Abstract:
Calculation of reactor core neutron source is one the most important procedures of neutron fluence rate calculation for the reactor vessel. A neutron source calculation code SCON was developed with Fortran for VVER with hexagonal fuel assemblies. Balakovo-3VVER-1000 benchmark problem and the neutron transport calculation code system DOORS were used to validate SCON. The results showed that the calculated results agree well with the reference results. It proves that the SCON code can provide accurate neutron source for the neutron transport calculation of the units with hexagonal fuel assemblies. It also proves that the neutron fluence rate calculation code system applies to the RPV neutron fluence calculation for VVER units.