Analysis of Ex-Vessel Steam Explosion under RPV Side Break Cases

Chen Peng; Zhao Xinhai; Zhan Dekui; Xia Shaoxiong

doi:10.13832/j.jnpe.2022.01.0175

Volume 43 Issue 1

Feb. 2022

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Chen Peng, Zhao Xinhai, Zhan Dekui, Xia Shaoxiong. Analysis of Ex-Vessel Steam Explosion under RPV Side Break Cases[J]. Nuclear Power Engineering, 2022, 43(1): 175-182. doi: 10.13832/j.jnpe.2022.01.0175

Citation:

Chen Peng, Zhao Xinhai, Zhan Dekui, Xia Shaoxiong. Analysis of Ex-Vessel Steam Explosion under RPV Side Break Cases[J]. Nuclear Power Engineering, 2022, 43(1): 175-182. doi: 10.13832/j.jnpe.2022.01.0175

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Analysis of Ex-Vessel Steam Explosion under RPV Side Break Cases

doi: 10.13832/j.jnpe.2022.01.0175

China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, 518000, China

Received Date: 2020-11-23
Accepted Date: 2020-12-03
Rev Recd Date: 2021-11-05
Publish Date: 2022-02-01

Abstract

Abstract

The calculation and analysis of steam explosion were carried out for the pressure vessel (RPV) side breach conditions that are more likely to occur in the actual process. According to the Phenomena Identification and Ranking Table (PIRT) issued by Organization for Economic Cooperation and Development (OECD), the sensitivity analysis parameters for ex-vessel steam explosion are selected. By establishing 3D local break and 2D circular break geometric models with MC3D, the sensitivity analysis under RPV side break conditions is carried out for the important parameters affecting the calculation results (break size, pit water level, break position, trigger conditions, liquid column fragmentation and droplet fragmentation model), and the worst calculation conditions are obtained. The sensitivity analysis results show that under the condition of large break loss of coolant accident (LBLOCA), when the reactor pit is at full water level, 2D side circular break occurs in RPV, steam explosion is triggered when contacting the reactor pit side wall, and CONST model and Classical model are adopted, the calculation results of pressure load on the reactor pit side wall are the most conservative and pose the greatest threat to the integrity of the reactor pit and containment.
- Ex-vessel steam explosion,
- RPV side break,
- MC3D

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References(20)

References

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