Numerical Simulation of Steam Migration in Containment of Large-Sized Advanced PWRs

ZHANG Shi; WANG De-zhong; MA Yuan-wei

Volume 34 Issue 2

Apr. 2013

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ZHANG Shi, WANG De-zhong, MA Yuan-wei. Numerical Simulation of Steam Migration in Containment of Large-Sized Advanced PWRs[J]. Nuclear Power Engineering, 2013, 34(2): 30-33.

Citation:

ZHANG Shi, WANG De-zhong, MA Yuan-wei. Numerical Simulation of Steam Migration in Containment of Large-Sized Advanced PWRs[J]. Nuclear Power Engineering, 2013, 34(2): 30-33.

ZHANG Shi, WANG De-zhong, MA Yuan-wei. Numerical Simulation of Steam Migration in Containment of Large-Sized Advanced PWRs[J]. Nuclear Power Engineering, 2013, 34(2): 30-33.

Citation:

ZHANG Shi, WANG De-zhong, MA Yuan-wei. Numerical Simulation of Steam Migration in Containment of Large-Sized Advanced PWRs[J]. Nuclear Power Engineering, 2013, 34(2): 30-33.

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Numerical Simulation of Steam Migration in Containment of Large-Sized Advanced PWRs

School of Mechanical and Power Engineering, Shanghai Jiao Tong University, Shanghai, 200240, China

Received Date: 2011-11-14
Rev Recd Date: 2012-05-29

Available Online: 2025-03-08

Publish Date: 2013-04-25

Abstract

Abstract

The migration of steam in the containment after the break of primary circulation pipelines of large-sized advanced PWR is studied by CFD method with Uchida correlations to simulate steam condensation analyzing the steam distribution of different coolant leakage rates.The result suggests that the distribution trend of steam is basically the same at various coolant leakage rates,and the steam concentration near the containment wall increases fluctuant for which the higher position has the smaller fluctuation.
- Containment,
- Coolant loss rate,
- Monitor,
- Steam migration,
- Numerical simulation

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