NMC CODE FOR STATISTICAL MODELING OF NEUTRON TRANSFER IN FISSILE MEDIA (PREPRINT IBRAE-2012-04)

Preprint IBRAE-2012-04

Brednikhin S.A., Lezhnin S.I., Frolov S.A., Yurov D.M.

The paper describes the structure of NMC, a new generation Monte-Carlo particle transport code. The code is capable to solve a wide range of standard problems such as computation for reactor unit flux. Besides of this it can easily be refined to solve highly specialized tasks with most effective method. The paper presents the results of: code validation with computation of effective multiplication factor and neutron flux energy density function of benchmark experiments from International Handbook Of Evaluated Criticality Safety Benchmark Experiments; neutron-physical characteristics study of the subcritical nuclear assembly, designed to operate in the hybrid fission-fusion system with a neutron source based on plasma gas-dynamic trap (GDT).
Based on the obtained results it is concluded about the possibility of using the code for scientific search purposes for modeling of the neutral particles transport processes as well as for testing new algorithms for statistical modeling.

Bibliographical reference 

Brednikhin S.A., Lezhnin S.I., Frolov S.A., Yurov D.M. NMC CODE FOR STATISTICAL MODELING OF NEUTRON TRANSFER IN FISSILE MEDIA. — Preprint / Nuclear Safety Institute RAS IBRAE-2012-04. — Moscow : NSI RAS, 2012. — 24 p. — Refs.: 10 items.