Use of AZTRAN v.3.0 in the Pin-By-Pin neutron analysis of a SMR type Smart/KSMR

This paper describes the use of AZTRAN v.3.0 software in the neutron modeling of a generic core for a small modular reactor type KSMR, a substitute for the core of the Korean Smart reactor and under development by the Karlsruhe Institute of Technology in Germany. The code is part of the AZTLAN platform and is implemented in Fortran 90, OpenMP and Mpi, it solves in parallel the time-dependent neutron transport equation for three-dimensional nuclei with Cartesian geometry. In the past, this code has been executed for particular cases of the C5G7 MOX benchmark in steady state and time-dependent TWIGL-3-Dimensional, obtaining solutions close to the reference ones and highly satisfactory results in relation to the acceleration method through hybrid parallelization. The KSMR is a square PWR type reactor core with 300 MW(Th) output and a relatively small number of square assemblies and was considered a good candidate for evaluating software performance in a real industrial environment without requiring a excessive computational power and in reasonable execution times. However, the high heterogeneities and leakage that are generally associated with SMRs are factors that should be thoroughly examined during the analysis of results. The quality of the results obtained for the time-independent core model with fully extracted control rods, in addition to the tools developed to visualize the results, are proof that the project is on the right track and that AZTRAN is emerging as a domestic tool at take into account for the analysis of nuclear reactors, while the experience obtained during this process indicates that to achieve the adoption of the platform by the industry, it is necessary to integrate improvements in the user interface and ease of use, which in turn suggests a direction for the improvement of the platform in the short and medium term. (author)