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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2015.1
- 수록면
- 66 - 73 (8page)
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초록· 키워드
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Background: A numerical simulation was carried out to investigate the difference betweeninternal and external heat-flux distributions at the reactor vessel wall under in-vesselretention through external reactor vessel cooling (IVR-ERVC).
Methods: Total loss of feed water, station blackout, and large break loss of coolant accidentswere selected as the severe accident scenarios, and a transient analysis using the elementbirth-and-death technique was conducted to reflect the vessel erosion (vessel wall thicknesschange) effect.
Results: It was found that the maximum heat flux at the focusing region was decreased atleast 10% when considering the two-dimensional heat conduction at the reactor vessel wall.
Conclusion: The results show that a higher thermal margin for the IVR-ERVC strategy can beachieved in the focusing region. In addition, sensitivity studies revealed that the heat fluxand reactor vessel thickness are dominantly affected by the molten corium pool formationaccording to the accident scenario
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참고문헌 (11)
참고문헌 신청
F.B. Cheung / 2005 / Limiting factors for external reactor vessel cooling / Nuclear Technology 152 : 145 ~ 161
J. L. Rempe / 2005 / Idaho National Laboratory Report
J.L. Rempe / 2008 / In-vessel retention of molten corium: lessons learned and outstanding issues / Nuclear Technology 161 : 210 ~ 267
K.S. Ha / 2013 / Prediction of boiling-induced natural circulation flow in engineered cooling channels / Nuclear Technology 181 : 133 ~ 143
R.J. Park / 2013 / Evaluation of in-vessel corium retention through external reactor cooling for small integral reactor / Nuclear Engineering and Design 262 : 571 ~ 578
J. L. Rempe / 2005 / Idaho National Laboratory Report
J.L. Rempe / 2008 / In-vessel retention of molten corium: lessons learned and outstanding issues / Nuclear Technology 161 : 210 ~ 267
K.S. Ha / 2013 / Prediction of boiling-induced natural circulation flow in engineered cooling channels / Nuclear Technology 181 : 133 ~ 143
R.J. Park / 2013 / Evaluation of in-vessel corium retention through external reactor cooling for small integral reactor / Nuclear Engineering and Design 262 : 571 ~ 578
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