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주승환
- Journal of the Korean Professional Engineers Association
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- v.32 no.6
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- pp.86-93
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- 1999
원자력 발전소 격납 용기의 누설시험 방법들은 3가지 유형으로 나타난다. 그것들은 A형, B형 그리고 C형 시험들이다. 본 누설시험의 시험 대상과 절차에 관한 해설을 실었다. 이 글과 앞으로 소개할 내용은 나무지 B형과 C형에 관한 해설을 주로 다루게 될 것이다. B형 시험과 C형 시험의 주된 대상들은 격납용기의 관통부들이다. 이 글에서는 B형과 C형 시험의 일분 주의 사항들을 해설한다.
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방경식;이주찬;김동학;이재호;서기석
- Proceedings of the Korean Radioactive Waste Society Conference
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- 2004.06a
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- pp.434-434
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- 2004
하나로에서 생산되는 방사성 동위원소를 생산단계에서 소비단계까지의 유통체계를 확립하기 위해서는 방사성동위원소를 안전하게 운반하기 위한 운반용기를 개발하여야 한다. 따라서, 원자력연구소에서는 Ir-192 110 ci용 밀봉선원 조사기를 개발하고 있다. 이 조사기는 국내ㆍ외 방사성물질 운반용기관련 법규의 운반용기 분류기준에 의하면 B형 운반용기로 분류된다. B형 운반용기는 관련법규에서 규정하고 있는 $800^{\circ}C$ 열 조건에서 30분 이상 동안 견딜 수 있는 능력을 갖추어야 한다.(중략)
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Chung Sung-Hwan;Kim Duck-Hoi;Jung Jin-Se;Yang Ke-Hyung;Lee Heung-Young
- Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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- v.3 no.3
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- pp.231-236
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- 2005
HIC transport packaging to transport a high integrity container(HIC) containing dry spent resin generated from nuclear power plants is to comply with the regulatory requirements of Korea and IAEA for Type B packaging due to the high radioactivity of the content, and to maintain the structural integrity under normal and accident conditions. It must withstand 9 m free drop impact onto an unyielding surface and 1 m drop impact onto a mild steel bar in a position causing maximum damage. For the conceptual design of a cylindrical HIC transport package, three dimensional dynamic structural analysis to ensure that the integrity of the package is maintained under all credible loads for 9 m free drop and 1 m puncture conditions were carried out using ABAQUS code.
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Lee, Min-Soo;Paek, Seung-Woo;Kim, Kwang-Rag;Ahn, Do-Hee;Yim, Sung-Paal;Chung, Hong-Suk;Choi, Heui-Joo;Choi, Jeong-Won;Son, Soon-Hwan;Song, Kyu-Min
- Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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- v.5 no.2
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- pp.155-169
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- 2007
A transport container for a 500 kCi tritium storage vessel was developed, which could be used for the transport of metal tritide from Wolsong TRF facility to a disposal site. The structural, thermal, shielding, and confinement analyses were performed for the container in a view of Type B. As a result of structural analysis, the developed container sustained its integrity under normal and accidental conditions. The maximum temperature increase of the inner storage vessel by radiation was evaluated at $134.8^{\circ}C at room temperature. In $800^{\circ}C$ fire test, The thermal barrier of container sustained the inner vessel at $405^{\circ}C after 30 min, which temperature was allowable for the container integrity since maximum design temperature of inner vessel was $550^{\circ}C. In the evaluation of the shielding, the activity of radiation was nearly zero on the outer surface of inner vessel. Consequently the transport container for a 500 kCi tritium was evaluated to pass all the safety tests including accidental condition, so it was concluded that the designed transport container is proper to be used.
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Cho Chun-Hyung;Lee Kang-Wook;Lee Yun-Do;Choi Byung-Il;Lee Heung-Young
- Proceedings of the Korean Radioactive Waste Society Conference
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- 2005.06a
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- pp.457-463
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- 2005
KHNP(Korea Hydro and Nuclear Power Ltd., Co.) is developing a HIC transport package which is satisfying domestic and IAEA regulations and NETEC(Nuclear Environment Technology Institute) is conducting a conceptual design. In this study, the shielding thickness was calculated using the data from radionuclide assay program which is currently using in nuclear sites and Micro Shield code. Considering the structural safety, carbon steel was chosen as shielding material and the shielding thickness was calculated for 500 R/hr and 100 R/hr at HIC surface, respectively. Through the shielding analysis, it was evaluated that the regulation limit is satisfied when the shielding thickness is 22 cm for 500 R/hr and 17 cm for 100/hr.
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