CACA-2:REVISED VERSION OF CACA - A HEAVY ISOTOPE AND FISSION-PRODUCT CONCENTRATION CALCULATIONAL CODE FOR EXPERIMENTAL IRRADIATION CAPSULES

摘要

This report describes a computer program which calculates nuclide concentration histories, power or neutron flux histo¬ries, burnups, and fission-product birthrates for fueled ex¬perimental capsules subjected to neutron irradiations. Sev¬enteen heavy nuclides in the chain from 232Th to 21f2Pu and a user-specified number of fission products are treated. A fourth-order Runge-Kutta calculational method solves the dif¬ferential equations for nuclide concentrations as a function of time. For a particular problem, a user-specified number of fuel regions may be treated. A fuel region is described by volume, length, and specific irradiation history. A num¬ber of initial fuel compositions may be specified for each fuel region. The irradiation history for each fuel region can be divided into time intervals, and a constant power density or a time-dependent neutron flux is specified for each time interval.