Contents
Thermal Engineering

Vol. 49, No. 11, 2002

The Creation of Computer Codes of the New Generation:
An Important Problem in Russian Nuclear Power Engineering

B. I. Nigmatulin, V. A. Vasilenko, and S. L. Solov’ev p. 879  abstract

Experience in Creating the Thermohydraulic Computer Code
of the New Generation KORSAR and Its Main Characteristics

V. A. Vasilenko, Yu. A. Migrov, S. N. Volkova, Yu. V. Yudov, I. G. Danilov,
V. G. Korotaev, V. V. Kut’in, B.R. Bondarchik, and D. V. Benediktov p. 888  abstract

A Two-Fluid Model of Unsteady Circuit Thermohydraulics
and Its Numerical Realization in the KORSAR Computer Code

Yu. V. Yudov p. 895  abstract

The Closing Relationships of the Thermohydraulic Model of the KORSAR Computer Code

Yu. V. Yudov, S. N. Volkova, and Yu. A. Migrov p. 901  abstract

The Specifics of Simulation of the Hydrodynamics of Stratified
and Annular-Dispersed Two-Phase Flow Patterns
in the KORSAR Computer Code

Yu. V. Yudov p. 909  abstract

The Distinguishing Features of Modeling Limitations
on Countercurrent Phase Flow with the KORSAR Computer Code

A. A. Sulatskii, Yu. V. Yudov, and B. R. Bondarchik p. 916  abstract

Matrices for Verification of Best Estimate Thermohydraulic Codes Applied to VVER Reactors

Yu. A. Bezrukov, S. A. Logvinov, A. I. Suslov, and S. L. Solov’ev p. 922  abstract

Experimental Investigations on ISB-VVER and PSB-VVER Integral Facilities
for Verification of Thermohydraulic Codes

M. P. Gashenko, I. A. Lipatov, I. I. Shmal’, G. I. Dremin, S. A. Galchanskaya,
A. A. Rovnov, S. M. Nikonov, Yu. S. Gorbunov, A. S. Moloshnikov,
I. V. Elkin, Yu. A. Migrov, S. N. Volkova, and Yu. V. Yudov p. 929  abstract

Verifying the Burnout and Post-Burnout Heat-Transfer Calculation
Models Incorporated in the KORSAR Computer Code

Yu. A. Bezrukov and V. I. Shchekoldin p. 937  abstract

Numerical Simulation of Emergency Regimes of a VVER-1000 Nuclear Reactor
by the TRAP and the KORSAR Computer Codes

Yu. V. Belyaev, S. I. Zaitsev, S. N. Volkova, A. N. Gudoshnikov, Yu. A. Migrov, and Yu. V. Yudov p. 943  abstract

Verifying the Post-Burnout Heat-Transfer Model of the Thermohydraulic Code KORSAR

A. A. Veremeev, A. A. Ivashkevich, I. P. Smogalev,
V. N. Vinogradov, A. D. Efanov, and V. V. Sergeev p. 948  abstract

Model Experiments and Calculations (by the TIGR-BRS Code)
for Investigating the Temperature and the Velocity Fields
in the Cores of Heavy Coolant Reactors

Yu. A. Kuzina and A. G. Sila-Novitskii p. 953  abstract

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