A qualitative identification and analysis of hazards,risks and operating procedures for a decommissioning safety assessment of a nuclear research reactor |
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| Authors: | KwanSeong Jeong DongGyu Lee KuneWoo Lee HyeonKyo Lim |
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| Affiliation: | 1. Division of Decommissioning Technology Development, Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon, 305-353, Republic of Korea;2. Department of Safety Engineering, Chungbuk National University, 410 Sungbong-ro, Heungduk-gu, Cheongju, Chungbuk, 361-763, Republic of Korea |
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| Abstract: | Korea Research Reactor-1(KRR-1, TRIGA Mark-II type reactor), the first nuclear research reactor in Korea, is being prepared for a decommissioning. The decommissioning methods and procedures of KRR-1 ought to be based on its structural conditions and radiological characteristics. Also, a systematic approach to the decommissioning tasks must be followed by reviews and assessments of the decommissioning workers’ safety. |
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