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.
Skip Nav Destination
Article navigation
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: [email protected]
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: [email protected]
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: [email protected]
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: [email protected]
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: [email protected]
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: [email protected]
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: [email protected]
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: [email protected]
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: [email protected]
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: [email protected]
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: [email protected]
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: [email protected]
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
Download citation file:
127
Views
Get Email Alerts
Cited By
Reviewer's Recognition
ASME J of Nuclear Rad Sci (July 2025)
Study of TRICO II Reactor Startup and Shutdown Operations Using the OpenMC Calculation Code
ASME J of Nuclear Rad Sci (July 2025)
Adjuster Absorber Rods Return to Service at PLNGS
ASME J of Nuclear Rad Sci (July 2025)
Related Articles
PBMR-A Future Failsafe Gas Turbine Nuclear Power Plant?
Mechanical Engineering (August,2011)
Handbook of Generation-IV Nuclear Reactors
ASME J of Nuclear Rad Sci (April,2017)
Irradiation Issues and Material Selection for Canadian SCWR Components
ASME J of Nuclear Rad Sci (July,2018)
Analyses of the Load Following Capabilities of Brayton Helium Gas Turbine Cycles for Generation IV Nuclear Power Plants
ASME J of Nuclear Rad Sci (October,2017)
Related Proceedings Papers
Related Chapters
Fissioning, Heat Generation and Transfer, and Burnup
Fundamentals of Nuclear Fuel
New Generation Reactors
Energy and Power Generation Handbook: Established and Emerging Technologies
Studies Performed
Closed-Cycle Gas Turbines: Operating Experience and Future Potential