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
- 2011.11
- 수록면
- 119 - 124 (6page)
이용수
초록· 키워드
오류제보하기
A dual-cooled annular nuclear fuel has been introduced for a significant increase in reactor power. The KAERI has been researching the development of a dual-cooled annular fuel for a power increase in an optimized PWR in Korea, OPR-1000. The pitch-to-diameter ratio of the annular fuel assembly is decreased in order to maintain the fuel amount ratio within the same assembly size as the solid fuel assembly. In the tight lattice rod bundle, a pressure loss for the rod friction may be definitely different from that in the conventional solid fuel assembly. In this study, the friction loss of the 4x4 or 5x5 bare rod bundles without the obstacles such as the spacer grids is measured for the pitch-to-diameter 1.08 and 1.35, respectively. The measured results are compared with the general correlations for the conventional rod bundle. CFD studies are performed to investigate the friction pressure loss for the simulated single rod geometry and the spacer grid effects in the rod bundle is estimated in the view of a friction loss for a rod.
목차
1. 서론
2. 압력손실측정 실험
3. 봉다발 압력손실 CFD
4. 결론
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UCI(KEPA) : I410-ECN-0101-2013-422-001395494