• Title/Summary/Keyword: 피폭방사선량평가

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Radiological Impact Assessment for the Domestic On-road Transportation of Radioactive Isotope Wastes (방사성동위원소 폐기물의 국내육상운반에 관한 방사선영향 평가)

  • Seo, Myunghwan;Hong, Sung-Wook;Park, Jin Beak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.14 no.3
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    • pp.279-287
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    • 2016

  • Korea Radioactive Waste Agency (KORAD) began to operate the low and intermediate level radioactive waste disposal facility in Gyeongju and to transport the radioactive waste containing radioactive isotopes from Daejeon to the disposal facility for the first time at 2015. For this radioactive waste transportation, in this study, radiological impact assessment is carried out for workers and public. The dose rate to workers and public during the transportation is estimated with consideration of the transportation scenarios and is compared with the Korean regulatory limit. The sensitivity analysis is carried out by considering both the variation of release ratios of the radioactive isotopes from the waste and the variation of the distances between the radioactive waste drum and worker during loading and unloading of radioactive waste. As for all the transportation scenarios, radiological impacts for workers and public have met the regulatory limits.

  • https://doi.org/10.7733/jnfcwt.2016.14.3.279 인용 PDF KSCI

An Analysis of Carbon-14 Metabolism for Internal Dosimetry at CANDU Nuclear Power Plants (중수로 원전 종사자의 방사선량 평가를 위한 $^{14}C$ 인체대사모델 분석)

  • Kim, Hee-Geun;Lee, Hyung-Seok;Ha, Gak-Hyun
    • Journal of Radiation Protection and Research
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    • v.28 no.3
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    • pp.207-213
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    • 2003

  • Carbon-14 is one of the major radionuclides released by CANDU Nuclear Power Plants(NPPs). It is almost always emitted as gas through the stack. From CANDU NPPs about 95% of all carbon-14 is released as carbon dioxide. Carbon-14 is a low energy beta emitter which, therefore, gives only a small skin dose from external radiation. As carbon dioxide Is physiologically rather inert gases for man's metabolism, the inhalation dose is probably less than 1 % of the ingestion dose. But this source of carbon-14, formed in a closed, nor-oxidative environment, was subsequently released into the workplace as an insoluble particulate when these systems were opened lip for re-tubing at CANDU NPPs. As a part of the improvement of dosimetry program at Wolsong Nuclear Power Plants, the carbon-14 metabolism based on references was investigated and studied to setup the internal dosimetry program due to inhalation of carbon-14.

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Preliminary Study on the Internal Dosimetry Program for Carbon-14 at Korean CANDU Reactors (중수로원전에서 발생하는 $^{14}C$에 대한 내부피폭 선량평가 프로그램에 관한 예비 조사)

  • Kong T.Y.;Kim H.C.;Park G.;Hang D.W.;Lee G.J.;Lee S.K.;Park S.C.
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2005.11a
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    • pp.317-320
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    • 2005

  • More strict radioactive regulations are applied to Korean nuclear power plants (NPPs) since ICRP-60 recommendation for radiation protection and has been enforced since 2003. In particular. carbon-14 and tritium concentrations are significantly higher at CANDU reactors compared to PWR reactors and this increases the risk of internal radiation exposure to workers at CANDU NPPs. Thus, it is necessary to estimate the exact amount of internal radiation exposure to workers fur radiological protection at CANDU reactors. In this paper, the current dosimetry method for carbon-14 is analyzed for the establishment of internal dosimetry for carbon-14 at domestic NPPs.

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The Assessment of Exposure Dose of Radiation Workers for Decommissioning Waste in the Radioactive Waste Inspection Building of Low and Intermediate-Level Radioactive Waste Disposal Facility (경주 중·저준위방사성폐기물 처분시설의 방폐물검사건물에서 해체 방사성폐기물 대상 방사선작업종사자의 피폭선량 평가 및 작업조건 도출)

  • Kim, Rin-Ah;Dho, Ho-Seog;Kim, Tae-Man;Cho, Chun-Hyung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.18 no.2_spc
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    • pp.317-325
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    • 2020

  • The Korea Radioactive Waste Agency plans to expand the storage capacity of radioactive waste by constructing a radioactive waste inspecting building to solve the problem of the lack of inspection space and drum-handling space in the radioactive waste receipt and storage building for the first-stage disposal facility. In this study, the exposure doses of radiation workers that handle new disposal containers for decommissioning waste in the storage areas of the radioactive waste inspecting building were calculated using the Monte Carlo N-particle transport code. The annual collective dose was calculated as a total of 84.8 man-mSv for 304 new disposal containers and an estimated annual 306 working hours for the radiation work. When the 304 new disposal containers (small/medium type) were stored in the storage areas, it was found that 25 radiation workers should be involved in acceptance/disposal inspection, and the estimated exposure dose per worker was calculated as an average annual value of 3.39 mSv. When the radiation workers handle the small containers in high-radiation dose areas, the small containers should be shielded further by increasing the concrete liner thickness to improve the work efficiency and radiation safety of the radiation workers. The results of this study will be useful in establishing the optimal radiation working conditions for radiation workers using the source term and characteristics of decommissioning waste based on actual measurements.

  • https://doi.org/10.7733/jnfcwt.2020.18.2(E).317 인용 PDF KSCI