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Development of a Stress Corrosion Cracking Life Prediction Model for Stainless Steel Considering the Effects of Dissolved Hydrogen and Radiation Damage in the Primary Water Environment of a Pressurized Water Reactor
- Author(s)
- HAM, JUNHYUK
- Advisor
- KIM, JI HYUN
- Issued Date
- 2025-02
- URI
- https://scholarworks.unist.ac.kr/handle/201301/86486 http://unist.dcollection.net/common/orgView/200000865858
- Publisher
- Ulsan National Institute of Science and Technology
- Degree
- Doctor
- Major
- Department of Nuclear Engineering
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