• Proceedings of the Korean Nuclear Society Conference
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.805-806
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• 2005

• Journal of the Ergonomics Society of Korea
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• 제35권4호
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• pp.247-261
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• 2016

Objective:The aim of this paper is to discuss the nuclear safety culture in Korea. Background: Recently, Korean nuclear field has met a strong anti-nuclear trend after a few happenings, as well as Fukushima accident, which are turned out to be caused by organizational pitfalls and safety culture defects in general. Method: We review the concepts and constructs of safety culture based on the brief history of the nuclear safety culture that IAEA mainly raised after the Chernobyl accident in 1986. Additionally, we give a comparative discussion on the approach to the safety culture with U.S. Results: Finally, we discuss the three technical domains and propose six selected domestic issues related to the nuclear safety culture for coping with the demanding requests on nuclear safety in Korea. Conclusion and Application: We suggest several recommendations and a research direction in the form of a re-start line for the nuclear safety culture in Korea.

• Nuclear Engineering and Technology
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• 제37권3호
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• pp.273-278
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• 2005

Key concepts in South Korean nuclear safety regulation are safety and risk. Nuclear regulation in South Korea has required reactor designs and safeguards that reduce the risk of a major accident to less than one in a million reactor-years-a risk supposedly low enough to be acceptable. To date, in South Korean nuclear safety regulation has involved the establishment of many technical standards to enable administration enforcement. In scientific lawsuits in which the legal issue is the validity of specialized technical standards that are used for judge whether a particular nuclear power plant is to be licensed, the concept of uncertainty law is often raised with regard to what extent the examination and judgment by the judicial power affects a discretion made by the administrative office. In other words, the safety standards for nuclear power plants has been adapted as a form of the scientific technical standards widely under the idea of uncertainty law. Thus, the improvement of nuclear safety regulation in South Korea seems to depend on the rational lawmaking and a reasonable, judicial examination of the scientific standards on nuclear safety.

• Nuclear Engineering and Technology
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• 제53권8호
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• pp.2600-2609
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• 2021

Low cycle fatigue behaviors of SA508-3 low-alloy steel were investigated in room-temperature air, high-temperature air and in light water reactor (LWR) water environments. The fatigue mean curve and design curve for the low-alloy steel are developed based on the fatigue data in room-temperature and high-temperature air. The environmental fatigue model for low-alloy steel is developed by the environmental fatigue correction factor (F_en) methodology based on the fatigue data in LWR water environments with the consideration of effects of strain rate, temperature, and dissolved oxygen concentration on the fatigue life.

• Proceedings of the Korean Nuclear Society Conference
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• 한국원자력학회 2005년도 추계학술발표회
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• pp.691-692
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• 2005

• Proceedings of the Korean Nuclear Society Conference
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• 한국원자력학회 1999년도 추계학술발표회요약집
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• pp.114.1-114
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• 1999

• Nuclear Engineering and Technology
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• 제41권4호
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• pp.403-412
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• 2009

For efficient and effective nuclear regulation, regulatory organizations must establish consistent and rigorous regulatory positions on safety matters. These positions should be based on high technical expertise and relevant ordinances, standards, and guidelines reflecting policy changes governing nuclear regulations. The Korea Institute of Nuclear Safety, a regulatory expert organization in Korea, has developed regulatory requirements, guidelines and analytical tools that provide regulatory technical bases for ensuring nuclear safety. The nuclear regulatory research also contributes to regulatory decision making by providing resolution for current and future safety issues. In this article, we introduce nuclear regulatory research and its main achievements in the past 10 years. Also, suggested here are future directions of nuclear regulatory research.

• Nuclear Engineering and Technology
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• 제53권9호
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• pp.2977-2981
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• 2021

Corrosion fatigue crack growth (FCG) behavior of 316LN stainless steel was investigated in high-temperature pressurized water at different temperatures, load ratios (R = K_max/K_min) and rise times (t_R). The environmental assisted effect on FCG rate was observed when both the R and t_R exceeded their critical values. The FCG rate showed a linear relation with stress intensity factor range (ΔK) in double logarithmic coordinate. The environmental assisted effect on FCG rate depended on the ΔK and quantitative relations were proposed. Possible mechanisms of environmental assisted FCG rate under different testing conditions are also discussed.

• Proceedings of the Korean Nuclear Society Conference
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• 한국원자력학회 2001년도 춘계학술발표회요약집
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• pp.551.2-551
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• 2001

• Proceedings of the Korean Nuclear Society Conference
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• 한국원자력학회 1999년도 춘계학술발표회요약집
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• pp.171-171
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• 1999