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논문 기본 정보
- 자료유형
- 학술대회자료
- 저자정보
- 발행연도
- 2008.11
- 수록면
- 3,175 - 3,180 (6page)
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초록· 키워드
오류제보하기
A metal-fueled pool-type liquid metal fast reactor (LMFR) provides large margins to sodium boiling and fuel damage under accident conditions. The favorable passive safety results are obtained by both a reactivity feedback mechanism in the core and a passive decay heat removal system. Among the various reactivity feedbacks, the ones by a thermal expansion of a radial dimension of the core and by the control rod drivelines are strongly dependent on the flow conditions in the core and the hot pool, respectively. The effects of multidimensional thermal hydraulic characteristics on these reactivity feedbacks are investigated by the system-wide safety analysis code SSC-K with advanced thermal hydraulics models. Particularly a detailed three dimensional thermal hydraulics reactor core model is integrated into SSC-K for use in a whole system analysis of the passive safety aspects of LMR designs. The model provides fuel and cladding temperatures for every fuel pin in a reactor and coolant temperatures for every coolant sub-channel in the reactor.
목차
Abstract
1. INTRODUCTION
2. KALIMER-150 DESIGN
3. COMPUTATIONAL METHODS
4. ACCIDENT ANALYSIS
5. ANALYSIS RESULTS
6. CONCLUSION
ACKNOWLEDGMENTS
REFERENCES
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