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[en] 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. (author)
Source
International Atomic Energy Agency, Vienna (Austria); 443 p; ISSN 1011-4289; 
; Jun 2000; p. 403-434; 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; 46 refs, 25 figs, 3 tabs
; Jun 2000; p. 403-434; 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; 46 refs, 25 figs, 3 tabs