Application research of PSA in identifying important non-safety SSCs of AHPR1000
Abstract
Abstract: The domestically advanced research and development reactor type AHPR1000 adopt passive systems to alleviate design basis accidents. Compared with the CAP series reactor types, AHPR1000 have added non safety level active safety measures. This study mainly investigates the identification method of important non safety level Structure, System and Component (SSCs) for passive advanced light water reactor type non safety level systems from the PSA theory. Based on the actual case of AHPR1000, a systematic study was conducted using the PSA model from the aspects of accident mitigation and uncertainty analysis. The important non safety level SSCs in AHPR1000 were identified, providing valuable reference and inspiration for subsequent engineering applications. It also provided strong technical support for the formulation and optimization of regulatory requirements for non safety level systems of passive advanced light water reactors.
Fields of Study & Subjects
Risk and Safety Analysis
Publication details
- Journal / source
- Annals of Nuclear Energy
- Publisher
- Elsevier BV
- Volume
- 238
- Pages
- 112575–112575
- Publication date
- 23 June 2026
- Language
- EN