[KSCI] Korea Science Citation Index Service

http://dx.doi.org/10.14773/cst.2021.20.4.189

Failure Evaluation Plan of a Reactor Internal Components of a Decommissioned Plant

Hwang, Seong Sik (Korea Atomic Energy Research Institute)
Kim, Sung Woo (Korea Atomic Energy Research Institute)
Choi, Min Jae (Korea Atomic Energy Research Institute)
Cho, Sung Hwan (Korea Atomic Energy Research Institute)
Kim, Dong Jin (Korea Atomic Energy Research Institute)

Publication Information

Corrosion Science and Technology / v.20, no.4, 2021 , pp. 189-195 More about this Journal

Abstract

A technology for designing and licensing a dedicated radiation shielding facility needs to be developed for safe and efficient operation an R&D center. Technology development is important for smooth operation of such facilities. Causes of damage to internal structures (such as baffle former bolt (BFB) of pressurized water reactor) of a nuclear power reactor should be analyzed along with prevention and countermeasures for similar cases of other plants. It is important to develop technologies that can comprehensively analyze various characteristics of internal structures of long term operated reactors. In high-temperature, high-pressure operating environment of nuclear power plants, cases of BFB cracks caused by irradiated assisted stress corrosion cracks (IASCC) have been reported overseas. The integrity of a reactor's internal structure has emerged as an important issue. Identifying the cause of the defect is requested by the Korean regulatory agency. It is also important to secure a foundation for testing technology to demonstrate the operating environment for medium-level irradiated testing materials. The demonstration testing facility can be used for research on material utilization of the plant, which might have highest fluence on the internal structure of a reactor globally.

Keywords

Nuclear power plant; PWR; Reactor internals; Materials harvesting; IASCC;

Citations & Related Records

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