Calculation of spectrum and neutron flux density in experimental channels of WWR-M reactor

Abstract

A program for calculating the spectra and densities of neutron fluxes in the experimental channels of the research reactor WWR-M was developed. To do this, the reactor core was modeled. Irradiation of neutron activation detectors was performed. The obtained experimental rates of nuclear reactions are consistent with the calculated within 10 %.

Keywords

• research reactor
• geant4
• neutron spectrum
• neutron flux density
• neutron activation detector
• reaction rate.