• Title/Summary/Keyword: 방사성폐기물 처분시설

Search Result 283, Processing Time 0.026 seconds

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)
    • /
    • v.14 no.3
    • /
    • pp.279-287
    • /
    • 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.

천층처분시설에서의 주요 안전성인자 영향 분석

  • 박주완;김현주;김창락
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2004.06a
    • /
    • pp.193-193
    • /
    • 2004
  • 처분시설의 안정성 평가에 사용된 시나리오와 파라미터들은 본질적으로 불확실성을 가지고 있다. 이러한 불확시설성을 평가하기 위해서 동일한 시나리오에 대해서 평가 입력 파라미터의 변화에 따라 개인피폭선량 결과가 어떻게 변화하는지를 분석하였다. 본 분석에서는 처분시설을 빠져나온 핵종이 하부의 불포화된 토양층을 지나 대수층에 이른후 지하수에 의한 분산과 이류 등에 의해 인간환경의 우물까지 이동되고, 우물을 통해 다시 희석되어 부지 경계의 주민이 우물물을 식수로 사용하는 '지하수음용시나리오'가 고려되었다.(중략)

  • PDF

State report of radioactive wastes disposal in Japan (일본의 방사성 폐기물 처분관련 현황)

  • Kim, Hyeong-Mok;Gwon, Sang-Gi;Jo, Won-Jin
    • Proceedings of the Korean Society for Rock Mechanics Conference
    • /
    • 2006.03a
    • /
    • pp.205-213
    • /
    • 2006
  • 본고에서는 해외사례의 조사/분석을 통해 국내 환경에 적합한 처분시스템을 개발하는데 효율적으로 이용할 목적으로 일본의 방사성 폐기물 처분과 관련한 주요기관의 사업내용을 정리하고 암석역학 전공자가 관심을 가져볼 만한 처분 관련 연구시설 및 연구내용을 소개한다. 저준위 폐기물을 대상으로 한 100m 심도의 롯까쇼무라 시험공동과 고준위 폐기물을 대상으로 결정암질에 건설되는 1000m 심도의 미즈나미 지하연구시설 및 퇴적암질에서의 500m 심도의 호로노베 지하연구시설을 소개하였다.

  • PDF

Analysis of the Disposal Tunnel Spacing and Disposal Pit Pitch for the HLW Repository Design (심지층 처분시설 설계를 위한 처분터널 및 처분공 간격 분석)

  • Lee, Jong-Youl;Kim, Seong-Ki;Kim, Jhin-Wung;Choi, Jong-Won;Hahn, Pil-Soo
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.3 no.4
    • /
    • pp.349-358
    • /
    • 2005
  • In this study, analysis of the disposal tunnel spacing and disposal pit pitch was carried out, as a factor of the design to estimate the scale and layout of the repository. To do this, based on the reference repository concept and the engineered barrier concept, several cross sections of the disposal tunnel and disposal pit were established. After then, the mechanical and thermal stabilities of the established tunnels were analyzed. Also, an optimized disposal tunnel spacing and the disposal pit pitch reducing the excavation volume was proposed. The results of these analyses can be used in the deep geological repository design. The detailed analyses by the exact site characteristics data to reduce the uncertainty of the site and the modification for the optimization are required.

  • PDF

진전하는 고레벨 폐기물의 연구개발

  • 한국원자력산업회의
    • Nuclear industry
    • /
    • no.5_6 s.7
    • /
    • pp.45-47
    • /
    • 1982
  • 원자력평화이용의 마지막 큰 과제라 할 수 있는 고레벨방사성폐기물의 처리${\cdot}$처분에 관해 고레벨폐기물 glass 고화체의 화학적내구성(침출율, 고온수화반응 등), 조사효과, 장기저장시설의 냉각특성, 지층처분에서의 포장성(암석특성이나 투수성) 등 많은 연구가 행해지고 있는데, 여기서는 장기저장시설과 처분시설의 시스템개념에 관한 것을 알아 보기로 한다.

  • PDF

Preparation and Management of the Input Data for the Safety Assessment of Low- and Intermediate-level Radioactive Waste Disposal Facility in Korea (중·저준위 방사성폐기물 처분시설 안전성평가를 위한 입력데이터 설정 및 관리에 대한 고찰)

  • Park, Jin Beak;Kim, Hyun-Joo;Lee, Dong-Hee
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.12 no.4
    • /
    • pp.345-361
    • /
    • 2014
  • The systematic quality assurance activities on documents of the safety assessment are required for the safety case of the low- and intermediate-level radioactive waste disposal facility. In this paper, quality assurance system focused on the input data including the site characterization, groundwater flow, system design and monitoring are prepared and discussed. Rule for the input data selection is suggested and applied for the safety assessment which is based on the in-situ/experiment observations, final facility design and waste pileup plan, engineered barrier, field monitoring, recent biosphere, and radionuclide inventory. The reduction of data uncertainty will be expected to contribute to the safety of disposal facility further.

Disposal Approach for Long-lived Low and Intermediate-Level Radioactive Waste (장반감기 중저준위 방사성 폐기물의 국외 처분동향과 처분방안)

  • Park, Jin-Beak;Park, Joo-Wan;Kim, Chang-Lak
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2005.11a
    • /
    • pp.143-152
    • /
    • 2005
  • There certainly exists the radioactive inventory that exceeds the waste acceptance criteria for final disposal of the low and intermediate-level radioactive waste. In this paper, current disposal status of the long-lived radioactive waste in several nations are summarized and the basic procedures for disposal approach are suggested. With this suggestion, intensive discussion and research activities can hopefully be launched to set down the possible resolutions to dispose of the long-lived radioactive waste.

  • PDF

A Safety Assessment for the Wolsong LILW Disposal Center: As a part of safety case for the first stage disposal (월성원자력환경관리센터의 폐쇄후 처분안전성평가: 1단계 인허가 적용사례를 중심으로)

  • Park, Joo-Wan;Yoon, Jeong-Hyun;Kim, Chang-Lak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.6 no.4
    • /
    • pp.329-346
    • /
    • 2008
  • Post-closure safety assessment for the Wolsong Low- and Intermediate-level radioactive waste Disposal Center is described. Based on assessment context, closure concept and ground water flow characteristics of the disposal site, brief descriptions are included on the assessment scenarios, models, input parameters and tools. Radionuclide transport modeling in the near-field and far-field, gas generation and transport modeling, human intrusion and biosphere transport are also described briefly. Assessment results for each scenarios are shown to meet the performance criteria of regulatory body. Further and continuous efforts to improve the safety of disposal facility will be made during the construction and operational period.

  • PDF