IEEE 603 has been the governing standard for commercial nuclear power reactor safety system criteria for over three decades. As the successor to IEEE 279, it inherited a focus on light water reactor technology, which is the only technology licensed for commercial operation in the United States of America. The standard is based on a deterministic approach to safety analysis that was used to develop all currently licensed reactor designs.
The next generation of Advanced Reactor technologies not only depart from light water, but from deterministic approaches to safety analysis. The next revision of IEEE 603 will keep pace with this emerging technology, broadening its scope to encompass non-light water technologies and endorsing risk-informed, performance-based approaches to the design and analysis of reactor safety systems.
- IEEE PES Nuclear Power Engineering Committee (NPEC)
- IEEE NPEC Subcommittee 6, Instrumentation & Control Systems
- Working Group 6.3, Single Failure and Safety System Criteria
- Risk informed optimization of instrumentation and control (I&C) architecture, 2017 International Conference on Innovations in Electrical Engineering and Computational Technologies (ICIEECT)
- Study on risk-informed safety classification in VVER nuclear power plant, 14th International Conference on Quality, Reliability, Risk, Maintenance, and Safety Engineering (QR2MSE 2024)
- Risk-Informed Performance and Safety Significance Analysis of NPP Mitigating Systems, 2023 14th International Conference on Reliability, Maintainability and Safety (ICRMS)
- Research on Process Hazard Analysis (PHA) Method for Early Safety Assessment of Advanced Non-LWR, 2023 5th International Conference on System Reliability and Safety Engineering (SRSE)
- Codes and Standards for Advanced Reactors – IEEE PES Trending Technologies