Designing an efficient reactor core simulation strategy for the Canadian-SCWR

超临界水反应堆是第四代能源系统，其设计基于以下两个考虑：卓越的安全性和可靠性以及反应堆堆芯损坏的可能性和程度非常低。由于超临界水反应堆是一个核系统，它的一般行为是由反应堆物理控制，这是用来预测随着时间的推移，以及在反应堆的变化所造成的变化，在核心的中子的人口在核心属性。在这里，我们建议设计一个有效的模拟策略的基础上，在反应堆物理数值模拟的超临界水反应堆。这意味着选择能够模拟堆芯配置的反应堆物理软件，在软件和模拟策略中实施新模型，以提高分析精度，并优化正常运行条件或事故情景下的反应性控制机制和停堆系统。

The Canadian-SCWR is a Generation IV energy system that is designed based on the following two considerations: excellence in safety and reliability and a very low likelihood and degree of reactor core damage. Because the SCWR is a nuclear system, its general behavior is controlled by reactor physics, which is used to predict the population of neutrons in the core with time as well as the changes in reactivity resulting from variation in the core properties. Here we propose to design an efficient simulation strategy for the Canadian-SCWR based on numerical simulation in reactor physics. This implies selecting reactor physics software that can model the core configuration, implementing new models in the software and in the simulation strategy to improve the precision of the analysis and optimize the reactivity control mechanism and shutdown systems for normal operation conditions or during accident scenarios.