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dc.contributor.authorYang, Xie
dc.contributor.authorShe, Ding
dc.contributor.authorShi, Lei
dc.date.accessioned2019-02-28T11:05:49Z
dc.date.available2019-02-28T11:05:49Z
dc.date.copyright3/5/2018 12:00:00 AM
dc.date.issued2018
dc.identifier.issn2332-8983
dc.identifier.otherners_004_02_021006.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252635
dc.description.abstractDue to the advantages of small volume, light weight, and long-time running, nuclear reactor can provide an ideal energy source for space crafts. In this paper, two small compact prismatic nuclear reactors with different core block materials are presented, which have a thermal power of 5 MW for 10 years of equivalent full power operation. These two reactors use Mo-14%Re alloy or nuclear grade graphite IG110 as core block material, loaded with 50% and 39.5% enriched uranium nitride (UN) fuel and cooled by helium, whose inlet/outlet temperature of the reactor and operational pressure are 850/1300 K and 2 MPa, respectively. High temperature helium flowing out of the reactor can be used as the working medium for closed Brayton cycle power conversion with high efficiency (more than 20%). Neutronics analyses of reactors for the preliminary design in this paper are performed using reactor Monte Carlo (RMC) code developed by Tsinghua University. Both the reactors have enough initial excess reactivity to ensure 10 years of full power operation without refueling, have safety margin for reactor shutdown with one control drum failed, and remain subcritical in the submersion accident. Finally, the two reactors are compared in aspect of the 235U mass and the total reactor mass.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleNeutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts
dc.typeJournal Paper
dc.journal.volume4
dc.journal.issue2
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4038774
dc.journal.fristpage21006
dc.journal.lastpage021006-5
dc.treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002
dc.contenttypeFulltext


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