Search | Korea Science

정관성;이동규;박희성;이근우
- Journal of Energy Engineering
- /
- v.13 no.3
- /
- pp.191-198
- /
- 2004
Korea Research Reactor (KRR) 1 & 2 has shut down and through preparatory activities, its decommissioning activities are underway. As its decommissioning activities have been done over several years, its relevant data have been spreaded with various type and media all over the discrete place and inadvertently managed. As s result, managing and assessing data of KRR 1 & 2 has been difficult and complex and its data cannot be evaluated. By developing the decommissioning database system of KRR 1 & 2, the data of decommissioning activities fan be correctly evaluated, being systematically managed and objectively assessed. Finally, the decommissioning project of KRR 1 & 2 have come to more effectively accomplished.
PDF KSCI

정관성;이동규;박희성;이근우;오원진
- Proceedings of the Korean Radioactive Waste Society Conference
- /
- 2004.06a
- /
- pp.58-71
- /
- 2004
Korea Research Reactor (KRR) 1＆2 has shut down and through preparatory activities, its decommissioning activities are underway. As its decommissioning activities have been done over several years, its relevant data have been spreaded with various type and media all over the discrete place and inadvertently managed, As a result, managing and assessing data of KRR 1＆2 has been difficult and complex and its data cannot be evaluated. By developing the decommissioning database system of KRR 1＆2 the data of decommissioning activities can be correctly evaluated, being systematically managed and objectively assessed. Finally, the decommissioning project of KRR 1＆2 have come to more effectively accomplished. As the data of decommissioning activities can be at last systematically analyzed and objectively assessed, the decommissioning project of KRR 1＆2 would be more effectively accomplished.
PDF

Kim, Kyo-Youn;Ha, Chung-Woo;I.C. Gauld
- Nuclear Engineering and Technology
- /
- v.21 no.2
- /
- pp.63-72
- /
- 1989
An analysis for the gamma radiation fields in the research reactor MAPLE-X10 facility has been peformed under the assumption of partial loss of reactor and service pool water to assess the safety from the view point of design. Four photon source terms considered in the analysis were calculated using the ORIGEN-S code. Gamma dose rate calculations over the reactor and service pools during the water-loss accident conditions were performed using QAD-CG code. MCNP code (Monte Carlo Neuron and Photon Transport code), also, was used to assess the scattered radiation fields away from the pools, which is appropriate for calculating the scattered photon dose rates outside of the solid angle subtended by the source and pool walls.
PDF

이재훈;김웅식;윤영길;안형준;설광원;이재성;신안동;이상규;최강룡;김만웅;정윤형
- Nuclear industry
- /
- v.19 no.6 s.196
- /
- pp.42-47
- /
- 1999
원자력발전소의 안전성분분석보고서(SAR) 작성시 이용되어온 USNRC의 RG 1.70을 참고로 하고, 신형 원자로와 관련된 최신의 규제 정보와 차세대 원자로의 설계 특성에 근거하여, 차세대 원자로 표준 설계용 SAR 작성 지침(안)을 개발하였다. 개발된 지침(안)은 RG 1.70에 비해 상당히 많은 추가적인 안전 설계 정보를 제시하도록 구성하였으므로, 이 지침을 표준 설계에 대한 안전성 심사에 이용할 때 효율적이고 일관성 있는 안전성 판단을 할 수 있고, 이에 근거하여 향후 통합 허가(COL)용 SAR 작성 지침을 쉽게 개발할 수 있을 것으로 기대된다. 또한 일부 산업 기술 기준의 준용을 제외하고는 국산화를 실현함으로써 우리 고유의 지침 역할을 할 수 있게 되었다. 본 연구를 통해 개발된 지침(안)의 객관성과 일관성을 보장하기 위하여 향후전문가 검토가 수행될 예정이며, 검토 의견을 반영하여 내용을 보완한 후 차세대 원자로 표준 설계의 인$\cdot$허가 심사에 활용될 예정이다.
PDF