Optimization of the Safety Characteristics of the Generation IV Super Critical Water Reator

在这里，我们建议基于以下两个考虑因素来分析第四代核系统SCWR的核安全性能：卓越的安全性和可靠性，以及极低的反应堆堆芯损坏可能性和程度。由于SCWR是一个核系统，它的一般行为由反应堆物理控制，反应堆物理用于预测堆芯中中子的数量随时间的变化，以及由于堆芯性能变化而导致的反应性变化。这些变化可能在反应堆运行时发生，必须评估它们对反应堆安全的影响。还必须最大限度地减少假定的事故情景可能导致的堆芯损坏的可能性。这意味着选择一种燃料配置，使冷却剂空隙和功率反应性系数为负值，同时优化燃料消耗。最后，还必须评估反应性控制机制和停堆系统在运行条件下或在事故情况下的效率，因为它们对确保反应堆的安全起着重要作用。

Here we propose to analyze the nuclear safety performance of the SCWR, a Generation IV nuclear system, 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. These changes may take place as the reactor operates and their impact on the reactor safety must be assessed. One must also minimize the likelihood of core damage that could result from postulated accident scenarios. This implies selecting a fuel configuration that will make the coolant void and power reactivity coefficients negative while optimizing fuel consumption. Finally, the efficiency of the reactivity control mechanism and shutdown systems for operation conditions or during accident scenarios must also be assessed since they play an important role to ensure the safety of the reactor.