Risk Evaluation for Induced Steam Generator Tube Rupture

Yang Jian; Zhu Wentao

doi:10.13832/j.jnpe.2017.01.0051

Volume 38 Issue 1

Feb. 2025

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Yang Jian, Zhu Wentao. Risk Evaluation for Induced Steam Generator Tube Rupture[J]. Nuclear Power Engineering, 2017, 38(1): 51-55. doi: 10.13832/j.jnpe.2017.01.0051

Citation:

Yang Jian, Zhu Wentao. Risk Evaluation for Induced Steam Generator Tube Rupture[J]. Nuclear Power Engineering, 2017, 38(1): 51-55. doi: 10.13832/j.jnpe.2017.01.0051

Yang Jian, Zhu Wentao. Risk Evaluation for Induced Steam Generator Tube Rupture[J]. Nuclear Power Engineering, 2017, 38(1): 51-55. doi: 10.13832/j.jnpe.2017.01.0051

Citation:

Yang Jian, Zhu Wentao. Risk Evaluation for Induced Steam Generator Tube Rupture[J]. Nuclear Power Engineering, 2017, 38(1): 51-55. doi: 10.13832/j.jnpe.2017.01.0051

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Risk Evaluation for Induced Steam Generator Tube Rupture

doi: 10.13832/j.jnpe.2017.01.0051

China Nuclear Power Engineering Co. Ltd., Beijing, 100840, China

Received Date: 2016-04-12
Rev Recd Date: 2016-12-15

Available Online: 2025-02-09

Abstract

Abstract

In the progression of a severe accident sequence,the induced rupture of SG tubes is of most concern in level 2 PSA.The key factors of these phenomena are identified firstly,and then modeled in the Accident Progression Event Tree（APET） by the Risk Oriented Accident Analysis Method（ROAAM）.The probabilities of important nodes in these event trees are determined by the combination of hydrogen-thermal analysis and parameter sample methods.Finally,the conditional probabilities and frequencies of induced SGTR during severe accident phase are calculated.The design characteristics for reducing the risk of induced SGTR are also discussed in this paper.