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.