Preliminary neutronics design and analysis of lithium heat pipe cooled space reactor with low-enriched uranium

Xiaoliang Zou; Yanting Sun; Qiusun Zeng; Xiaojian Wen; Xiaogang Cao; Xi Huang; Yibao Liu

Nuclear Engineering and Technology (Dec 2024)

Preliminary neutronics design and analysis of lithium heat pipe cooled space reactor with low-enriched uranium

Xiaoliang Zou,
Yanting Sun,
Qiusun Zeng,
Xiaojian Wen,
Xiaogang Cao,
Xi Huang,
Yibao Liu

Affiliations

Xiaoliang Zou: Department of Nuclear Science and Engineering, East China University of Technology, Nanchang, Jiangxi, 330013, China; Jiangxi Engineering Technology Research Center of Nuclear Radiation Detection and Application, East China University of Technology, Nanchang, Jiangxi, 330013, China
Yanting Sun: Department of Nuclear Science and Engineering, East China University of Technology, Nanchang, Jiangxi, 330013, China; Jiangxi Engineering Technology Research Center of Nuclear Radiation Detection and Application, East China University of Technology, Nanchang, Jiangxi, 330013, China; Corresponding author. Department of Nuclear Science and Engineering, East China University of Technology, Nanchang, Jiangxi, 330013, China.
Qiusun Zeng: Institute of Nuclear Energy Safety Technology, Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei, 230031, China
Xiaojian Wen: Department of Nuclear Science and Engineering, East China University of Technology, Nanchang, Jiangxi, 330013, China; Jiangxi Engineering Technology Research Center of Nuclear Radiation Detection and Application, East China University of Technology, Nanchang, Jiangxi, 330013, China
Xiaogang Cao: Department of Nuclear Science and Engineering, East China University of Technology, Nanchang, Jiangxi, 330013, China; Jiangxi Engineering Technology Research Center of Nuclear Radiation Detection and Application, East China University of Technology, Nanchang, Jiangxi, 330013, China
Xi Huang: Department of Nuclear Science and Engineering, East China University of Technology, Nanchang, Jiangxi, 330013, China; Jiangxi Engineering Technology Research Center of Nuclear Radiation Detection and Application, East China University of Technology, Nanchang, Jiangxi, 330013, China
Yibao Liu: Department of Nuclear Science and Engineering, East China University of Technology, Nanchang, Jiangxi, 330013, China; Jiangxi Engineering Technology Research Center of Nuclear Radiation Detection and Application, East China University of Technology, Nanchang, Jiangxi, 330013, China

Journal volume & issue: Vol. 56, no. 12
pp. 5330 – 5338

Abstract

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The space nuclear reactor cooled by heat pipes has become the preferred choice for future space missions and deep space exploration missions. The use of low-enriched uranium (LEU) is promoted to achieve the goal of nuclear non-proliferation worldwide. In this study, a lithium heat pipe cooled space reactor with LEU (HP-LEU) was proposed based on Heat Pipes-Segmented Thermoelectric Module Converters (HP-STMCs), with the addition of moderators. The HP-LEU employs yttrium hydride (YH2) as the moderator and 19.9 % enriched uranium nitride (UN) as the fuel. The neutronics analysis has been performed on the HP-LEU reactor and the results have showed that the HP-LEU has a lifetime of more than 12 years. Two control systems have been applied in the reactor and have demonstrated the capacity to independently regulate and shut down the reactor. The total temperature reactivity coefficients are consistently negative, indicating that the HP-LEU reactor is inherently safe during operation. During normal operation, the temperatures of the materials are all acceptable. This study can serve as a reference for lithium heat pipe cooled space reactors with LEU.

Published in Nuclear Engineering and Technology

ISSN: 1738-5733 (Print)
Publisher: Elsevier
Country of publisher: Korea, Republic of
LCC subjects: Technology: Electrical engineering. Electronics. Nuclear engineering: Nuclear engineering. Atomic power
Website: http://www.journals.elsevier.com/nuclear-engineering-and-technology

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