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
- 2023.5
- 수록면
- 1,935 - 1,945 (11page)
- DOI
- 10.1016/j.net.2022.12.006
이용수
초록· 키워드
오류제보하기
The radiological safety of workers in a newly developed microwave-based spent resin treatment facility was assessed based on work location and operational scenarios. The results show that the remote operation room worker was exposed to maximum annual dose of 3.19Eþ00 mSv, which is 15.9% of the dose limit, thereby confirming radiological safety. Inside the pathway, annual doses in the range of 7.87E-02e2.07E-01 mSv were measured initially at the mock-up tank and later at the point between the spent resin separation and treatment parts. The dose of emergency maintenance workers was below the dose limit (4.08E-03e4.99Eþ00 mSv); however, before treatment (separation and microwave), the dose of maintenance and repair workers exceeded the dose limit. The doses of the effluent removal workers at the zeolite and activated carbon storage tank and spent resin storage tank were the lowest at 2.79E-01 e2.87E-01 mSv and 9.27E-01 mSv in “1 h” and “4e5 h of operation”, respectively. The immediately lower and upper layers of the facility room exhibited the highest annual doses of 1.84Eþ00 and 3.22Eþ00 mSv, respectively. Through this study, a scenario that can minimize the dose considering the movement of spent resin through the facility can be developed
목차
등록된 정보가 없습니다.
참고문헌 (0)
참고문헌 신청함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
Dose evaluation of workers according to operating time and outfl ow rate in a spent resin treatment facility
Nuclear Engineering and Technology
2021 .11
-
Radiological safety assessment of lead shielded spent resin treatment facility with the treatment capacity of 1 ton/day
Nuclear Engineering and Technology
2021 .01
-
Development of Internal Dose Assessment Procedure for Workers in Industries Using Raw Materials Containing Naturally Occurring Radioactive Materials
방사선방어학회지
2016 .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
-
직무피폭의 선량제약치에 관한 연구: 분야별 전문가 의견 중심으로
방사선산업학회지
2023 .03
-
Radiation Exposure from Nuclear Power Plants in Korea: 2011-2015
방사선방어학회지
2017 .01
-
ED3를 이용한 방사성동위원소 의약품의 수정체 피폭선량평가
방사선산업학회지
2017 .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
-
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
-
대학 내 학습공간과 공동 생활공간에 대한 실내 라돈 농도 측정과 유효선량 산출
한국방사선학회 논문지
2018 .01
-
선량제약치 도입을 위한 원자력발전소 주변 주민의 방사선량 분포 도출
방사선산업학회지
2022 .09
-
국내 수처리시설 종사자 작업유형에 따른 외부피폭 방사선량 평가
방사선산업학회지
2023 .06
-
원자력시설 해체 종사자의 방사선피폭 관리를 위한피폭방사선량 관리체계 및 관리 목표치에 대한 연구
방사선산업학회지
2018 .01
-
Administrative dose control for occupationally-exposed workers in Korean nuclear power plants
Nuclear Engineering and Technology
2021 .01
-
의료기관 방사선작업종사자와 임상실습 학생의 피폭선량 분석
한국산학기술학회 논문지
2016 .08
-
방사선작업종사자 피폭선량 관리에 대한 연구
방사선산업학회지
2020 .01
-
External dose assessment for workers dismantling the bio-shield of a commercial power nuclear reactor: Case study of Kori-1, Korea
Nuclear Engineering and Technology
2020 .09
-
Using RESRAD-BUILD for Potential Radiation Dose Estimation the Korea Research Reactor-1 When It Opens to the Public as a Memorial Hall
International JOURNAL OF CONTENTS
2020 .06
-
대표인 개념 도입에 따른 습관자료 변경 시 국내 원자력발전소 주변 일반인 선량 변화 분석
방사선산업학회지
2021 .12
-
수정체 방사선 방호에 관한 규제기준 및 기술기준 검토
방사선산업학회지
2024 .03
이 논문의 저자 정보
최근 본 자료
댓글(0)
0