Investigation on irradiated-thermal-mechanical coupling performance and failure behaviors of TRISO particle fuel for space reactor applications

IF 3.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Progress in Nuclear Energy Pub Date : 2025-02-01 DOI:10.1016/j.pnucene.2025.105633
Lin Peng , Yuan Yang , Songyang Li , Zhonghao Nong , Simiao Tang
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Abstract

TRISO particles, recognized for their excellent ability to retain fission products and maintain structural integrity, are crucial candidates for space reactor applications. However, current studies primarily focus on conventional reactor conditions, leaving gaps in understanding their performance under the more demanding conditions of space reactors. This study aims to address these gaps by developing a thermal-mechanical coupling simulation for TRISO particles using the finite element method, incorporating comprehensive material properties, irradiation behaviors and fission gas release. The model was validated through tangential stress comparison in IAEA CRP-6 Case 8 and further verified with TRISO particle calculation results from the BISON code, demonstrating the reliability of the simulation and the accuracy of the model. Under space reactor conditions, the higher kernel power, prolonged fuel lifetime, and increased fission gas pressure significantly elevate the tensile stress in the CVD-SiC layer, raising its failure probability at the later stages of burnup. While the SiC layer remains highly reliable under conventional HTGR conditions, its failure probability under space reactor conditions may become substantial. Sensitivity analysis was conducted by varying five key parameters. The results revealed that higher temperatures, greater fission rates, and extended operation times significantly increase the buffer-IPyC gas pressure, posing the greatest challenge to TRISO particle performance in space reactors. These findings reveal the greatest challenges for TRISO particles in space reactors compared to conventional reactors and underscore the necessity of enhancing their designs to ensure reliability and structural integrity in space reactor applications.
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来源期刊
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
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