참고문헌
- Rehme, K. and Trippe, G., 1980, Pressure drop and velocity distribution in rod bundle with spacer grids, Nucl. Engng And Design 62, pp. 349-359 https://doi.org/10.1016/0029-5493(80)90038-2
- Rowe, D. S., Johnson, B. M. and Knudsen, J. G., 1974, Implications concerning rod bundle cross flow mixing based on measurements of turbulent flow structure, Int. J. Heat Mass Transfer, 17, pp.407-419 https://doi.org/10.1016/0017-9310(74)90012-X
- Ibragimov, M. K., Isupov, I. V., Kobzar, L. L. and Subbotin, V. I., 1966, Calculation of the tangential stresses at the wall in a channel and the velocity distribution in a turbulent flow of liquid, Atomic Energy 21, pp. 731-739 https://doi.org/10.1007/BF01116588
- Shen, Y. F., Cao, Z. D. and Lu, Q. G., 1991, An investigation of crossflow mixing effect caused by grid spacer with mixing blades in a rod bundle, Nucl. Engng and Design 125, pp. 111-119 https://doi.org/10.1016/0029-5493(91)90071-O
- Yang, S. K. and Chung, M. K., 1996, Spacer grid effects on turbulent flow in rod bundles, J. of KNS, Vol. 28, No.1, p. 56
- Karoutas, Z., Gu, C. Y. and SchoIin, B., 1995, 3- D flow analyses for design of nuclear fuel spacer, Proceedings of the NURETH-7 (NUREG/ CP-0142, Vol. 4), pp.3153-3174
- In, W. K., Oh, D. S. and Chun, T. H., 2001, Flow analysis for optimum- design of mixing vane in a PWR fuel assembly, J. of KNS, Vol. 33, No.3, p, 327
- Park, J. S., 2001, A Study of Turbulent Heat Transfer Performance Enhancement in Rod Bundle Subchannel by the Large Scale Secondary Vortex Flow, Ph. D. thesis, The University of Korea, pp. 13-15,64-66
- Sha, W. T., 1980, An overview on rodbundle thermal hydraulic analysis, Nucl. Engng and Design 62, pp. 1-24 https://doi.org/10.1016/0029-5493(80)90018-7
- KEPCO, 1998, Final Safety Analysis Report For Uljin NPP 3/4, Table 4.4 1, Fig. 4.1 2
- An, J. S. and Choi, Y. D., 2004, A Study of Turbulence Characteristics of Large Scale Vortex Flow Mixing Vane of Nuclear Fuel Rod Bundle, Proceeding of KSME Spring Annal Meeting