Thermo-mechanical response of SiCf/SiC composite cladding: Effect of loss-of-coolant accident duration

IF 3.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Shuang Liang , Chong Wei , Bowen Qiu , Cheng Zhang , Haoyu Liao , Xingjie Ren , Zhong Xiao
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引用次数: 0

Abstract

SiCf/SiC composite is one of the candidate materials for fuel cladding in Generation IV advanced nuclear reactors. However, there are still few risks under accident conditions, such as large physical property changes and poor thermal conductivity, the performance of the cladding remains to be studied especially in extreme accident conditions (loss-of-coolant accident, LOCA and reactivity-insertion accident, RIA). In this study, the thermo-mechanical responses of SiCf/SiC composite cladding under different LOCA durations were investigated by a meso-macroscopic coupling finite element simulation method. At mesoscopic scale, we present a mathematical model between the longitudinal tensile ultimate strength and temperature (200K∼2000K), which enables us to define the failure of macroscopic cladding. At macroscopic scale, the established mathematical model was applied to the failure analysis of macroscopic cladding, then the temperature and hoop stress of the inner and outer surfaces of the cladding were studied under different LOCA durations of 200s, 300s and 400s. The results showed that under LOCA condition, the hoop stress difference between the inner and external surfaces of the SiCf/SiC composite cladding increases about 200% compared with that under normal service conditions. Meanwhile, the hoop stress difference increases slowly with the increase of LOCA duration, and the maximum increment can reach about 2.8%. In addition, the peak temperature increases with the increase of LOCA duration, which the maximum increment can reach about 5.6%, while the peak temperature difference between the inner and external surfaces increases slowly with the increase of LOCA duration, and the maximum increment can reach about 5.1%.
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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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