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2003. Includes bibliographical references (p. 67-68). This electronic version was submitted by the student author. The certified thesis is available in the Institute Archives and Special Collections. 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. by Kun Yu. S.M. 2005-05-19T15:46:52Z 2005-05-19T15:46:52Z 2003 2003 Thesis http://hdl.handle.net/1721.1/17045 54977617 eng 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. http://dspace.mit.edu/handle/1721.1/7582 78 p. 677231 bytes 676986 bytes application/pdf application/pdf application/pdf Massachusetts Institute of Technology
spellingShingle Nuclear Engineering.
Yu, Kun, 1974-
Neutronic evaluation of GCFR core diluents and reflectors
title Neutronic evaluation of GCFR core diluents and reflectors
title_full Neutronic evaluation of GCFR core diluents and reflectors
title_fullStr Neutronic evaluation of GCFR core diluents and reflectors
title_full_unstemmed Neutronic evaluation of GCFR core diluents and reflectors
title_short Neutronic evaluation of GCFR core diluents and reflectors
title_sort neutronic evaluation of gcfr core diluents and reflectors
topic Nuclear Engineering.
url http://hdl.handle.net/1721.1/17045
work_keys_str_mv AT yukun1974 neutronicevaluationofgcfrcorediluentsandreflectors
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