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논문 기본 정보
- 자료유형
- 학술대회자료
- 저자정보
- 발행연도
- 2014.11
- 수록면
- 3,035 - 3,040 (6page)
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초록· 키워드
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A Direct Vessel Injection (DVI) of Emergency Core Cooling System(ECCS) water is increasingly adopted instead of the conventional cold leg injection system in the recently constructed and proposed reactors. In such a design, however, it may be concerned that the ECCS water injected through the DVI nozzle is easily bypassed to the broken cold leg by the cross flow of high speed steam in the downcomer during the reflood phase of a postulated large break loss-of-coolant accident (LBLOCA). Thus, an Emergency Core Barrel Duct (ECBD) is introduced to reduce the ECC bypass flow in the advanced DVI (DVI+) system for the recent APR+ reactor. In this study, the effects of the cross steam flow on DVI+ water injection has been numerically investigated by CFD analysis for a simple/air-water system with the ECBD. It was observed that the inflow rate into the ECBD is strongly dependent on the cross flow. As a result, the loss coefficients for the system thermal-hydraulic code to analyse the effect of the ECBD was determined by the CFD results. The result of this study on the cross flow effect on DVI+ water injection can be applied to analyse the performance evaluation of the ECBD on the reactor safety using the nuclear system code.
목차
Abstract
1. 서론
2. CFD 해석 모델
3. 결과 및 논의
4. 결론
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