ALGORISM FOR CALCULATING GENERATION AND DEPLETION OF RADIOACTIVE NUCLIDES IN MULTI-NEUTRON-SPECTRA-REGION SYSTEM

摘要

PURPOSE: A method is provided to simply calculate the nuclide concentration of a multi-region molten salt reactor by using one group multi-dimensional equation. CONSTITUTION: A matrix A is composed by using the half life about the M-number of regions and a nuclear reaction cross section library. A nuclear fuel initial configuration, a nuclear fuel flow rate, purification process property, and retreatment process property are inputted. The matrix A is re-organized in consideration of influence due to the nuclear fuel flow. The neutron flux is calculated. The matrix A is readjusted. The nuclide concentration of the M-number of regions is calculated.