Study on Heat Exchange Experiment Characteristics of SPRHR Condenser for Nuclear Power Plants

Yang Jinchun

doi:10.13832/j.jnpe.2018.01.0061

Volume 39 Issue 1

Feb. 2025

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Yang Jinchun. Study on Heat Exchange Experiment Characteristics of SPRHR Condenser for Nuclear Power Plants[J]. Nuclear Power Engineering, 2018, 39(1): 61-63. doi: 10.13832/j.jnpe.2018.01.0061

Citation:

Yang Jinchun. Study on Heat Exchange Experiment Characteristics of SPRHR Condenser for Nuclear Power Plants[J]. Nuclear Power Engineering, 2018, 39(1): 61-63. doi: 10.13832/j.jnpe.2018.01.0061

Yang Jinchun. Study on Heat Exchange Experiment Characteristics of SPRHR Condenser for Nuclear Power Plants[J]. Nuclear Power Engineering, 2018, 39(1): 61-63. doi: 10.13832/j.jnpe.2018.01.0061

Citation:

Yang Jinchun. Study on Heat Exchange Experiment Characteristics of SPRHR Condenser for Nuclear Power Plants[J]. Nuclear Power Engineering, 2018, 39(1): 61-63. doi: 10.13832/j.jnpe.2018.01.0061

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Study on Heat Exchange Experiment Characteristics of SPRHR Condenser for Nuclear Power Plants

doi: 10.13832/j.jnpe.2018.01.0061

Yang Jinchun

China Nuclear Power Design Co. Ltd., Shenzhen, Guangdong, 518026, China

Received Date: 2017-02-15
Rev Recd Date: 2017-10-22

Available Online: 2025-02-09

Publish Date: 2025-02-09

Abstract

Abstract

In order to meet the safety requirement of nuclear power plants, the residual heat must be removed by the passive system under severe accidents. An experiment is conducted on the heat exchange characteristics of Secondary Passive Residual Heat Removal Condenser（SPRHR condenser） under different vapor pressure and temperature conditions. The results show that the heat exchange characteristics of SPRHR is stable and with enough safe margin. The heat exchange characteristics of SPRHR can be predicted well by Shah and Foster-Zuber correlations.
- SPHR condenser,
- Condensing heat transfer,
- Pool boiling