Modeling nuclear reactors for simulating transients can be very challenging for a lot of reasons, e.g. space–time representation, heterogeneity, etc. Reactor-specific design and data may also be required for the facility being analyzed. Although reactor point kinetics theory is usually a method of choice in analyzing such transients, a reactor’s specifications are required to achieve meaningful results. This work describes a unique method for estimating the fuel temperature reactivity coefficient for use with the point reactor kinetics model of the UMass-Lowell Research Reactor. The computed coefficient is later validated with experimental data.

由于许多原因，例如时空表示、异质性等，模拟瞬变的核反应堆建模可能非常具有挑战性。被分析的设施也可能需要特定于反应堆的设计和数据。尽管反应器点动力学理论通常是分析此类瞬变的一种选择方法，但需要反应器的规范才能获得有意义的结果。这项工作描述了一种用于估计燃料温度反应系数的独特方法，该方法与 UMass-Lowell 研究反应堆的点反应堆动力学模型一起使用。计算出的系数稍后会用实验数据进行验证。