Exhaustive simulation approach for severe accident risk in nuclear power plants: OPR-1000 full-power internal events-Reference-Cited by-同舟云学术

Exhaustive simulation approach for severe accident risk in nuclear power plants: OPR-1000 full-power internal events

Published:2022-09 Issue: Volume:225 Page:108580
ISSN:0951-8320
Container-title:Reliability Engineering & System Safety
language:en
Short-container-title:Reliability Engineering & System Safety

Author:

Cho Jaehyun^ORCID,Lee Sang Hun,Bang Young Suk,Lee Suwon,Park Soo Yong

Funder

Ministry of Science, ICT and Future Planning

National Research Foundation of Korea

Publisher

Elsevier BV

Subject

Industrial and Manufacturing Engineering,Safety, Risk, Reliability and Quality

Reference29 articles.

1. On the quantitative definition of risk;Kaplan;Risk Anal,1981

2. Recent changes of safety regulation in Korea;Kim,2016

3. Modular accident analysis program 5 (MAAP5) version 5.03 – windows,2014

4. NRC, MELCOR computer code manuals:primer and user's guide version 1.8.5 (NUREG/CR-6119, volume 1, revision 2), NUREG/CR-6119, U.S.NRC, Washington D.C. (2000).

5. Development and application of level 2 probabilistic safety assessment for nuclear power plant, Specific Safety Guide, No. SSG-4, IAEA, 2010.

Cited by 11 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Optimization method for offsite consequence analysis by efficient plume segmentation;Nuclear Engineering and Technology;2024-09

2. Realistic estimation framework of radioactive release distributions into the environment during nuclear power plant accidents;Nuclear Engineering and Technology;2024-08

3. Impact of a novel emergency cooling system on data center environment under long-term power failure;Applied Thermal Engineering;2024-06

4. Fragility and Leakage Risk Assessment of Nuclear Containment Structure under Loss-of-Coolant Accident Conditions Considering Liner Corrosion;Applied Sciences;2024-03-13

5. Identifying and quantifying a complete set of full-power initiating events during early design stages of high-temperature gas-cooled reactors;Reliability Engineering & System Safety;2024-02