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    Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002::page 21006
    Author:
    Yang, Xie
    ,
    She, Ding
    ,
    Shi, Lei
    DOI: 10.1115/1.4038774
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Due 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.
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      Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts

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    http://yetl.yabesh.ir/yetl1/handle/yetl/4252635
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    contributor authorYang, Xie
    contributor authorShe, Ding
    contributor authorShi, Lei
    date accessioned2019-02-28T11:05:49Z
    date available2019-02-28T11:05:49Z
    date copyright3/5/2018 12:00:00 AM
    date issued2018
    identifier issn2332-8983
    identifier otherners_004_02_021006.pdf
    identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252635
    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.
    publisherThe American Society of Mechanical Engineers (ASME)
    titleNeutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts
    typeJournal Paper
    journal volume4
    journal issue2
    journal titleJournal of Nuclear Engineering and Radiation Science
    identifier doi10.1115/1.4038774
    journal fristpage21006
    journal lastpage021006-5
    treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002
    contenttypeFulltext
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