An integrated modeling approach for event sequence development in multi-unit probabilistic risk assessment

To obtain a complete site risk profile for multi-unit nuclear power plants (NPPs), the existing single-unit probabilistic risk assessment (PRA) model needs to be upgraded to address both intra-unit and inter-unit dependencies. The high temperature gas cooled reactor-pebble bed module (HTR-PM), with two reactor-steam generator modules and one shared steam turbine-generator set, is a ready-in-hand pilot for multi-unit PRA (MUPRA) studies. In this paper, a general framework for MUPRA is firstly developed based on HTR-PM PRA methodology. An Integrated Modeling (IM) approach is then proposed for multi-unit event sequence modeling. The approach is discussed in detail and illustrated with a loss of offsite power (LOOP) case study. Also, the limitations of the current analysis are put forward for open discussion.

[1]  Mohammad Modarres,et al.  An event classification schema for evaluating site risk in a multi-unit nuclear power plant probabilistic risk assessment , 2013, Reliab. Eng. Syst. Saf..

[2]  Suzanne Schroer An event classification schema for considering site risk in a multi-unit nuclear power plant probabilistic risk assessment , 2012 .

[3]  Joon-Eon Yang,et al.  A new method to evaluate alternate AC power source effects in multi-unit nuclear power plants , 2003, Reliab. Eng. Syst. Saf..

[4]  Nathan E. Bixler A Methodology for Performing Consequence Analysis for Multi-Unit/Spent Fuel Pool Source Terms. , 2014 .

[5]  Tadakuni Hakata,et al.  Seismic PSA method for multiple nuclear power plants in a site , 2007, Reliab. Eng. Syst. Saf..

[6]  Mohammad Modarres,et al.  Framework for assessing integrated site risk of small modular reactors using dynamic Probabilistic Risk Assessment simulation , 2015 .

[7]  Jun Zhao,et al.  Development of Probabilistic Safety Assessment with respect to the first demonstration nuclear power plant of high temperature gas cooled reactor in China , 2012 .

[8]  C. Senthil Kumar,et al.  Probabilistic safety assessment of multi-unit nuclear power plant sites – An integrated approach , 2014 .

[9]  Qianqian Jia,et al.  A design of human–machine interface for the two-modular high-temperature gas-cooled reactor nuclear power plant , 2014 .

[10]  Steven A. Arndt Methods and Strategies for Future Reactor Safety Goals , 2010 .

[11]  Ken Muramatsu,et al.  Effect of Correlations of Component Failures and Cross-Connections of EDGs on Seismically Induced Core Damages of a Multi-Unit Site , 2008 .

[12]  Yujie Dong,et al.  Current status and technical description of Chinese 2 × 250 MWth HTR-PM demonstration plant , 2009 .

[13]  K. Ebisawa,et al.  Concept and methodology for evaluating core damage frequency considering failure correlation at multi units and sites and its application , 2015 .

[14]  Zhang Li-guo Probabilistic Safety Assessment Framework of Pebble-Bed Modular High-Temperature Gas-Cooled Reactor , 2009 .

[15]  Dominique Vasseur,et al.  Probabilistic Safety Assessment of twin-unit nuclear sites: Methodological elements , 2016, Reliab. Eng. Syst. Saf..

[16]  Ovidiu Coman,et al.  Technical Approach for Safety Assessment of Multi-Unit NPP Sites Subject To External Events , 2014 .

[17]  C. Senthil Kumar,et al.  Integrated risk assessment for multi-unit NPP sites—A comparison , 2015 .