Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Natural convection as the way of heat removal from fast reactor core at cooldown regimes

Zhukov, A.V.; Kuzina, J.A.; Uhov, V.A.; Sorokin, G.A. (State Scientific Centre of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))

Abstract

The problems of thermohydraulics in fast reactors at cooldown regimes at heat removal by natural convection are considered. The results of experiments and calculations obtained in various countries in this area are presented. The special attention is given to heat removal through inter-assembly space in the core and also to problems of thermohydraulics in the upper plenum.

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key words: after-heat removal; calculation methods; fast reactors; fuel assemblies; hydrodynamics; natural convection; reactor cores; thermal analysis
Reference:
Technical committee meeting on methods and codes for calculations of thermohydraulic parameters for fuel, absorber pins and assemblies of LMFR's with traditional and burner cores. Obninsk (Russian Federation) 27-31 Jul 1998
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1157, pp:396-427