BURN-UP EFFECT OF 235U IN A FISSION CHAMBER USED TO MEASURE THE NEUTRON FLUXS

Abstract

Fission chamber is a type of gas-filled detector, is used to measure neutron flux in nuclear reactors, experiments on particle accelerators, medical devices, etc... When the fission chamber is placed under neutron irradiation, one of the important effects is the burnup of fissile material as electrode coating. In the paper, the burnup effect of ²³⁵U in fission chamber using ²³⁵U as electrode coating was investigated. The changing in efficiency of the fission chamber over time due to the burning of ²³⁵U has been considered for neutron fluxes of different forms of the power spectrum.