Nuclear Science

Submit a Manuscript

Publishing with us to make your research visible to the widest possible audience.

Propose a Special Issue

Building a community of authors and readers to discuss the latest research and develop new ideas.

Discussion on Key Issues in the Review of Technical Specifications of China Experimental Fast Reactor

China experimental fast reactor is the first fast reactor. As the highest law during the operation of nuclear facilities, the technical specifications play a vital role in the stable operation of fast reactors. The review of operation technical specifications is a comprehensive review, especially for fast reactor, which is the first time in China. There are great differences between fast reactor and traditional pressurized water reactor in technology. Due to the current regulations and standards in China, most of them are formulated according to PWR. The design of the new reactor has not formed a complete standard system, especially the operation mode. The modification of the operation mode is a major modification of the operation technical specification. This paper mainly describes the core problems encountered in the nuclear safety review of the technical specifications of China experimental fast reactor, such as the operation mode, the operability of the primary circuit sodium pump, the overpressure protection system, the periodic test of the containment chamber for sodium fire and argon release accidents, and finally obtains a suitable solution. It provides technical support for the continuous development of China's fast reactor industry. The review of technical specifications for fast reactor has achieved good practical results and provided valuable experience for subsequent commercial power plants.

Fast Reactor, Nuclear Safety Review, Discussion, Technical Specification

APA Style

He Dan, Li Haitao. (2022). Discussion on Key Issues in the Review of Technical Specifications of China Experimental Fast Reactor. Nuclear Science, 7(2), 30-33. https://doi.org/10.11648/j.ns.20220702.11

ACS Style

He Dan; Li Haitao. Discussion on Key Issues in the Review of Technical Specifications of China Experimental Fast Reactor. Nucl. Sci. 2022, 7(2), 30-33. doi: 10.11648/j.ns.20220702.11

AMA Style

He Dan, Li Haitao. Discussion on Key Issues in the Review of Technical Specifications of China Experimental Fast Reactor. Nucl Sci. 2022;7(2):30-33. doi: 10.11648/j.ns.20220702.11

Copyright © 2022 Authors retain the copyright of this article.
This article is an open access article distributed under the Creative Commons Attribution License (http://creativecommons.org/licenses/by/4.0/) which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

1. Ma Huan. Status and analysis of technical specifications for nuclear power plant operation in China. Frontier of Architectural Research. 2020.05.
2. Yu Chao. Analysis and Discussion on the influence of nuclear power plant operation technical specifications on nuclear safety. Science & Technology Vision. 2018.
3. Order of the president of the people's Republic of China No. 73 nuclear safety law, 2017.
4. Administrative regulations of the State Council regulations of the people's Republic of China on safety supervision and administration of civil nuclear facilities 1986.
5. HAF201-1995 National Nuclear Safety Administration safety regulations for research reactor design.
6. HAF202-1995 National Nuclear Safety Administration research reactor operation safety regulations.
7. HAD202/01-1989 National Nuclear Safety Administration research reactor operation management.
8. HAD202/03-1996 National Nuclear Safety Administration Application and modification of research reactor.
9. China Academy of atomic energy Final safety analysis report of China Experimental Fast Reactor.
10. Nureg-1431 Standard Technical Specifications Westinghouse plants.
11. China Academy of atomic energy Final safety analysis report of China Experimental Fast Reactor Rev. 1.
12. EJ/T 20042-2014 Design criteria for sodium cooled fast breeder reactor Safety design.
13. HAD103/01 Operating limits and conditions and operating procedures for nuclear power plants.
14. NRC RG1.12 nuclear power plant instrumentation.
15. Tsai S S. The NACOM Code for Analysis of Postulated Sodium Spray Fires in LMFBRs [R]. NUREG/CR- 1405.1989.
16. HAD202/06 Research reactor maintenance, periodic test and inspection.