Development of high-fidelity neutron transport code STREAM

Abstract

This paper presents a methodology developed and implemented in the neutron transport code STREAM to perform high-fidelity, multicycle, multiphysics simulations of light water reactor whole-core problems. STREAM uses state-of-the-art methodologies to achieve high accuracy and computational performance. Further, it can compute fine-mesh neutron transport solutions for three-dimensional (3D) whole-core problems using the 3D method of characteristics/diamond-difference (MOC/DD). For multigroup calculation, STREAM generates problem-dependent multigroup cross-sections using intrinsic cross-section libraries and a resonance self-shielding method. To perform the multicycle analysis of commercial power reactors, many advanced methods and features have been developed and implemented. In this paper, the methodologies and features of STREAM are presented, followed by the whole-core simulation capability.