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Evaluation of the Preliminary Dose Rate of the New-Type Disposal Container According to the Predicted Value of the Radionuclides Inventory of the Decommissioning Concrete Waste

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한국방사성폐기물학회 학술논문요약집 (Abstracts of Proceedings of the Korean Radioactive Wasts Society)
한국방사성폐기물학회 (Korean Radioactive Waste Society)
목차
1. Introduction
2. Limits on the surface dose rate of overseasdisposal containers
    2.1 France
    2.2 Sweden
    2.3 US
    2.4 UK
    2.5 Russia
3. Evaluation of dose rate of new-typedisposal container
    3.1 Specifications of new-type disposal container
    3.2 Decommissioned NPP's Bio-shield ConcreteRadionuclide Inventory Assumption
    3.3 Disposal container surface dose rate evaluationresult
4. Conclusion
Acknowledgement
저자
  • Ho-seog Dho(Korea Radioactive Waste Agency, 174, Gajeong-ro, Yuseong-Gu, Daejeon, 34129, Korea)
  • Tae-man Kim(Korea Radioactive Waste Agency, 174, Gajeong-ro, Yuseong-Gu, Daejeon, 34129, Korea)
  • Rin-ah Kim(Korea Radioactive Waste Agency, 174, Gajeong-ro, Yuseong-Gu, Daejeon, 34129, Korea)
  • Chun-hyung Cho(Korea Radioactive Waste Agency, 174, Gajeong-ro, Yuseong-Gu, Daejeon, 34129, Korea)