Neutron-Physical Model Impact on the Calculation of a Serious Accident with Sodium Boiling in a Fast Reactor.

Autor:	Ashurko, Yu., Volkov, A., Raskach, K., Solomonova, N.
Předmět:	COOLANT loss in water cooled reactors SODIUM compounds NUCLEAR reactor accident prevention POWER plants NEUTRONS
Zdroj:	Atomic Energy; Aug2017, Vol. 122 Issue 4, p217-225, 9p
Abstrakt:	A comparative analysis is made of calculations of a loss-of-coolant accident in a 1500 MW(t) fast reactor. The COREMELT code with different neutron-physical modules RADAR3D and RAKAR2D and the same thermohydraulic module COREMELT are used. The computational results are used as a basis for comparing the self-protection of a reactor with a sodium cavity at the top of the core for the case of a serious accident with coolant boiling. The effect of the diffusion and transport modules of the spatial neutron-physics models on the calculation is analyzed. [ABSTRACT FROM AUTHOR]
Databáze:	Complementary Index
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