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Kazachkovskij, O.D.; Sorokin, A.P.; Zhukov, A.V.; Ushakov, P.A.; Bogoslovskaya, G.P.; Kriventsev, V.I.; Titov, P.A.
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Obninsk. Fiziko-Ehnergeticheskij Inst1985
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Obninsk. Fiziko-Ehnergeticheskij Inst1985
AbstractAbstract
[en] Mathematical model for the calculation of velocity and temperature fields in deformed fuel bundles of fast reactors is described; the brief description of the program and test calculation is presented. Thermohydraulic analysis is based on the solution of the equation system of mass, momentum and energy balance for characteristic cells. The fuel bundle region is devided in to above characteristics cells. Maximum values of temperature of fuel element cans and variations of temperature about the fuel element perimeter are estimated. Test calculation made for the Phenix reactor has shown a considerable increase of variations of temperature about the perimeter of fuel elements in deformed fuel bundle in comparison with a reference one
Original Title
Metod sosredotochennykh parametrov v zadache o temperaturnom pole v formoizmenennykh TVS bystrykh reaktorov s neadiabaticheskimi granichnymi usloviyami
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1985; 23 p; 31 refs.; 5 figs.; 1 tab.
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