Tabular method of calculating the critical heat flux in water-cooled triangular rod assemblies
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A new method of calculating the critical heat flux in fuel-rod assemblies is presented. The method is based on a generalization of the experimental data in tabular form. The table for the critical heat fluxes is constructed for the correct macrocells of triangular bundles with relative rod spacing s/d=1/4 and a 9.36 mm heat diameter of a microcell for the following conditions: no effect due to peripheral zones and unheated rods; turbulizing influence of the entrance conditions and spacers; and, the heating along the length and across assemblies is uniform. To use the table for other, quite wide regions of the determining parameters, relations are presented for calculating the effect of the important parameters: heating diameter, relative rod spacing in the assembly, distance to the entrance (heated length), turbulizing influence of the spacers, and others. 1 figure, 1 table, 9 references.
KeywordsCritical Heat Flux Mass Velocity Ring Channel Critical Cross Section Steam Content
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- 1.V. P. Bobkov, V. N. Vinogradov, and P. L. Kirillov, “Critical heat flux in triangular rod bundles (skeleton tables, 1997 version),”Preprint FÉI-2603 (1998).Google Scholar
- 2.V. P. Bobkov, P. L. Kiriilov, I. P. Smogalev, and V. N. Vinogradov, “Look up tables developing methods for critical heat flux in rod bundles,”Report for NURETH-9 (1997).Google Scholar
- 3.D. Groeneveld, J. Joober, L. Leung, et al., “the effect of fuel subchannel geometry on CHF,” in:Proceedings of NURETH-5, Salt Lake City (1992), Vol. 3, pp. 683–690.Google Scholar
- 4.V. P. Bobkov, “Basic laws for crisis in rod bundles and other complex channels,” in:Proceedings of the 1st Russian Conference on Heat Transfer (1994), Vo. 4, pp. 32–37.Google Scholar
- 5.V. P. Bobkov, M. N. Vinogradov, O. A. Zyatnina, and N. V. Kozina, “Description of the critical heat flux in rod bundles and other complicated channels,” in:Proceedings of International Conference on the Thermophysical Aspects of Safety, Obninsk (1995), Vol. 1, pp. 143–154.Google Scholar
- 6.V. P. Bobkov, M. N. Vinogradov, O. A. Zyatnina, and N. V. Kozina, “Method for describing crisis in channels with a complicated cross section,”Teploénergetika, No. 3, 37–46 (1995).Google Scholar
- 7.V. P. Bobkov, M. N. Vinogradov, O. A. Zyatnina, and N. V. Kozina, “Relative description of crisis in rod assemblies and other complicated channels,”ibid., No. 3, 1–7 (1997).Google Scholar
- 8.Yu. V. Mironov, N. S. Razina, and S. V. Shpanskii, “Bundle 2B—program for thermohydraulic analysis of two-phase flows in rod assemblies taking account of the nonhomogeneous structure of a transverse mixing flow,” in:Thermophysical Investigations to Ensure Safety of Water-Moderated Water-Cooled Type Nuclear Reactors, Seminar TF-78, Budapest (1978), Vol. 2, pp. 761–774.Google Scholar
- 9.Ya. Koshtyalek and F. Svitak, “Assessment of models for transverse mass and energy transfer in analysis with respect to cells of fuel-rod bundles,”ibid., in:Thermophysical Investigations to Ensure Safety of Water-Moderated Water-Cooled Type Nuclear Reactors, Seminar TF-78, Budapest (1978), Vol. 2, pp. 775–790.Google Scholar