Numerical simulation of the thermohydraulics of reactor fuel assemblies with blockages

Author:

Kuzina Yu. A.,Sorokin A. P.,Zhukov A. V.

Publisher

Springer Science and Business Media LLC

Subject

Nuclear Energy and Engineering

Reference65 articles.

1. A. V. Zhukov, P. L. Kirillov, N. M. Matyukhi, et al.,Thermohydraulic Calculations of Fuel Assemblies of Fast Reactors with Liquid Metal Coolant [in Russian], Énergoatomizdat, Moscow (1985).

2. A. V. Zhukov, A. P. Sorokin, and N. M. Matyukhin,Interchannel Transfer in the Fast-Reactor Fuel Assemblies: Computer Codes and Practical Applications [in Russian], Énergoatomizdat, Moscow (1991).

3. A. V. Zhukov, A. P. Sorokin, and V. V. Khudasko,Effect of Thermohydraulic Factors on the Safety of Reactor Fuel Assemblies [in Russian], Textbook, IATÉ, Obninsk (1990).

4. A. V. Zhukov, Yu. N. Kornienko, A. P. Sorokin, et al., “Methods for calculation of fuel assemblies taking account of the interchannel interaction of the coolant”,Analytical Review, FÉI, OB-107 (1990).

5. A. V. Zhukov, A. P. Sorokin, P. A. Ushakov, et al., “Channel thermohydraulic calculations of nuclear reactor fuel assemblies”At. Énerg.,51, No. 5, 307–311 (1981).

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