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dc.contributor.authorStauff, Nicolas
dc.contributor.authorDriscoll, Michael J
dc.contributor.authorForget, Benoit Robert Yves
dc.contributor.authorHejzlar, Pavel
dc.date.accessioned2017-05-24T19:24:34Z
dc.date.available2017-05-24T19:24:34Z
dc.date.issued2010-06
dc.date.submitted2009-06
dc.identifier.issn0029-5450
dc.identifier.issn1943-7471
dc.identifier.urihttp://hdl.handle.net/1721.1/109322
dc.description.abstractBreeding blankets are of interest for a sodium fast reactor (SFR) as they allow for small cores to have positive breeding gains. However, because they breed very high-quality plutonium, core designers are not currently encouraged to employ blankets. After verifying that the ERANOS code was in good agreement with BGcore, a Monte Carlo-based depletion system, it was shown that an SFR blanket design could breed less attractive plutonium than light water reactor (LWR)-bred plutonium for making a nuclear explosive device. Minor actinide (MA) doping and moderator addition were the two options studied. This study shows that it is possible to build an SFR with a secure blanket with MA addition; at steady state MAs from approximately 1.5 LWRs are required per SFR [both rated at 1 GW(electric)].en_US
dc.language.isoen_US
dc.publisherAmerican Nuclear Societyen_US
dc.relation.isversionofhttp://dx.doi.org/10.13182/NT10-1en_US
dc.rightsCreative Commons Attribution-Noncommercial-Share Alikeen_US
dc.rights.urihttp://creativecommons.org/licenses/by-nc-sa/4.0/en_US
dc.sourceProf. Forget via Chris Sherratten_US
dc.titleResolution of Proliferation Issues for a Sodium Fast Reactor Blanketen_US
dc.typeArticleen_US
dc.identifier.citationStauff, N. E.; Driscoll, M. J.; Forget, B. and Hejzlar, P. “Resolution of Proliferation Issues for a Sodium Fast Reactor Blanket.” Nuclear Technology 170, no. 3 (June 2010): 371-382en_US
dc.contributor.departmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineeringen_US
dc.contributor.mitauthorStauff, Nicolas
dc.contributor.mitauthorDriscoll, Michael J
dc.contributor.mitauthorForget, Benoit Robert Yves
dc.contributor.mitauthorHejzlar, Pavel
dc.relation.journalNuclear Technologyen_US
dc.eprint.versionAuthor's final manuscripten_US
dc.type.urihttp://purl.org/eprint/type/JournalArticleen_US
eprint.statushttp://purl.org/eprint/status/PeerRevieweden_US
dspace.orderedauthorsStauff, N. E.; Driscoll, M. J.; Forget, B.; Hejzlar, P.en_US
dspace.embargo.termsNen_US
dc.identifier.orcidhttps://orcid.org/0000-0002-2919-2312
dc.identifier.orcidhttps://orcid.org/0000-0003-1459-7672
dc.identifier.orcidhttps://orcid.org/0000-0003-1715-3735
mit.licenseOPEN_ACCESS_POLICYen_US
mit.metadata.statusComplete


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