지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2024.3
- 수록면
- 43 - 52 (10page)
- DOI
- 10.23042/radin.2024.18.1.43
이용수
초록· 키워드
오류제보하기
Currently, there are no interim storage facilities and permanent disposal facilities in Korea, so all spentnuclear fuels are temporarily stored. However, the temporary storage facility is approaching saturation, and as a measureto this, the 2nd Basic Plan for the Management of High-Level Radioactive Waste presented an operation plan fordry interim storage facilities and dry temporary storage facilities on the NPP on-site. The dry storage can be operatedin 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 andevaluate and compare the radiological impact for each method. The purpose of this study is to develop an exposurescenario for workers transporting spent nuclear fuel by dry storage method. To this end, first, the operation procedureof 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 storagemodule-based system were selected for analysis. Factors were assumed that could affect the type of work (workingdistance, working hours, number of workers, etc.) during transportation work. Finally, the work type of the processesinvolved in transporting spent nuclear fuel by dry storage method was set, and an exposure scenario was developedaccordingly. The concrete overpack method, the metal overpack method, and the vertical storage module methodwere classified into a total of 31, 9, and 23 processes, respectively. The work distance, work time, and number ofworkers for each process were set. The product of working hours and number of workers (Man-hour) was set high inthe order of concrete overpack method, vertical storage module method, and metal overpack method, and short-rangework (10 cm) was most often applied to the concrete overpack method. The results of this study are expected to beused as basic data for performing radiological comparisons of transport workers by dry storage method of spent nuclearfuel.
목차
등록된 정보가 없습니다.
참고문헌 (0)
참고문헌 신청함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
Thermal Expansion Analysis of Concrete Spent Nuclear Fuel Dry Storage Developed in Korea
한국방사성폐기물학회 학술대회
2017 .01
-
Review of Spent Nuclear Fuel Dry Storage Demonstration Programs in US
한국방사성폐기물학회 학술대회
2017 .01
-
Considerations of Drying System Design for the Dry Storage of Spent Nuclear Fuel
한국방사성폐기물학회 학술대회
2017 .01
-
사용후핵연료 운반용기 및 건식저장 기술 동향
한국압력기기공학회 논문집
2020 .06
-
Safety Strengthening for On-Site Spent Nuclear Fuel Dry Storage Facilities
한국방사성폐기물학회 학술대회
2017 .01
-
경수로 사용후핵연료 중간저장시설 개념(안) 수립
방사선산업학회지
2024 .09
-
Design of Integrated Analysis Tool for Degradation Evaluation of Spent Nuclear Fuel in Dry Storage System
한국방사성폐기물학회 학술대회
2018 .01
-
The Study of Spent Nuclear Fuel Storage Facility to Consider Beyond Design Basis Accident
한국방사성폐기물학회 학술대회
2018 .01
-
Comparison of Permeability Calculation Inside a Spent Nuclear Fuel in a Dry Storage
한국방사성폐기물학회 학술대회
2017 .01
-
Dry storage of spent nuclear fuel and high active waste in Germany — Current situation and technical aspects on inventories integrity for a prolonged storage time
Nuclear Engineering and Technology
2018 .01
-
국내 · 외 사용후핵연료 저장 및 최종관리 정책 현황 분석
방사선산업학회지
2021 .12
-
미국의 사용후핵연료 건식저장 실증연구의 과거와 현재
방사성폐기물학회지
2017 .01
-
Confirmatory Procedure of Spent Fuel Information for Spent Fuel Transport to the Interim Storage Facility
한국방사성폐기물학회 학술대회
2017 .01
-
Estimation of On-Site Dry Storage Capacity Needed Based on Current Nuclear Policy in Korea
한국방사성폐기물학회 학술대회
2017 .01
-
Thermal Analysis for Spent Nuclear Fuel Temporary Storage System in Pyroprocessing Facility
한국방사성폐기물학회 학술대회
2017 .01
-
Numerical Analysis on Natural Convection of Backfill Gases in a Dry Storage System for Spent Nuclear Fuels
한국방사성폐기물학회 학술대회
2018 .01
-
Thermal analysis of certain accident conditions of dry spent nuclear fuel storage
Nuclear Engineering and Technology
2018 .01
-
FRAPCON analysis of cladding performance during dry storage operations
Nuclear Engineering and Technology
2018 .01
-
Evaluation of Acceptance Criterion for Dryness of Canister and Spent Nuclear Fuel for Dry Storage
한국방사성폐기물학회 학술대회
2018 .01
-
Predicting Amount of Radial Hydrides in Spent Fuel During Dry Storage
한국방사성폐기물학회 학술대회
2018 .01
최근 본 자료
댓글(0)
0