방사성폐수지 처리를 위한 연속식 상용 제염시스템 차폐 설계 및 평가 (Design and Evaluation of Shielding for the Continuous Common Decontamination System for Radioactive Spent Resin Disposal)

서지정보

· 발행기관 : (사)한국방사선산업학회
· 수록지 정보 : 방사선산업학회지 / 13권 / 2호 / 103 ~ 108페이지
· 저자명 : 장한, 양남희, 정원선, 조영수, 이경진

초록

If the continuous common decontamination system of radioactive spent resin designedby Huvis Water Co., Ltd is actually operated, the radioactive spent resin with the considerablyhighradioactivity level would be handled, so that the radiation shielding is essential to the treatmentfacilities, and its performance should be secured as well. When designing the shielding or calculatingthe thickness of shielding wall, the dose at the point of interest should be calculated by assuming thecase without the shielding material, and then the shielding material and the thickness of shieldingare decided. In the treatment facilities, the treatment system as a source term is divided into threeprocesses, and out of them, from the SKID 1 with 60Co and 137Cs as source term to the work zonewere set up as the point of interest. For the calculation of dose rate, the point kennel method wasused. In accordance with the shielding design standard, the shielding material and its thickness weredecided, so that the dose rate at the point of interest after shielding could be less than 1 mSv·week-1.
Regarding the shielding materials, the concrete, steel, and lead that would be generally used themost in reality, were decided. The thicknesses of shielding meeting the standard value at all thepoints of interest were like 30 cm for concrete, and 3 cm for lead. Considering the optimization ofradiation protection, it should be set up as the above values or up. The shielding material and itsthickness should be selected by considering the economic feasibility and many efficiencies.

영어초록

If the continuous common decontamination system of radioactive spent resin designedby Huvis Water Co., Ltd is actually operated, the radioactive spent resin with the considerablyhighradioactivity level would be handled, so that the radiation shielding is essential to the treatmentfacilities, and its performance should be secured as well. When designing the shielding or calculatingthe thickness of shielding wall, the dose at the point of interest should be calculated by assuming thecase without the shielding material, and then the shielding material and the thickness of shieldingare decided. In the treatment facilities, the treatment system as a source term is divided into threeprocesses, and out of them, from the SKID 1 with 60Co and 137Cs as source term to the work zonewere set up as the point of interest. For the calculation of dose rate, the point kennel method wasused. In accordance with the shielding design standard, the shielding material and its thickness weredecided, so that the dose rate at the point of interest after shielding could be less than 1 mSv·week-1.
Regarding the shielding materials, the concrete, steel, and lead that would be generally used themost in reality, were decided. The thicknesses of shielding meeting the standard value at all thepoints of interest were like 30 cm for concrete, and 3 cm for lead. Considering the optimization ofradiation protection, it should be set up as the above values or up. The shielding material and itsthickness should be selected by considering the economic feasibility and many efficiencies.

참고자료

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