Using of the Serpent code based on the Monte-Carlo method for calculation of the VVER-1000 fuel assembly characteristics

Abstract

The description of calculation scheme of fuel assembly for preparation of few-group characteristics is considered with help of Serpent code. This code uses the Monte-Carlo method and energy continuous microscopic data libraries. Serpent code is devoted for calculation of fuel assembly characteristics, burnup calculations and preparation of few-group homogenized macroscopic cross-sections. The results of verification simulations in comparison with other codes (WIMS, HELIOS, NESSEL etc.), which are used for neutron-physical analysis of VVER type fuel, are presented.

Keywords

• uel assembly
• VVER-1000
• Monte Carlo method
• reactor calculation
• Serpent
• MCNP
• SCALE
• WIMSD5B