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A Study on Pre-Transition Corrosion Behavior of Zirconium Alloy in Simulated Primary Water Conditions of Nuclear Power Plant
- Author(s)
- Kim, Taeho
- Advisor
- Kim, Ji Hyun
- Issued Date
- 2018-08
- URI
- https://scholarworks.unist.ac.kr/handle/201301/72440 http://unist.dcollection.net/common/orgView/200000108210
- Publisher
- Ulsan National Institute of Science and Technology (UNIST)
- Degree
- Doctor
- Major
- Department of Nuclear Engineering
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