Estimation of the fuel temperature reactivity coefficient of the UMass-Lowell research reactor based on empirical and theoretical point reactor kinetics models

被引：0
|
作者：
Boffie, J. [1 ]
Aghara, S. K. [1 ]
Dim, O. U. [1 ]
Strandburg, J. [1 ]
机构：
[1] Univ Massachusetts Lowell, Dept Chem Engn, Nucl Engn Program, Lowell, MA 01854 USA
来源：
NUCLEAR ENGINEERING AND DESIGN | 2021年 / 381卷
关键词：
Inverse kinetics; Reactivity feedbacks; Transients; Nonlinear equation; Feedback coefficient; SCHEME;
D O I：
10.1016/j.nucengdes.2021.111341
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
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.
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页数：8
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