Fast Reactors and Accelerator Driven Systems Knowledge Base
Conference Article: Numerical simulation of fuel assembly thermohydraulics of fast reactors with the partial blockage of cross section under the coolant
Zhukov, A.V.; Sorokin, A.P. (State Scientific Center of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))Abstract
The problems of numerical modeling of thermohydraulics in assembly of fuel elements of fast reactors with the partial blockage of cross-section under the coolant are considered. The information about existing codes constructed on use of subchannel technique and model of porous body are presented. The results of calculation obtained by these codes are presented.
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key words: computer codes; fast reactors; flow blockage; fluid flow; fuel assemblies; hydrodynamics; mathematical models
- 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:296-321
- International Atomic Energy Agency, Vienna (Austria)