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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April 2018
Research-Article
Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts
Xie Yang,
Xie Yang
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
e-mail: yxheneng@163.com
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
e-mail: yxheneng@163.com
Search for other works by this author on:
Ding She,
Ding She
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
e-mail: sheding@tsinghua.edu.cn
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
e-mail: sheding@tsinghua.edu.cn
Search for other works by this author on:
Lei Shi
Lei Shi
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
e-mail: shlinet@tsinghua.edu.cn
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
e-mail: shlinet@tsinghua.edu.cn
Search for other works by this author on:
Xie Yang
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
e-mail: yxheneng@163.com
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
e-mail: yxheneng@163.com
Ding She
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
e-mail: sheding@tsinghua.edu.cn
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
e-mail: sheding@tsinghua.edu.cn
Lei Shi
Key Laboratory of Advanced Reactor Engineering
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
e-mail: shlinet@tsinghua.edu.cn
and Safety of Ministry of Education,
Collaborative Innovation Center of
Advanced Nuclear Energy Technology,
Institute of Nuclear and New Energy Technology,
Tsinghua University,
Beijing 100084, China
e-mail: shlinet@tsinghua.edu.cn
Manuscript received September 25, 2017; final manuscript received November 24, 2017; published online March 5, 2018. Assoc. Editor: Leon Cizelj.
ASME J of Nuclear Rad Sci. Apr 2018, 4(2): 021006 (5 pages)
Published Online: March 5, 2018
Article history
Received:
September 25, 2017
Revised:
November 24, 2017
Citation
Yang, X., She, D., and Shi, L. (March 5, 2018). "Neutronics Analysis of Small Compact Prismatic Nuclear Reactors for Space Crafts." ASME. ASME J of Nuclear Rad Sci. April 2018; 4(2): 021006. https://doi.org/10.1115/1.4038774
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