For every reactor design, sensitivity, uncertainty and transient analysis have huge importance in identifying the fundamental physical processes and critical points in a system. In the Institute of Nuclear Techniques, we pay special attention to perform these types of studies in fundamentally different ways. One of our main codes, the SEnTRi (Sensitivity and Transient investigator), targets these analyses with a deterministic approach. The code utilizes the PARTISN, discrete ordinate neutron transport code as a neutronic solver to perform sensitivity calculation with the linear perturbation theory and transient analysis with a direct and a predictor-corrector quasistatic approach. Multiple studies have already been performed with SEnTRi code for fast reactor designs and on the BME Training Reactor.
Z. I. Böröczki, M. Szieberth, F. Gabrielli, A. Rineiski: "On the effect of angular and spatial discretization on perturbation calculations", Journal of Computational and Theoretical Transport, Taylor & Francis, (2020), 1-17. DOI
Z. I. Böröczki, B. Molnár, G. Klujber, G. Tolnai, D. Legrady, F. Gabrielli, A. Rineiski, M. Szieberth: "Simulation of a research reactor reactivity transient with deterministic and GPU-assisted Monte Carlo reactor kinetics codes", The European Physical Journal Plus [2.612] 135-281 (2020) 1-18. DOI
Z. I. Böröczki: "Sensitivity analysis with the PARTISN discrete ordinates neutron transport code", Proceedings of the PhD workshop of the Physics Doctoral School at the Faculty of Science Budapest University of Technology and Economics (ed. F. Simon), Budapest, Hungary, 2018.07.06, ISBN: 978-963-313-293-7