NUCLEAR TECHNIQUES, Volume. 47, Issue 7, 070601(2024)

Coupled irradiation-thermal-mechanical analysis of fuel in solid core of heat pipe cooled reactor

Xuan YANG1, Quan LI2, Chenxi LI2, Jing ZHANG1、*, Yingwei WU1、**, Yanan HE1, Kailun GUO1, Guanghui SU1, Wenxi TIAN1, and Suizheng QIU1
Author Affiliations
  • 1School of Energy and Power Engineering, Xi'an Jiaotong University, Xi'an 710049, China
  • 2Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China
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    References(17)

    [6] LU Huaiyu, TANG Changbing, LI Yuanming et al. Numerical study on radiation-thermal-mechanical behavior of fuel rods in heat pipe reactor[J]. China Steel Focus, 38-39(2020).

    [15] Fancher R B, Fiero I B, Freeburn H R et al. ESCORE: the EPRI steady-state core reload evaluator code: General description[R](1987).

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    Xuan YANG, Quan LI, Chenxi LI, Jing ZHANG, Yingwei WU, Yanan HE, Kailun GUO, Guanghui SU, Wenxi TIAN, Suizheng QIU. Coupled irradiation-thermal-mechanical analysis of fuel in solid core of heat pipe cooled reactor[J]. NUCLEAR TECHNIQUES, 2024, 47(7): 070601

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    Paper Information

    Category: Research Articles

    Received: Dec. 28, 2023

    Accepted: --

    Published Online: Aug. 27, 2024

    The Author Email: ZHANG Jing (章静), WU Yingwei (巫英伟)

    DOI:10.11889/j.0253-3219.2024.hjs.47.070601

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