New nuclear safety objectives and principles are being studied in main nuclear power countries and organizations after Fukushima Dai-ichi nuclear accident, to further improve the safety level of nuclear power plants (NPPs). Based on International Atomic Energy Agency (IAEA) Specific Safety Requirements (No.SSR-2/1), “Safety of Nuclear Power Plants: Design” (HAF102-2016) is issued in China. The concept “design extension condition (DEC)” is put forward, which is intend to enhance the plant’s capability to withstand accidents that are more severe than Design Basis Accidents (DBA). DEC could include conditions without significant fuel degradation (DEC-A in this paper) and conditions with core melting (DEC-B in this paper), e.g. severe accident. In this paper, the DEC-A and its application was discussed preliminarily, firstly, the development and connotation was introduced, then the identification of DEC-A, and the safety analysis principles of DEC-A were mainly described. This study may play a valuable role for implementation of new nuclear safety requirements in China.
Skip Nav Destination
2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5785-4
PROCEEDINGS PAPER
Preliminary Study on the Identification of DECs Without Significant Fuel Degradation in New NPP Designs
Zhiyi Yang,
Zhiyi Yang
Nuclear and Radiation Safety Center, MEP, Beijing, China
Search for other works by this author on:
Yimin Chong,
Yimin Chong
Nuclear and Radiation Safety Center, MEP, Beijing, China
Search for other works by this author on:
Chun Li,
Chun Li
Nuclear and Radiation Safety Center, MEP, Beijing, China
Search for other works by this author on:
Jiajia Zhang
Jiajia Zhang
Nuclear and Radiation Safety Center, MEP, Beijing, China
Search for other works by this author on:
Zhiyi Yang
Nuclear and Radiation Safety Center, MEP, Beijing, China
Yimin Chong
Nuclear and Radiation Safety Center, MEP, Beijing, China
Chun Li
Nuclear and Radiation Safety Center, MEP, Beijing, China
Jiajia Zhang
Nuclear and Radiation Safety Center, MEP, Beijing, China
Paper No:
ICONE25-68012, V007T11A026; 4 pages
Published Online:
October 17, 2017
Citation
Yang, Z, Chong, Y, Li, C, & Zhang, J. "Preliminary Study on the Identification of DECs Without Significant Fuel Degradation in New NPP Designs." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events. Shanghai, China. July 2–6, 2017. V007T11A026. ASME. https://doi.org/10.1115/ICONE25-68012
Download citation file:
13
Views
Related Proceedings Papers
Related Articles
A Happy New Year…
ASME J of Nuclear Rad Sci (January,2019)
The Fabulous Nuclear Odyssey of Belgium
J. Pressure Vessel Technol (June,2009)
Current Status of Reactors Deployment and Small Modular Reactors Development in the World
ASME J of Nuclear Rad Sci (October,2020)
Related Chapters
Czech and Slovakian Codes
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition
Application of Probabilistic Methods for the Evaluation of Deterministic Deviations from Technical Specifications (PSAM-0277)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards