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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2009.1
- 수록면
- 617 - 648 (32page)
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초록· 키워드
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Under the government supported long-term nuclear R&D program, the severe accident research program at KAERI is
directed to investigate unresolved severe accident issues such as core debris coolability, steam explosions, and hydrogen
combustion both experimentally and numerically. Extensive studies have been performed to evaluate the in-vessel retention
of core debris through external reactor vessel cooling concept for APR1400 as a severe accident management strategy.
Additionally, an improvement of the insulator design outside the vessel was investigated. To address steam explosions, a
series of experiments using a prototypic material was performed in the TROI facility. Major parameters such as material
composition and void fraction as well as the relevant physics affecting the energetics of steam explosions were investigated.
For hydrogen control in Korean nuclear power plants, evaluation of the hydrogen concentration and the possibility of
deflagration-to-detonation transition occurrence in the containment using three-dimensional analysis code, GASFLOW, were
performed. Finally, the integrated severe accident analysis code, MIDAS, has been developed for domestication based on
MELCOR. The data transfer scheme using pointers was restructured with the modules and the derived-type direct variables
using FORTRAN90. New models were implemented to extend the capability of MIDAS.
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참고문헌 (28)
참고문헌 신청
/ 1998 / Korea Electric Power Research Institute, Workshop on Invessel retention for the KNGR severe accident management (1998)
A.W. Cronenberg / 1978 / Vapor Explosion Phenomena with Respect to Nuclear Reactor Safety Assessment
B. C. Lee / 1997 / Development and Application of Two- Dimensional Hydrogen Mixing Model in Containment Subcompartment Under Severe Accidents / J. Korean Nucl. Soc. 29 : 2 ~
D. Magallon / 2005 / European expert network for the reduction of uncertainties in severe accident safety issues (EURSAFE) / Nuclear Engineering and Design 235 : 309 ~ 346
D. Magallon / 2006 / SERENA (Steam Explosion Resolution for Nuclear Applications) Final Report
A.W. Cronenberg / 1978 / Vapor Explosion Phenomena with Respect to Nuclear Reactor Safety Assessment
B. C. Lee / 1997 / Development and Application of Two- Dimensional Hydrogen Mixing Model in Containment Subcompartment Under Severe Accidents / J. Korean Nucl. Soc. 29 : 2 ~
D. Magallon / 2005 / European expert network for the reduction of uncertainties in severe accident safety issues (EURSAFE) / Nuclear Engineering and Design 235 : 309 ~ 346
D. Magallon / 2006 / SERENA (Steam Explosion Resolution for Nuclear Applications) Final Report
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