Considerations in Describing Burnout in Rod Bundles 1

Thermal Engineering

Volumn 44, Issue 3, 1997, Pages 171-177

  Bobkov, V P ^a   Vinogradov, V N ^a   Zyatnina, O A ^a   Kozina, N V ^a  

^a State Sci Ctr of the Russ Fed   (Russian Federation)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0342895097     PISSN: 00406015     EISSN: None     Source Type: Journal    
DOI: None     Document Type: Article

References (12)

1. Bobkov, V.P., Vinogradov, V.N., Zatnina, O.A., and Kozina, N.V., A Method for Evaluating the Critical Heat Flux in Channels and Cells of an Arbitrary Geometry, Teploenergetika (Moscow), 1995, no. 3, pp. 37-46.
2. Bobkov, V.P., Burnout in Channels Having Different Cross-Sections: The Description Model, Preprint of the Energy Physics Institute, Obninsk, 1993, no. 2313.
3. Bobkov, V.P., Zyatina, O.A., Kozina, N.V., and Sudnitsyn, O.A., Burnout in Channels of Different Cross-Sectional Geometries: A Model and the Results of a Statistical Analysis, Preprint of the Energy Physics Institute, Obninsk, 1993, no. 2314.
4. Groeneveld, D.C., Kirillov, P.L., Bobkov, V.P., et al., The 1994 Lookup Table for Critical Heat Flux in Tubes, Nuclear Engineering and Design, 1996.
5. Groeneveld, D.C., Joober, K., Doefler, S., Wong, L.K.H., and Cheng, S.C., The Effect of Fuel Subchannel Geometry on CHF, Thesis of Report to NURETH-5, 1992.
6. Zhukov, Yu.M., The Possibility of Using Lookup Tables for a Tube in the Calculation of Burnout in Rod Bundles of Water-Cooled Nuclear Reactors, Atomnaya Energiya, 1994, vol. 77, no. 2, pp. 108-111.
7. Mironov, Yu.V. and Shpanskii, S.V., Distribution of Two-Phase Flow Parameters in the Cross-Section of a Channel with Fuel Rod Bundles, Atomnaya Energiya, 1975, vol. 39, no. 6, pp. 403-408.
8. Klochkova, L.F., Sal'nikova, O.V., and Sapankevich, A.P., Approbation of Several Design Recommendations for Calculating the Critical Heat Flux in Rod Bundles, Preprint of the Energy Physics Institute, Obninsk, 1989, no. 1898.
9. Osmachkin, V.S., Burnout with Boiling Water Flowing Along Fuel Rod Bundles Preprint of the Kurchatov Institute of Atomic Energy, Moscow, 1970, no. 2014.
10. Pernitsa, P. and Chizhek, I., Correlation for Burnout in Rod Bundles for the Model of an Individual Channel, Preprint of the Institute of Nuclear Research, Rzhezh, Chechia, 1989, no. 9011 T.
11. Bezrukov, Yu.A., Astakhov, V.I., Brantov, V.B., et al., Experimental Research and a Statistical Analysis of Data on Burnout in Rod Bundles for VVER Reactors, Teploenergrtika (Moscow), 1976, no. 2, pp. 80-82.
12. Dubrovskii, I.S., Yugai, T., Pashchenko, M.P., and Chalykh, A.F., Steady-State and Transient Burnout with a Steam-Water Mixture Flowing Along Rod Bundles, Seminar SEV TF-74, Moscow, 1994, pp. 67-78.