Fast Reactors and Accelerator Driven Systems Knowledge Base
Conference Article: Methods of statistical calculation of fast reactor core with account of influence of fuel assembly form change in process of campaign and other factors
Sorokin, G.A.; Zhukov, A.V.; Bogoslovskaya, G.P.; Sorokin, A.P. (State Scientific Center of Russian Federation, Institute of Physics and Power Engineering, Obninsk, Kaluga Region (Russian Federation))Abstract
The method of calculation of a temperature field in fast reactor core using criterion equal thermotechnical reliability of subassembles in various zones throttling taking into account change thermohydraulic characteristics of subassembles during campaign under influence change form of core, redistribution heat generation, casual any deviation of various parameters is stated. The distribution of the statistical characteristics of a temperature field in subassembles is calculated on subchannel method with account of an interchannel exchange and feature of influence of deformation on a temperature field in subassembles using Monte-Carlo method. The results of the calculations show that deformation can have significant influence on a temperature mode of core. It is necessary to make thermohydraulic analysis of core during campaign at a stage of preliminary study of the projects fast reactors.
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key words: fast reactors; fuel assemblies; heat transfer; hydrodynamics; monte carlo method; reactor cores; temperature distribution; 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:234-248
- International Atomic Energy Agency, Vienna (Austria)