A model for nuclear research reactor dynamics

被引:5
|
作者
Barati, Ramin [1 ]
Setayeshi, Saeed [1 ]
机构
[1] Amirkabir Univ Technol, Tehran Polytech, Fac Nucl Engn & Phys, Tehran, Iran
关键词
THERMAL-HYDRAULICS; KINETICS; SIMULATION; MATLAB; SCOPE;
D O I
10.1016/j.nucengdes.2013.04.036
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
In this paper, a useful thirty-fourth order model is presented to simulate the kinetics and dynamics of a research reactor core. The model considers relevant physical phenomena that govern the core such as reactor kinetics, reactivity feedbacks due to coolant and fuel temperatures (Doppler effects) with variable reactivity coefficients, xenon, samarium, boron concentration, fuel burn up and thermal hydraulics. WIMS and CITVAP codes are used to extract neutron cross sections and calculate the initial neuron flux respectively. The purpose is to present a model with results similar to reality as much as possible with reducing common simplifications in reactor modeling to be used in different analyses such as reactor control, functional reliability and safety. The model predictions are qualified by comparing with experimental data, detailed simulations of reactivity insertion transients, and steady state for Tehran research reactor reported in the literature and satisfactory results have been obtained. (C) 2013 Elsevier RV. All rights reserved.
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页码:251 / 263
页数:13
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