工程计算快堆准备群常数的交叉软件模块

V. Koscheev, I. Tormischev, V. Mischin, A. Peregudov, K. Raskach, M. Semenov, A. Yakunin
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引用次数: 0

摘要

这项工作的目的是测试CROSSER高速常数准备模块,以便在快堆中子物理特性的工程计算实践中使用。快中子反应堆BN-600、BN-800和BN-1200的计算模型作为测试任务。计算了以下中子物理参数:反应器模型的临界性、CPS的效率和钠空洞反应性系数。主反应堆功能是使用MMKK工程程序计算的,其常数是使用CROSSER模块准备的。MMKK项目的初始核数据集是ABBN-93常数库和基于ROSFOND-2010库获得的ABBN-RFE格式的常数。采用对粒子能量进行详细跟踪的MMKC程序计算结果作为参考计算结果。从ROSFOND 2010库中获得的ACE格式的详细数据被用作该计划的初始核数据。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
CROSSER - SOFTWARE MODULE FOR PREPARATION GROUP CONSTANTS FOR ENGINEERING CALCULATIONS FAST REACTORS
The purpose of this work was to test the CROSSER high-speed constant preparation module for use in the practice of engineering calculations of the neutron-physical characteristics of fast reactors. Computational models of fast reactors BN-600, BN-800 and BN-1200 were used as test tasks. The following neutron-physical parameters were calculated: the criticality of the reactor model, the efficiency of the CPS and the sodium void coefficient of reactivity. The main reactor functionals were calculated using the MMKK engineering program, the constants for which were prepared using the CROSSER module. The initial sets of nuclear data for the MMKK program were the ABBN-93 library of constants and the constants in the ABBN-RFE formats obtained on the basis of the ROSFOND-2010 library. The results obtained using the MMKC program with detailed tracking of the particle energy were used as the reference calculation results. Detailed data in ACE format obtained from the ROSFOND 2010 library were used as the initial nuclear data for this program.
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