Source term characterization program for the decommissioning waste from a CANDU reactor

摘要

An automatic source term characterization program was developed, and its structure, logic, and function are explained here in detail. Called the CANDU Activated Source Term Evaluator (CASE), the developed program is equipped with a convenient graphical user interface; it uses MCNP for the neutron transport calculation and ORICEN2 for activation analysis. CASE can prepare the MCNP input and run MCNP to obtain the neutron flux and the cross section. It can also prepare the ORIGEN2 input for the activation analysis of the region of interest, process the ORIGEN2 output, and compare the estimated specific activity of activated waste with the waste classification standard. CASE is expected to be very useful for reducing the engineering time, minimizing human error, and enhancing the reliability of source term evaluations of decommissioning waste from CANDU reactors.