• Title/Summary/Keyword: B형 운반용기

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Ir-192 100 ci용 조사기 열 시험

  • 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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Structural Evaluation on HIC Transport Packaging under Accident Conditions (HIC 운반용기의 사고조건에 대한 구조평가)

  • 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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Safety evaluation of type B transport container for tritium storage vessel (B형 삼중수소 운반용기 안정성 평가)

  • 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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Shielding Analysis for Industrial Package: Focusing on Dry Active Waste (IP형 운반용기 차폐해석-잡고체폐기물을 중심으로)

  • Lee Kang-Wook;Cho Chun-Hyung;Jang Hyun-Kie;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.523-530
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    • 2005

  • In this study, maximum exposure rate at DAW(Dry Active Waste) drum surface which is satisfying regulation limit was calculated for conceptual design of IP(Industrial Package). DAW can be classified as combustible and non-combustible waste and the calculation was conducted for single and mixed radionuclide for each type of waste. In case of combustible waste that mixed radionuclide is uniformly distributed, the maximum exposure rates at drum surface were 3.60E-01, 8.85E-01 and 1.27E+01 mSv/hr for IP Type 1, 2-a and 2-b, respectively. and 3.60E-01, 8.85E-01, 1.27E+01 mSv/hr for single radionuclide(Co-60). In case of non-combustible waste that mixed radionuclide is uniformly distributed, the maximum exposure rates at drum surface were 7.14E-01, 1.83E+00, 2.69E+01 mSv/hr for IP Type 1, 2-a and 2-b, respectively. and 7.13E-01, 1.81E-01, 2.62E+01 mSv/hr for single radionuclide(Co-60). Through this study, the maximum amount of DAW can be transported by IP was suggested as maximum exposure rate at drum surface and the calculation for the other types of waste will be conducted.

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