CANDU Reactor Space-Time Kinetic Model for Load Following Studies-Reference-Cited by-同舟云学术

CANDU Reactor Space-Time Kinetic Model for Load Following Studies

Published:2010-12-21 Issue:5 Volume:133 Page:
ISSN:0742-4795
Container-title:Journal of Engineering for Gas Turbines and Power
language:en
Short-container-title:

Author:

Xia Lingzhi¹,Jiang Jin²

Affiliation:

1. Department of Electrical and Computer Engineering, The University of Western Ontario, London, ON, N6A 5B9, Canada

2. Department of Electrical and Computer Engineering, The University of Western Ontario, London, ON, N6A 5B9, Canada; Institute of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, Shaanxi 710049, China

Abstract

Abstract This paper presents the development of a three-dimensional space-time neutronic kinetic model of a Canadian deuterium uranium (CANDU) reactor using a modal method. In this method, the reactor space-time neutron flux is synthesized by a time-weighted series of precalculated neutron flux modes. The modes are eigenfunctions of the governing neutron diffusion equation during reference steady-state operation. The xenon effect has also been considered. The reactor model is then implemented within a simulation platform of a CANDU6 reactor regulating system in MATLAB/SIMULINK. A nondimensionalized SIMULINK representation of the reactor kinetic model is established. The behavior of the reactor during load following transients has been simulated using the developed reactor-modeling module. The simulation results prove the efficiency of the model. A three-dimensional neutron flux distribution during transients is represented.

Publisher

ASME International

Subject

Mechanical Engineering,Energy Engineering and Power Technology,Aerospace Engineering,Fuel Technology,Nuclear Energy and Engineering

Link

http://asmedigitalcollection.asme.org/gasturbinespower/article-pdf/133/5/052915/6754775/052915_1.pdf

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