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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 저널정보
- 대한기계학회 Journal of Mechanical Science and Technology Journal of Mechanical Science and Technology Vol.20 No.9
- 발행연도
- 2006.9
- 수록면
- 1,514 - 1,524 (11page)
이용수
초록· 키워드
오류제보하기
This work presents the three-dimensional analysis of flow and heat transfer performed for a wire-wrapped fuel assembly of liquid metal reactor using Reynolds-averaged Navier-Stokes analysis in conjunction with SST model as a turbulence closure. The whole fuel assembly has been analyzed for one period of the wire-spacer using periodic boundary conditions at inlet and outlet of the calculation domain. Three different assemblies, two 7-pin wire-spacer fuel assemblies and one bare rod bundle, apart from the pressure drop calculations for a 19-pin case, have been analyzed. Individual as well as a comparative analysis of the flow field and heat transfer have been discussed. Also, discussed is the position of hot spots observed in the wire-spacer fuel assembly. The flow field in the subchannels of a bare rod bundle and a wire-spacer fuel assembly is found to be different. A directional temperature gradient is found to exist in the subchannels of a wire-spacer fuel assembly. Local Nusselt number in the subchannels of wirefuel assemblies is found to vary according to the wire-wrap position while in case of bare rod bundle, it's found to be constant.
목차
영어 초록
1. Introduction
2. Analysis Methods
3. Results and Discussion
4. Conclusions
Acknowledgements
References
참고문헌 (25)
참고문헌 신청
CFX-5.7 Solver Theory,2004, Ansys Inc.
Cheng, S. K. and Todreas, N. E., 1986, "Hydrodynamic Models and Correlations for Bare and Wire-Wrapped Hexagonal rod Bundles-Bundle Friction Factors, Subchannel Friction Factors and Mixing Parameters," Nuclear Engineering and Design, Vol.92, pp.227~251.
Choi, S. K., Choi, K., Nam, H. Y., Choi, J. H. and Choi, H. K., 2003, "Measurement of Pressure Drop in a Full-Scale Fuel Assembly of a Liquid Metal Reactor," Journal of Pressure Vessel Technology, Vol.125.
Chun, M. H. and K. W. Seo, 2001, "An Experimental Study and Assessment of Existing Friction Factor Correlations for Wire-Wrapped Fuel Assemblies," Annals of Nuclear Energy, Vol.28, pp.1683~1695.
Coffield, R. D. and Markley, R. A., 1980, "Natural Convection Analysis and Verification for LMFBR Cores," Nuclear Engineering and Design, Vol.62, pp.181~198.
Cheng, S. K. and Todreas, N. E., 1986, "Hydrodynamic Models and Correlations for Bare and Wire-Wrapped Hexagonal rod Bundles-Bundle Friction Factors, Subchannel Friction Factors and Mixing Parameters," Nuclear Engineering and Design, Vol.92, pp.227~251.
Choi, S. K., Choi, K., Nam, H. Y., Choi, J. H. and Choi, H. K., 2003, "Measurement of Pressure Drop in a Full-Scale Fuel Assembly of a Liquid Metal Reactor," Journal of Pressure Vessel Technology, Vol.125.
Chun, M. H. and K. W. Seo, 2001, "An Experimental Study and Assessment of Existing Friction Factor Correlations for Wire-Wrapped Fuel Assemblies," Annals of Nuclear Energy, Vol.28, pp.1683~1695.
Coffield, R. D. and Markley, R. A., 1980, "Natural Convection Analysis and Verification for LMFBR Cores," Nuclear Engineering and Design, Vol.62, pp.181~198.
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