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
- 2020.11
- 수록면
- 2,511 - 2,521 (11page)
- DOI
- https://doi.org/10.1016/j.net.2020.04.031
이용수
초록· 키워드
오류제보하기
The Fukushima accident is characterized by the fact that three reactors at the same site experiencedreactor vessel failure and the accident resulted in significant radiological release to the environment,which was about 1/10 of the Chernobyl releases. The safe removal of fuel debris in the reactor vessel andPrimary Containment Vessel (PCV) and treatment of huge amount of contaminated water are the majorissues for the decommissioning in coming decades. Discussions on the new researches efforts beingcarried out in the area of investigation of the end state of fuel debris and Boling Water reactor (BWR)specific core melt progression, development of technologies for the mitigation of radiological releases tocomply with the strengthened safety requirement set after the Fukushima accident are discussed.
목차
등록된 정보가 없습니다.
참고문헌 (29)
참고문헌 신청
IAEA / 2015 / The Fukushima Daiichi Accident, vols. 1 - 4
J. Rempe / 2017 / Safety insights from forensics evaluations at Daiichi / Nuclear Materials and Energy 10:18~34
D. Peko / 2018 / Working together to enhance nuclear reactor safety / Nucl. News :36~42
M. Pellegrini / 2019 / Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project / 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR
2015 / Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant (BSAF Project)
J. Rempe / 2017 / Safety insights from forensics evaluations at Daiichi / Nuclear Materials and Energy 10:18~34
D. Peko / 2018 / Working together to enhance nuclear reactor safety / Nucl. News :36~42
M. Pellegrini / 2019 / Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project / 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Portland, OR
2015 / Benchmark Study of the Accident at the Fukushima Daiichi Nuclear Power Plant (BSAF Project)
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
Study on Radiological Inventory Assessment of K 1 Reactor Vessel
한국방사성폐기물학회 학술대회
2019 .01
-
Estimation of In-plant Source Term Release Behaviors from Fukushima Daiichi Reactor Cores by Forward Method and Comparison with Reverse Method
방사선방어학회지
2017 .01
-
Analysis of Fukushima Accident in Resilience Engineering Perspective Using the FRAM (Functional Resonance Analysis Method)
대한인간공학회지
2018 .06
-
EXPERIMENTAL STUDY ON DEVELOPMENT OF EX-VESSEL DEBRIS BED WITH INCLINED BOTTOM SURFACE
대한기계학회 춘추학술대회
2020 .12
-
Fukushima Mapping Project After the Fukushima Dai-ichi Nuclear Power Station Accident
한국방사성폐기물학회 학술대회
2018 .01
-
EXPERIMENTAL INVESTIGATIONS RELEVANT FOR HYDROGEN AND FISSION PRODUCT ISSUES RAISED BY THE FUKUSHIMA ACCIDENT
Nuclear Engineering and Technology
2015 .01
-
Reactor Vessel Water Level Estimation During Severe Accidents Using Cascaded Fuzzy Neural Networks
Nuclear Engineering and Technology
2016 .06
-
COMPASS - New modeling and simulation approach to PWR in-vessel accident progression
Nuclear Engineering and Technology
2019 .01
-
CURRENT RESEARCH AND DEVELOPMENT ACTIVITIES ON FISSION PRODUCTS AND HYDROGEN RISK AFTER THE ACCIDENT AT FUKUSHIMA DAIICHI NUCLEAR POWER STATION
Nuclear Engineering and Technology
2015 .01
-
Characteristics of debris resulting from simulated molten fuel coolant interactions in SFRS
Nuclear Engineering and Technology
2024 .01
-
Evaluating direct vessel injection accident-event progression of AP1000 and key figures of merit to support the design and development of water-cooled small modular reactors
Nuclear Engineering and Technology
2024 .06
-
Event/accident Simulation Model of the Reactor Pressure Vessel Internal Segmentation Activity
한국방사성폐기물학회 학술대회
2019 .01
-
EVALUATION OF HEAT-FLUX DISTRIBUTION AT THE INNER AND OUTER REACTOR VESSEL WALLS UNDER THE IN-VESSEL RETENTION THROUGH EXTERNAL REACTOR VESSEL COOLING CONDITION
Nuclear Engineering and Technology
2015 .01
-
Analysis on the discharge characteristics and spreading behavior of an ex-vessel core melt in the SMART
Nuclear Engineering and Technology
2022 .12
-
OVERVIEW ON HYDROGEN RISK RESEARCH AND DEVELOPMENT ACTIVITIES: METHODOLOGY AND OPEN ISSUES
Nuclear Engineering and Technology
2015 .01
-
Influence of an in-vessel debris bed on the heat load to a reactor vessel under an IVR condition
Nuclear Engineering and Technology
2023 .01
-
후쿠시마 원전 사건을 통한 안전문화 측면 고찰
한국에너지학회 학술발표회
2015 .11
-
Radioactive Waste Treatment for Release of Korea Research Reactor Site
한국방사성폐기물학회 학술대회
2017 .01
-
Numerical analysis on in-core ignition and subsequent flame propagation to containment in OPR1000 under loss of coolant accident
Nuclear Engineering and Technology
2022 .08
-
Corium Weight Effect on the RPV Lower-head during Severe Accident Condition
대한기계학회 춘추학술대회
2019 .11
이 논문의 저자 정보
최근 본 자료
댓글(0)
0