Researching | Irradiation-induced swelling of U-Mo fuel for heat-pipe reactor under high temperature

NUCLEAR TECHNIQUES, Volume. 47, Issue 11, 110601(2024)

Irradiation-induced swelling of U-Mo fuel for heat-pipe reactor under high temperature

Qinwen YAO, Xitong GUAN, Quan CHENG, Jigao DAI, Yuanfang ZOU, Xiaojun HE^*, and Aimin ZHANG

Author Affiliations

Department of Reactor Engineering Technology, China Institute of Atomic Energy, Beijing 102413, China

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References(20)

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[5] Gibson M, Poston D, Mcclure P et al. Kilopower reactor using stirling technology (KRUSTY) nuclear ground test results and lessons learned[R](2018).

[6] Poston D I, Gibson M A, Godfroy T et al. KRUSTY reactor design[J]. Nuclear Technology, 206, S13-S30(2020).

[7] Gibson M A, Oleson S R, Poston D I et al. NASA's Kilopower reactor development and the path to higher power missions[C], 1-14(2017).

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[9] CHAI Xiaoming, MA Yugao, HAN Wenbin et al. Coupled three-dimensional neutronic/thermal-mechanical analysis of heat pipe cooled reactor solid-state core[J]. Atomic Energy Science and Technology, 55, 189-195(2021).

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[11] Xiao H X, Long C S, Tian X F et al. Atomistic simulations of the small xenon bubble behavior in U–Mo alloy[J]. Materials & Design, 74, 55-60(2015).

[12] Robinson A B, Williams W J, Hanson W A et al. Swelling of U-Mo monolithic fuel: developing a predictive swelling correlation under research reactor conditions[J]. Journal of Nuclear Materials, 544, 152703(2021).

[13] ZHOU Bangxin[M]. Nuclear reactor materials(2021).

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Qinwen YAO, Xitong GUAN, Quan CHENG, Jigao DAI, Yuanfang ZOU, Xiaojun HE, Aimin ZHANG. Irradiation-induced swelling of U-Mo fuel for heat-pipe reactor under high temperature[J]. NUCLEAR TECHNIQUES, 2024, 47(11): 110601

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Paper Information

Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING

Received: Apr. 16, 2024

Accepted: --

Published Online: Jan. 2, 2025

The Author Email: HE Xiaojun (HEXiaojun)

DOI:10.11889/j.0253-3219.2024.hjs.47.110601

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