Study on IVR Capability Margin of Pressurized Water Reactor Based on Decay Heat Uncertainty

Song Jian; Yu Hongxing; Deng Jian; Xiang Qingan; Zhu Dahuan; Xu Youyou; Luo Yuejian

doi:10.13832/j.jnpe.2021.06.0161

Volume 42 Issue 6

Dec. 2021

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Article Navigation > Nuclear Power Engineering > 2021 > 42(6): 161-166

Song Jian, Yu Hongxing, Deng Jian, Xiang Qingan, Zhu Dahuan, Xu Youyou, Luo Yuejian. Study on IVR Capability Margin of Pressurized Water Reactor Based on Decay Heat Uncertainty[J]. Nuclear Power Engineering, 2021, 42(6): 161-166. doi: 10.13832/j.jnpe.2021.06.0161

Citation:

Song Jian, Yu Hongxing, Deng Jian, Xiang Qingan, Zhu Dahuan, Xu Youyou, Luo Yuejian. Study on IVR Capability Margin of Pressurized Water Reactor Based on Decay Heat Uncertainty[J]. Nuclear Power Engineering, 2021, 42(6): 161-166. doi: 10.13832/j.jnpe.2021.06.0161

Citation:

Song Jian, Yu Hongxing, Deng Jian, Xiang Qingan, Zhu Dahuan, Xu Youyou, Luo Yuejian. Study on IVR Capability Margin of Pressurized Water Reactor Based on Decay Heat Uncertainty[J]. Nuclear Power Engineering, 2021, 42(6): 161-166. doi: 10.13832/j.jnpe.2021.06.0161

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Study on IVR Capability Margin of Pressurized Water Reactor Based on Decay Heat Uncertainty

doi: 10.13832/j.jnpe.2021.06.0161

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2020-09-23
Rev Recd Date: 2020-11-13
Publish Date: 2021-12-09

Abstract

Abstract

In order to determine the influence of decay heat on the IVR (In-Vessel Retention) capability margin of HPWR, an evaluation method combining significance level evaluation and sampling failure rate was used to evaluate IVR capability margin. Using CISER for IVR to carry out the sampling calculation, the ratio of the peak heat flux on the lower head wall to the local critical heat flux (CHF) under different power levels and decay heat distribution parameters of nuclear power plants was obtained to carry out the significance level estimation and failure rate calculation of the heat flux ratio to judge whether the IVR measure is effective based on the penetration criterion of lower head (less than local CHF) to obtain the IVR capability margin. The results show that IVR alone is not recommended as a serious accident mitigation measure for PWR plants with an electrical power of more than 1400 MW without any optimization of the heat transfer composition inside and outside the lower head.
- Decay heat,
- Critical heat flux (CHF),
- In-vessel retention (IVR),
- Sampling failure rate

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References(15)

References

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