Three-dimensional analysis of flow and heat transfer in a wire-wrapped fuel assembly

Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05

Volumn 1, Issue , 2005, Pages 325-331

  Ahmad, Imteyaz ^a   Kim, Kwang Yong ^a  

^a Inha University   (South Korea)

Author keywords

[No Author keywords available]

Indexed keywords

FLOW PATTERNS; NAVIER STOKES EQUATIONS; NUCLEAR REACTORS; NUSSELT NUMBER; PRESSURE DROP; REYNOLDS NUMBER; THERMAL GRADIENTS; TURBULENCE;

FUEL ASSEMBLY; REYNOLDS AVERAGED NAVIER STOKES EQUATIONS (RANS); SUBCHANNEL VELOCITY DISTRIBUTION;

NUCLEAR FUELS;

EID: 34249055223     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (14)

1. M. H. FONTANA, "Temperature distribution in the duct wall and at the exit of a 19-rod simulated LMFBR fuel assembly (FFM-2A)," ORNL-4852, Oak Ridge National Laboratory, Apr. (1973).
2. R. M. ROIDT, M. D. Carelli, and R. A. Markley, "Experimental investigations of the hydraulic field in wire-wrapped LMFBR core assemblies," Nuclear Engineering and Design 62, 295-321 (1980).
3. F.C. ENGEL, B. Minushkin, R.J. Atkins, and R.A. Markley, "Characterization of heat transfer and temperature distribution in an electrically heated model of an LMFBR blanket assembly," Nuclear Engineering and Design, 62, 335-347(1980).
4. MOON-HYUN CHUN and Kyong-Won Seo, "An experimental study and assessment of existing friction factor correlations for wire-wrapped fuel assemblies," Annals of Nuclear Energy, 28, 1683-1695(2001).
5. S. K. CHOI, K. Choi, H. Y. Nam, J. H. Choi, and H. K. Choi, "Measurement of Pressure Drop in a full-scale fuel assembly of a Liquid Metal Reactor," Journal of Pressure Vessel Technology, 125(May 2003).
6. E.U. KHAN, W.M. Rohsenw, A.A. Sonin and N.E. Todreas, "A porous body model for predicting temperature distribution in wire-wrapped fuel rod assemblies," Nuclear Engineering and Design, 35, 1-12(1975).
7. WILLIAM T. SHA, "An overview on rod-bundle Thermal-Hydraulic analysis," Nuclear Engineering and Design, 62, 1-24(1980).
8. "CFX-5.7 Solver Theory," Ansys Inc., 2004.
9. MENTER, F., and Esch, T, 2001, "Elements of Industrial Het Transfer Predictions," 16th Bazilian Congress of Mechanical Engineeing (CPBEM), Uberlandia, Brazil.
10. S.K. CHENG and N.E. Todreas, "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, 92, 227-251(1986).
11. KWANG-YONG KIM and Jun-Woo Seo, "Numerical Optimization for The Design of A Spacer Grid with Mixing Vane in A Pressurized Water Reactor Fuel Assembly," Nuclear Technology, 149, 62-70(2005).
12. th Edition, pp-467-493.
13. H.M. KIM and K.Y. Kim, "Design Optimization of rib-roughened channel to enhance turbulent heat transfer," Int. J. Heat and Mass Transfer, 47, 5159-5168(2004).
14. X.Z. GUI and K.Y. Kim, "Three dimensional analysis of turbulent heat transfer and flow through mixing vane in a subchannel of nuclear reactor," Journal of Nuclear Science and Techonology, 40, 10, 719-724(2003).