• Title/Summary/Keyword: B형용기

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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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Method for Determining Transportation Grade for HIC Containing Spent Resin Using Radioactivity Analysis (방사성페기물 핵종분석 결과를 사용한 폐수지의 운반물등급 분류 방법)

  • Kim, Tae-Wook;Choi, Ki-Seop;Kang, Ki-Doo;Ha, Jong-Hyun
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.6 no.1
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    • pp.11-15
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    • 2008

  • In order to transport spent resin in a high integrated container made of high density polyethylene, a method for determining transportation grade by radioactivity analysis was developed. Ratios of radioisotopes in spent resin were derived from radioactivity analysis on spent resin. Associated curie-to-dose factors were determined to estimate radioisotope inventory from surface dose rates of spent resin. From the results, Activity limit of type A package was derived to be 1.19 TBq for HIC, and the corresponding surface dose rate was found to be 124.2 mSv/h.

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