CALCULATION OF NEUTRON AND GAMMA-RAY DOSE RATES BY THE USE OF THE MONTE CARLO CODE MCU
24th Symposium of AER on VVER Reactor Physics and Reactor Safety (2014, Sochi, Russia)
Advances in spectral and core calculation methods
Abstract
CALCULATION OF NEUTRON AND GAMMA-RAY DOSE RATES BY THE USE OF THE MONTE CARLO CODE MCU
Oleynik D.S.
NRC “Kurchatov institute”, Moscow, Russia,
ABSTRACT
Neutron and gamma-ray dose rate calculations are important part of the process of substantiation of radiation safety. Generally these rates are required in a point or surface at some distance from spent fuel.
The MCU code has been updated for that purposes, that is a point and ring detectors estimation and also surface flux tally have been included. Verification and validation of the code has been performed for VVER spent fuel storages and shipping casks using 38 measurements and 204 computational tasks. Uncertainty of the calculations has been formulated in the result of V&V.
Updated version of the MCU code provides neutron and gamma-ray dose rate calculations for substantiation of radiation safety of VVER spent fuel.