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
- 2021.11
- 수록면
- 3,824 - 3,836 (13page)
- DOI
- https://doi.org/10.1016/j.net.2021.06.007
이용수
초록· 키워드
오류제보하기
Workers’ safety from radiological exposure in a 1 ton/day capacity spent resin treatment facility wasevaluated according to the operating times and outflow rate due to process related leakages. The conservative annual dose based on the operating times of the workers exceeded the dose limit by at least7.38Eþ01 mSv for close work. The realistic dose range was derived as 1.62Eþ01 mSve6.60Eþ01 mSv. Theconservative and realistic annual doses for remote workers were 1.33Eþ01 mSv and 3.00Eþ00 mSvrespectively, which were less than the dose limit. The MWR was identified as the major contributor toworker exposure within the 1 h period required for removal of radioactive materials. The dose considering both internal and external exposures without APF was derived to be 1.92Eþ01 mSv for conservativeevaluation and 4.00Eþ00 mSv for realistic evaluation. Furthermore, the dose with APF was derived as7.27E-01 mSv for conservative evaluation and 1.51E-01 mSv for realistic evaluation. Considering the APFfor leakage from all parts, the dose range was derived as 1.25Eþ00 mSve2.03Eþ00 mSv for conservativeevaluation and 2.61E-01 mSve4.23E-01 mSv for realistic evaluation. Hence, it was confirmed thatradiological safety was secured in the event of a leakage accident
목차
등록된 정보가 없습니다.
참고문헌 (21)
참고문헌 신청
National Council on Radiation Protection and Measurements / 1985 / C-14 in the environment
U. Lee / 2019 / Radiological impact assessment for workers on treatment of radioactive spent resin from heavy water reactors / J. Radiol. Prot 39:422~442
Å. Magnusson / 2008 / 14C in spent ion-exchange resins and process water from nuclear reactors : a method for quantitative determination of organic and inorganic fractions / J. Radioanal. Nucl. Chem 275:261~273
Nursaidatul Syafadillah Kamaruzaman / 2018 / Management of Spent Ion-Exchange Resins From Nuclear Power Plant by Blending Method / Journal of Nuclear Fuel Cycle and Waste Technology 16(1):65~82
US Nuclear Regulatory Commission / 2013 / Final Comparative Environmental Evaluation of Alternatives for Handling Low-Level Radioactive Waste Spent Ion Exchange Resins from Commercial Nuclear Power Plants
U. Lee / 2019 / Radiological impact assessment for workers on treatment of radioactive spent resin from heavy water reactors / J. Radiol. Prot 39:422~442
Å. Magnusson / 2008 / 14C in spent ion-exchange resins and process water from nuclear reactors : a method for quantitative determination of organic and inorganic fractions / J. Radioanal. Nucl. Chem 275:261~273
Nursaidatul Syafadillah Kamaruzaman / 2018 / Management of Spent Ion-Exchange Resins From Nuclear Power Plant by Blending Method / Journal of Nuclear Fuel Cycle and Waste Technology 16(1):65~82
US Nuclear Regulatory Commission / 2013 / Final Comparative Environmental Evaluation of Alternatives for Handling Low-Level Radioactive Waste Spent Ion Exchange Resins from Commercial Nuclear Power Plants
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
Radiological safety analysis of a newly designed spent resin mixture treatment facility during normal and abnormal operational scenarios for the safety of radiation workers
Nuclear Engineering and Technology
2023 .05
-
Radiological safety assessment of lead shielded spent resin treatment facility with the treatment capacity of 1 ton/day
Nuclear Engineering and Technology
2021 .01
-
Evaluating internal exposure due to intake of 131I at a nuclear medicine centre of Dhaka using bioassay methods
Nuclear Engineering and Technology
2024 .06
-
Development of Internal Dose Assessment Procedure for Workers in Industries Using Raw Materials Containing Naturally Occurring Radioactive Materials
방사선방어학회지
2016 .01
-
직무피폭의 선량제약치에 관한 연구: 분야별 전문가 의견 중심으로
방사선산업학회지
2023 .03
-
Radiation Exposure from Nuclear Power Plants in Korea: 2011-2015
방사선방어학회지
2017 .01
-
대학 내 학습공간과 공동 생활공간에 대한 실내 라돈 농도 측정과 유효선량 산출
한국방사선학회 논문지
2018 .01
-
ED3를 이용한 방사성동위원소 의약품의 수정체 피폭선량평가
방사선산업학회지
2017 .01
-
진단참고준위(DRL)를 기준으로 PCXMC 프로그램을 이용한 성인의 일반촬영 부위별 유효선량 평가
한국방사선학회 논문지
2018 .01
-
의료기관 방사선작업종사자와 임상실습 학생의 피폭선량 분석
한국산학기술학회 논문지
2016 .08
-
선량제약치 도입을 위한 원자력발전소 주변 주민의 방사선량 분포 도출
방사선산업학회지
2022 .09
-
Derivation of a new dose constraint applicable to radioactive discharges from Korean nuclear power plants through retrospective dose assessment
Nuclear Engineering and Technology
2022 .10
-
의료용 디지털 영상 획득 엑스선발생장치 일반촬영 검사실 차폐 시설 성능 평가
한국산학기술학회 논문지
2024 .11
-
국내 흉부 X-선 검사에 따른 유효선량 계산
한국방사선학회 논문지
2018 .01
-
핵의학 방사선 작업종사자 피폭 감소 방안에 대한 연구
한국방사선학회 논문지
2019 .01
-
국내 원전 종사자의 방사선량 : 2009-2013
방사선방어학회지
2015 .01
-
Organ dose reconstruction for the radiation epidemiological study of Korean radiation workers: The first dose evaluation for the Korean Radiation Worker Study (KRWS)
Nuclear Engineering and Technology
2023 .02
-
Status of Radiation Dose and Radioactive Contamination due to the Fukushima Accident
방사선방어학회지
2016 .01
-
원자력시설 해체 종사자의 방사선피폭 관리를 위한피폭방사선량 관리체계 및 관리 목표치에 대한 연구
방사선산업학회지
2018 .01
-
국내 수처리시설 종사자 작업유형에 따른 외부피폭 방사선량 평가
방사선산업학회지
2023 .06
이 논문의 저자 정보
최근 본 자료
댓글(0)
0