Skip to content
Licensed Unlicensed Requires Authentication Published by De Gruyter August 18, 2023

Application of internal fire probabilistic risk assessment in design optimization for marine SMR

  • Chao Wang EMAIL logo , Xiaoming Zhang and Chao Xiong
From the journal Kerntechnik

Abstract

Small Modular Reactors (SMR) have attracted more and more attention. It can provide economic, stable and clean power for remote areas. It is also a reliable solution in satisfying the power supply of small and medium grids, as well as comprehensive energy supply including heat, electricity, water and steam, and distributed energy supply. Internal Fire Probabilistic Risk Assessment (PRA) is a system analysis method of assessing fire risk for a nuclear power plant, which plays a more and more important role. It can provide an overall understanding of the internal fire risk for SMR. Corresponding design optimization suggestions can be obtained through further analysis of the fire areas with major fire risk, which can help reduce the risk of internal fire and improve the safety of reactor. The paper introduces the basic information of marine SMR and development of internal fire PRA. Then the internal fire risk for marine SMR have been analyzed by this method. The results show that marine SMR have high safety with a Core Damage Frequency (CDF) for internal fire risk of less than 1.0 × 10−7 per year.


Corresponding author: Chao Wang, China Nuclear Power Technology Research Institute, Shenzhen 518000, China, E-mail:

  1. Research ethics: Not applicable.

  2. Author contributions: The authors have accepted responsibility for the entire content of this manuscript and approved its submission.

  3. Competing interests: The authors state no conflict of interest.

  4. Research funding: None declared.

  5. Data availability: Not applicable.

References

Najafi, B., Nowlen, S., Joglar, F., Funk, D., Anoba, R., Kazarians, M., Wyant, F., Kolaczkowski, A., Hannaman, G., and Forester, J. (2005). Fire PRA methodology for nuclear power facilities. NUREG/CR-6850, USNRC.Search in Google Scholar

National Nuclear Safety Administration (2004). Design safety regulations for nuclear power plant. National Nuclear Safety Administration, Peking (HAF102).Search in Google Scholar

Suzhou Nuclear Power Research Institute Co., L. (2013). National energy administration. Probabilistic safety assessment applied to nuclear power plants part 4: fire (NB/T 20037.4).Search in Google Scholar

Zhichao, Y., Ning, Z., and Xiao, J. (2012). Fire probabilistic safety assessment of Daya Bay nuclear power plant. Daya Bay Nuclear Power, Shenzhen, pp. 50–53.Search in Google Scholar

Received: 2023-04-27
Accepted: 2023-08-02
Published Online: 2023-08-18
Published in Print: 2024-02-26

© 2023 Walter de Gruyter GmbH, Berlin/Boston

Downloaded on 17.5.2024 from https://www.degruyter.com/document/doi/10.1515/kern-2023-0031/html
Scroll to top button