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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    Background

    Heat pipe cooled reactor (HPR) has many characteristics, such as reliability, inherent safety, small volume, modularity, and solid core. The nuclear fuel of solid core is seriously affected by high temperature, strong irradiation, and solid constraint when operating, which affect the heat transfer performance and mechanical properties of the core seriously. The stress and gap heat transfer caused by the contact between monolith and other components change nonlinearly with the increase of burnup, and they influence each other. Therefore, the coupled irradiation-thermal-mechanical behavior of the monolith is a complex multi-physics phenomena.

    Purpose

    This study aims to develop a coupled irradiation-thermal-mechanical model to explore the characteristics of gap variation, heat transfer and mechanics during the lifetime of solid core.

    Methods

    First of all, based on the geometric parameter and material of a typical solid core of HPR with fuel rod composed of UO2 pellets and 316 stainless steel cladding, a coupled irradiation-thermal-mechanical model was developed and applied to the finite element multi-physics field analysis software COMSOL. The calculation parameter settings mainly referred to the design parameters of the MegaPower reactor. Then, a thermal conductivity model changing with the increase of burnup for UO2, the gap heat transfer model and mechanical contact were introduced in the gaps in the solid core, and both irradiation-induced deformation effect including densification and fission product swelling, and creep effect of UO2 pellets and 316 stainless steel monolith were taken into account. Finally, the model was applied to calculating the typical HPR and the characteristics of gap variation, heat transfer and mechanics were analyzed.

    Results

    Analysis results show that pellet temperature and creep of monolith and cladding increase after complete contact between monolith and cladding. A smaller average number of heat pipes around the fuel rod result in higher temperature and stress distribution in the nearby area, and the cladding in this area has a risk of creep failure during its lifetime caused by internal pressure of the fuel rod and contact pressure between the monolith and cladding.

    Conclusions

    The gap contact can affect the heat transfer and mechanical properties of the solid core of HPR, and even result in an increase in the risk of cladding failure.

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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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