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
- 학술대회자료
- 저자정보
- 발행연도
- 2019.11
- 수록면
- 949 - 952 (4page)
이용수
초록· 키워드
오류제보하기
Severe accidents in nuclear plants result in the relocation of molten core material in the lower plenum of the reactor vessels. As preventive measure to reduce accident progression during the event, an In-Vessel-Retention (IVR) strategy was developed through external vessel cooling process. Without appropriate cooling, the lower-head may fail from combined effects of thermal, pressure and dead-weight loading of the vessel. This study undertook 2D thermosmechanical analysis of the RV involving TLFW scenario has been done using ANSYS 2019VR1. High temperatures to tune of 50000C have been established over 15000 seconds simulation and with the loading conditions, static structural analysis predict failure of the vessel at 13,305 seconds.
목차
Abstract
1. Introduction
2. Methods and Results
3. Conclusions
REFERENCES
참고문헌 (0)
참고문헌 신청함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
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
-
An interactive multiple model method to identify the in-vessel phenomenon of a nuclear plant during a severe accident from the outer wall temperature of the reactor vessel
Nuclear Engineering and Technology
2021 .02
-
Failure simulation of nuclear pressure vessel under LBLOCA scenarios
Nuclear Engineering and Technology
2024 .07
-
Event/accident Simulation Model of the Reactor Pressure Vessel Internal Segmentation Activity
한국방사성폐기물학회 학술대회
2019 .01
-
단열재 조건에 따른 원자로용기 외벽냉각 성능 예비분석
한국압력기기공학회 논문집
2023 .06
-
EXPERIMENTAL STUDY ON DEVELOPMENT OF EX-VESSEL DEBRIS BED WITH INCLINED BOTTOM SURFACE
대한기계학회 춘추학술대회
2020 .12
-
설계방식에 따른 초고압 반응용기의 구조적 특성에 관한 연구
한국정밀공학회 학술발표대회 논문집
2018 .05
-
Multi-dimensional finite element analyses of OECD lower head failure tests
Nuclear Engineering and Technology
2022 .12
-
Enhancement of Downward-Facing Saturated Boiling Heat Transfer by the Cold Spray Technique
Nuclear Engineering and Technology
2017 .01
-
Reactor Vessel Water Level Estimation During Severe Accidents Using Cascaded Fuzzy Neural Networks
Nuclear Engineering and Technology
2016 .06
-
Experimental Validation of Longitudinal Control of a Platoon of Vessels Established via the V-REP Simulator
INTERNATIONAL JOURNAL of FUZZY LOGIC and INTELLIGENT SYSTEMS
2019 .12
-
유한요소해석을 이용한 100L-700MPa 급 초고압용기 설계 기법 개발
한국정밀공학회 학술발표대회 논문집
2019 .05
-
최적화 설계를 통한 혼합가스 성능시험용 고온 고압 용기의 제작
한국기계가공학회지
2019 .11
-
Numerical study on thermal-hydraulics of external reactor vessel cooling in high-power reactor using MARS-KS1.5 code: CFD-aided estimation of natural circulation flow rate
Nuclear Engineering and Technology
2022 .01
-
다변량 관리도를 활용한 선박 메인 엔진의 이상 관리 상한선 결정에 관한 연구
대한조선학회 논문집
2018 .12
-
Function of Motion Detection for Small-Size Vessel using Smart Phone
한국인터넷방송통신학회 논문지
2016 .01
-
COMPASS - New modeling and simulation approach to PWR in-vessel accident progression
Nuclear Engineering and Technology
2019 .01
-
혁신형 안전경수로의 원자로용기 외벽냉각 시 2상 자연순환 유동에 대한 수치해석적 연구
에너지공학
2019 .12
-
Study on Prediction of Failure Behavior of Composite Pressure Vessel Using Explicit Finite Element Analysis
한국철도학회 논문집
2024 .09
-
CSPACE for a simulation of core damage progression during severe accidents
Nuclear Engineering and Technology
2021 .12
이 논문의 저자 정보
최근 본 자료
댓글(0)
0