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ZHANG Ying chao, CHEN Peng (China Institute of Atomic Energy, P.O. Box 275 64, Beijing 102413, China). Analysis of PCMI Threshold of Fuel Rod for Qinshan Nuclear Power Plant[J]. Atomic Energy Science and Technology, 2000, 34(S1): 86-86. DOI: 10.7538/yzk.2000.34.S1.0086
Citation: ZHANG Ying chao, CHEN Peng (China Institute of Atomic Energy, P.O. Box 275 64, Beijing 102413, China). Analysis of PCMI Threshold of Fuel Rod for Qinshan Nuclear Power Plant[J]. Atomic Energy Science and Technology, 2000, 34(S1): 86-86. DOI: 10.7538/yzk.2000.34.S1.0086
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Analysis of PCMI Threshold of Fuel Rod for Qinshan Nuclear Power Plant

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  • The Japanese fuel behavior analysis code FEMAXI Ⅳ provided by OECD is used to calculate the stress level of Qinshan Nuclear Power Plant fuel rod under pellet clad mechanical interaction (PCMI) and to evaluate the safety margin of PCMI. The threshold of rod power is obtained after the determination of threshold of local hoop stress. The safety margin of linear power is 147 W/cm and the safety margin of local hoop stress is 263 MPa under the accident condition of unanticipated control rod withdrawing according to the threshold.
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