Determination of the Radiochemical Yield of Fission-Fragment 99Mo In VVR-Ts

Abstract

The parameters of the neutron flux in the experimental channels of VVR-Ts are determined. It is shown that to evaluate the ⁹⁹Mo yield it is necessary to take account of, aside from the neutron flux, the dependence of the fission cross section of ²³⁵U on the temperature of the neutron gas. The blocking coefficient is calculated for an experimental uranium target. The computed radiochemical yield of ⁹⁹Mo is compared with the experimentally measured value. It is shown that the average yield equals 0.75. A correlation is found between the neutron flux density, which is directly proportional to the power of the VVR-Ts nuclear reactor, at the target location and the radiochemical yield of ⁹⁹Mo.