The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Online ISSN : 2424-2934
2019.27
Session ID : 1828
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DEVELOPMENT AND PRELIMINARY SAFETY ANALYSIS OF THE SMALL MODULAR REACTOR BOC-600
*Zhanfei QIWeiwei WANGZhan LIUGuodong WANGHaitao WANGZhen CAO
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Abstract
The Small Modular Reactor BOC-600 is developed by State Nuclear Power Technology Corporation (SNPTC) / Shanghai Nuclear Engineering Research and Design Institute (SNERDI) with a compact design, which was formerly known as CAP200. The BOC-600 optimized based on CAP200 can be applied for electric power supply, heat supply and seawater desalination. The passive safety systems and inherent safety of the BOC-600 provide a major enhancement in plant safety to passively maintain core cooling and containment integrity. The BOC-600 passive safety systems are significantly simpler than typical PWR safety systems since they contain significantly fewer components, reducing the required tests, inspections and maintenance, which provide measurable improvements in plant simplification, safety and reliability. The main design features and engineered safety features are briefly introduced in this paper. The preliminary safety analysis, which a few non-loss-of-coolant and loss-of-coolant accidents are given as well, show that the safety function requirements of core residual heat removal, safety injection, depressurization and containment cooling are all met. Further design optimization is still ongoing.
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© 2019 The Japan Society of Mechanical Engineers
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