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22대 대한민국 국회 국회정보길라잡이 국회의원검색
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Currently, there are no interim storage facilities and permanent disposal facilities in Korea, so all spent nuclear fuels are temporarily stored. However, the temporary storage facility is approaching saturation, and as a measure to this, the 2nd Basic Plan for the Management of High-Level Radioactive Waste presented an operation plan for dry interim storage facilities and dry temporary storage facilities on the NPP on-site. The dry storage can be operated in various ways, and to select the optimal dry storage method, the reduction of exposure for workers must be considered. Accordingly, it is necessary to develop a worker exposure scenario according to the dry storage method and evaluate and compare the radiological impact for each method. The purpose of this study is to develop an exposure scenario for workers transporting spent nuclear fuel by dry storage method. To this end, first, the operation procedure of the foreign commercial spent nuclear fuel dry storage system was analyzed based on the Final Safety Analysis Report(FSAR). 1) the concrete overpack-based system, 2) the metal overpack-based system, and 3) the vertical storage module-based system were selected for analysis. Factors were assumed that could affect the type of work (working distance, working hours, number of workers, etc.) during transportation work. Finally, the work type of the processes involved in transporting spent nuclear fuel by dry storage method was set, and an exposure scenario was developed accordingly. The concrete overpack method, the metal overpack method, and the vertical storage module method were classified into a total of 31, 9, and 23 processes, respectively. The work distance, work time, and number of workers for each process were set. The product of working hours and number of workers (Man-hour) was set high in the order of concrete overpack method, vertical storage module method, and metal overpack method, and short-range work (10 cm) was most often applied to the concrete overpack method. The results of this study are expected to be used as basic data for performing radiological comparisons of transport workers by dry storage method of spent nuclear fuel.

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기사명 저자명 페이지 원문 목차
수정체 방사선 방호에 관한 규제기준 및 기술기준 검토 = Review on regulatory and technical standards of radiation protection for lens of the eye 김시영, 황석주, 김재성, 손중권 p. 1-7

실시간 능동형 타입 격납장치 개발 = Development of real-time active type seals 신중기, 백희균, 이용주 p. 9-14

Visual Sample Plan을 활용한 미신고 시설 핵활동 분석 시료 채취 계획 = Soil sampling plan for analysis of nuclear facility activities utilizing visual sample plan 박수희, 한지영, 박제완, 김용민 p. 15-21

Dose reduction factors for high-exposure tasks at Korean pressurized water reactors Changju Song, Tae Young Kong, Seongjun Kim, Jinho Son, Jiung Kim, Jaeok Park, Hee Geun Kim, Yongkwon Kim, Hyungkwon Jung p. 23-33

국내·외 방사성폐기물 해상운반 현황 및 침몰사고 시 일반인 선량평가 사례 분석 = Analysis of domestic and overseas radioactive waste maritime transportation and dose assessment for the public by sinking accident 오가은, 곽민우, 김혁재, 김광표 p. 35-42

건식 저장방식별 사용후핵연료 운반 작업자 피폭시나리오 개발 = Development of spent nuclear fuel transportation worker exposure scenario by dry storage methods 손건우, 김혁재, 이신동, 곽민우, 김광표 p. 43-52

X-선 조사 후 고온 열화된 치자 염직물에서 추출한 색소 변이 연구 = A study on dye variation extracted from dyed textile with gardenia degraded at high temperature after X-ray irradiation 윤다영, 박혜진, 박세은, 허선홍, 임수빈, 정용재 p. 53-61

New radiolytic cyclization products, phlorocyclin and isophlorocyclin exhibit anti-inflammatory effects in LPS-stimulated macrophages Tae Hoon Kim p. 63-70

안전조치 검증장비의 극한 온도환경 적용성 평가 = Evaluation of usability in extreme temperature environments of safeguards equipment 백희균, 이진원, 신중기 p. 71-78

극한 온도환경에서의 안전조치 검증장비 사용을 위한 리트로핏 제작 및 현장 평가 = Retrofit production and field evaluation for use of safeguards equipment in extreme temperature environments 백희균, 이진원, 신중기 p. 79-87

프러시안 블루-알지네이트 비드를 이용한 세슘 제거 연구 = A study of cesium removal using Prussian blue-alginate beads 박소언, 민수정, 서범경, 노창현, 홍상범 p. 89-93

중저준위 방사성폐기물 전주기 이력관리체계 구축 및 개선 = The establishment and improvement of full cycle history management system for low- and intermediate-level radioactive waste 이진우, 이준, 은희철, 정지영 p. 95-100

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