Research on Heat Removal Capability for Passive Moderator Residual Heat Removal System of TACR-1000 when Station Black-Out Accident

YAN Lin; JIA Bao-shan; LIAN Hai-bo

Volume 29 Issue 4

Aug. 2008

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Article Navigation > Nuclear Power Engineering > 2008 > 29(4): 117-122

YAN Lin, JIA Bao-shan, LIAN Hai-bo. Research on Heat Removal Capability for Passive Moderator Residual Heat Removal System of TACR-1000 when Station Black-Out Accident[J]. Nuclear Power Engineering, 2008, 29(4): 117-122.

Citation:

YAN Lin, JIA Bao-shan, LIAN Hai-bo. Research on Heat Removal Capability for Passive Moderator Residual Heat Removal System of TACR-1000 when Station Black-Out Accident[J]. Nuclear Power Engineering, 2008, 29(4): 117-122.

Citation:

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Research on Heat Removal Capability for Passive Moderator Residual Heat Removal System of TACR-1000 when Station Black-Out Accident

Department of Engineering Physics, Tsinghua University, Beijing, 100084, China

Received Date: 2007-06-08
Rev Recd Date: 2007-10-09

Available Online: 2025-07-22

Publish Date: 2008-08-15

Abstract

Abstract

To evaluate the effectiveness of the Passive Moderator Residual Heat Removal System（PMRHRS）,CATHENA（Canadian Algorithm for Thermal hydraulic Network Analysis） code is used to simulate its cooling capability under normal condition and the lost of flow accident condition.And the result of steady state is obtained by the simulation and calculation for the Moderator Cooling System（MCS）,which is used as the initial value for the transient state analysis.The heat removal capability of the PMRHRS is then calculated and the result is initially analyzed to prove that the PMRHRS can keep the reactor safe.
- Moderator,
- Residual heat removal system,
- Canadian Algorithm for Thermal Hydraulic Network Analysis（CATHENA）