A setup for active neutron analysis of the fissile material content in fuel assemblies of nuclear reactors

Аннотация

An active neutron method for measuring the residual mass of ²³⁵U in spent fuel assemblies (FAs) of the IRT MEPhI research reactor is presented. The special measuring stand design and uniform irradiation of the fuel with neutrons along the entire length of the active part of the FA provide high accuracy of determination of the residual ²³⁵U content. AmLi neutron sources yield a higher effect/background ratio than other types of sources and do not induce the fission of ²³⁸U. The proposed method of transfer of the isotope source in accordance with a given algorithm may be used in experiments where the studied object needs to be irradiated with a uniform fluence.