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.

本文介绍了一种以中子输运代码STREAM开发和实施的方法，以执行轻水反应堆全核心问题的高保真，多周期，多物理场仿真。STREAM使用最先进的方法来实现高精度和计算性能。此外，它可以使用3D特性/金刚石差异（MOC / DD）方法计算三维（3D）全核问题的细孔中子输运解。对于多组计算，STREAM使用固有截面库和共振自屏蔽方法生成与问题相关的多组截面。为了进行商用动力反应堆的多循环分析，已经开发并实施了许多先进的方法和功能。本文介绍了STREAM的方法和功能，