Validação da metodologia de geração de seções de choque no formato NEMTAB

Abstract

In several situations of interest, the neutron-thermohydraulic coupling of nuclear codes are important tools used for safety analysis. Within this context, the Department of Nuclear Engineering at UFMG, in collaboration with international institutions, has been using the coupled system PARCS (Pardue Advanced Reactor Core Simulator) / RELAP5 (Reactor Excursion and Leak Analysis Program). For the representation of the studied system, it is necessary to generate the macroscopic cross sections that feed the neutronic system, simulated through the PARCS code. The neutron simulation, dependent on the coolant temperature, will be fed back through thermo-hydraulic calculations of the RELAP code. Within this context, a thesis was developed presenting the cross section generation methodology using the WIMSD-5B cell calculation code (Winfrith Improved Multigroup Scheme). The objective of this work is to use the methodology already developed and create an automated cross section generation platform, according to the system and conditions chosen by the user. The cross sections will be written in NEMTAB format, the format used by the PARCS neutron analysis code. Furthermore, both the methodology and the platform will be validated through their application to a benchmark.