Horizontal steam generator thermal-hydraulics at various steady-state power levels

International Conference on Nuclear Engineering, Proceedings, ICONE

Volumn 3, Issue , 2002, Pages 767-779

  Stevanovic, Vladimir D ^a   Stosic, Zoran V ^a   Kiera, Michael ^a   Stoll, Uwe ^a  

^a FRAMATOME ANP GMBH   (Germany)

Author keywords

[No Author keywords available]

Indexed keywords

HORIZONTAL STEAM GENERATOR; STEAM STATE POWER LEVELS; THERMAL HYDRAULICS;

COMPUTER SIMULATION; MATHEMATICAL MODELS; NUCLEAR POWER PLANTS; THREE DIMENSIONAL;

STEAM GENERATORS;

EID: 0036387967     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1115/ICONE10-22451     Document Type: Conference Paper

References (8)

1. Rassohin, N. G., Nuclear Power Plant Steam Generators, Moskva, Atomizdat, 1980.
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3. Melikhov, V. I., Melikhov, O. I., and Nigmatulin, B. I., Thermal-Hydraulics Analysis of Horizontal Steam Generator, Proceedings, Symp. Two-Phase Flow Modelling and Experimentation, Vol. 1, pp. 511-518, 1995.
4. Stevanovic, V., Studovic, M., Depisch, F. and Kiera, M., 3D Modeling as a Support to Thermal-Hydraulic Safety Analyses with Standard Codes, Proc. 7th International Conference on Nuclear Engineering, ICONE-7, 1999.
5. Patankar, S. V., Numerical Heat Transfer and Fluid Flow, Hemisphere, 1980.
6. Ageev, A. G., Vaslyeva, R. V., Dmitriev, A. I., Tarankov, G. A., and Titov, V. F., Investigation of Hydrodynamics of Steam Generator PGV-1000, Elektricheskie stancii, No. 6, pp. 19-23, 1987 (in Russian).
7. Pylev, S., Roginskaja, V., Elkin, I., Assessment of RELAP5/MOD3.2 on experimental data of water level behaviour in VVER-440 steam generator in two transient regimes with six MCP tripping and stop feedwater on Kola NPP, Nuclear Safety Institute, RRC Kurchatov Institute, Moscow, 1997.
8. RELAP5 Development Team, RELAP5/MOD3 Code Manual, Idaho National Laboratory INEL-95/0174, June 1995.