Common Cause Failure Analysis of RHRS at PWR Based on GO-FLOW Methodology

Yang Jun; Yang Ming

Volume 35 Issue S1

Feb. 2025

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Yang Jun, Yang Ming. Common Cause Failure Analysis of RHRS at PWR Based on GO-FLOW Methodology[J]. Nuclear Power Engineering, 2014, 35(S1): 156-160.

Citation:

Yang Jun, Yang Ming. Common Cause Failure Analysis of RHRS at PWR Based on GO-FLOW Methodology[J]. Nuclear Power Engineering, 2014, 35(S1): 156-160.

Yang Jun, Yang Ming. Common Cause Failure Analysis of RHRS at PWR Based on GO-FLOW Methodology[J]. Nuclear Power Engineering, 2014, 35(S1): 156-160.

Citation:

Yang Jun, Yang Ming. Common Cause Failure Analysis of RHRS at PWR Based on GO-FLOW Methodology[J]. Nuclear Power Engineering, 2014, 35(S1): 156-160.

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Common Cause Failure Analysis of RHRS at PWR Based on GO-FLOW Methodology

Yang Jun,
Yang Ming

Key Laboratory of Fundamental Science on Nuclear Safety and Simulation Technology, Harbin Engineering University, Harbin, 150001, China

Received Date: 2013-11-15
Rev Recd Date: 2014-01-13

Available Online: 2025-02-15

Abstract

Abstract

In this paper,GO-FLOW method is applied to analyze the reliability of residual heat removal system at pressurized water reactor NPPs.The contribution to system unavailability caused by common cause failures is further calculated with β model,MGL model and α model.The results show that common cause failure has a significant effect on system reliability and GO-FLOW method can be effectively applied to system reliability analysis with common cause failures.
- System reliability,
- Common cause failure,
- GO-FLOW,
- NPPs

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