| description abstract | Methodological processes for nuclear power plant (NPP) pressure vessels' (PV) neutron fluence rate determination take the form of experimental measurement or theoretical calculations. However, the process of experimental measurement takes longer periods, as it requires the incorporation of surveillance capsules into a PV system undergoing normal NPP operation. Therefore, strong reliance on computation and modeling of radiation-induced degradation is given much attention. In this work, the VENUS-3 benchmark has been analyzed using SuperMC code, with the intention of validating SuperMC for accurate reactor neutronics; dosimetry response calculations for in-core/ex-core structural components, particularly with respect to the VENUS-3 configuration type pressurized water reactors (PWRs). In this work, complete three-dimensional (3D) geometry including the source modeling for VENUS-3 facility has been developed with SuperMC. Neutron transport and calculations of equivalent fission flux for the experimental target quantities, 115In (n, n′), 58Ni (n, p), and 27Al (n, α), are also achieved. The calculation results show good agreement with the experimental measurement. The greater majority of the calculated values (C/E) were within the required accuracy of ±10% for reactor components' dosimetry calculations. Most of the calculated values were contained within 5% deviation from the experimental data. Additional calculations and detailed analysis for fast neutron flux distribution and iron displacement per atom rate (dpa/s), including the characteristic effect of partial length shielded assembly (PLSA) on VENUS-3 core barrel, are also discussed. It is therefore evidenced that the effectiveness of SuperMC code for in-core/ex-core reactor neutronics computations has been convincingly demonstrated through the VENUS-3 benchmark testing. | |
