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
- 2022.10
- 수록면
- 3,849 - 3,854 (6page)
- DOI
- 10.1016/j.net.2022.05.014
이용수
초록· 키워드
오류제보하기
The present work aims to optimize the radiation protection efficiency for ion-selective containers used in the liquid treatment for the nuclear power plant (NPP) cooling cycle. Some naturally occurring rocks were examined as filler materials to reduce absorbed dose and equivalent dos received from the radioactive waste container. Thus, the absorbed dose and equivalent dose were simulated at a distance of 1 m from the surface of the radioactive waste container using the Monte Carlo simulation. Both absorbed dose and equivalent dose rate are reduced by raising the filler thickness. The total absorbed dose is reduced from 7.66E-20 to 1.03E-20 Gy, and the equivalent dose is rate reduced from 183.81 to 24.63 mSv/ h, raising the filler thickness between 0 and 17 cm, respectively. Also, the filler type significantly affects the equivalent dose rate, where the redorded equivalent dose rates are 24.63, 24.08, 27.63, 33.80, and 36.08 mSv/h for natural rocks basalt-1, basalt-2, basalt-sill, limestone, and rhyolite, respectively. The mentioned results show that the natural rocks, especially a thicker thickness (i.e., 17 cm thickness) of natural rocks basalt-1 and basalt-2, significantly reduce the gamma emissions from the radioactive wastes inside the modified container. Moreover, using an outer cementation concrete wall of 15 cm causes an additional decrease in the equivalent dose rate received from the container where the equivalent dose rate dropped to 6.63 mSv/h.
목차
등록된 정보가 없습니다.
참고문헌 (0)
참고문헌 신청함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
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
-
Development of Internal Dose Assessment Procedure for Workers in Industries Using Raw Materials Containing Naturally Occurring Radioactive Materials
방사선방어학회지
2016 .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
-
ED3를 이용한 방사성동위원소 의약품의 수정체 피폭선량평가
방사선산업학회지
2017 .01
-
Assessment of Occupational Exposure Dose to Radiation Workers in Secondary Standard Dosimetry Laboratory of Mongolia
방사선산업학회지
2019 .01
-
원전사고 후 광역의 방사성 오염부지 내 거주민에 대한시간에 따른 피폭방사선량 평가
방사선산업학회지
2015 .12
-
Administrative dose control for occupationally-exposed workers in Korean nuclear power plants
Nuclear Engineering and Technology
2021 .01
-
Radiological analysis of transport and storage container for very low-level liquid radioactive waste
Nuclear Engineering and Technology
2021 .12
-
선량제약치 도입을 위한 원자력발전소 주변 주민의 방사선량 분포 도출
방사선산업학회지
2022 .09
-
직무피폭의 선량제약치에 관한 연구: 분야별 전문가 의견 중심으로
방사선산업학회지
2023 .03
-
Radioactive effluents released from Korean nuclear power plants and the resulting radiation doses to members of the public
Nuclear Engineering and Technology
2017 .01
-
Radiological safety assessment of lead shielded spent resin treatment facility with the treatment capacity of 1 ton/day
Nuclear Engineering and Technology
2021 .01
-
Insights from an OKMC simulation of dose rate effects on the irradiated microstructure of RPV model alloys
Nuclear Engineering and Technology
2023 .03
-
Multi-layers grid environment modeling for nuclear facilities: A virtual simulation-based exploration of dose assessment and dose optimization
Nuclear Engineering and Technology
2020 .01
-
대표인 개념 도입에 따른 습관자료 변경 시 국내 원자력발전소 주변 일반인 선량 변화 분석
방사선산업학회지
2021 .12
-
유리선량계를 이용한 관전류자동조절기법과 고정관전류기법에서 저선량 및 고해상 흉부CT의 노이즈 및 선량 비교
방사선산업학회지
2017 .01
-
Radiation Exposure from Nuclear Power Plants in Korea: 2011-2015
방사선방어학회지
2017 .01
-
국내 수처리시설 종사자 작업유형에 따른 외부피폭 방사선량 평가
방사선산업학회지
2023 .06
-
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
이 논문의 저자 정보
최근 본 자료
댓글(0)
0