0
Research Papers: Nuclear Power

CANDU Reactor Space-Time Kinetic Model for Load Following Studies

[+] Author and Article Information
Lingzhi Xia

Department of Electrical and Computer Engineering, The University of Western Ontario, London, ON, N6A 5B9, Canadalxia4@uwo.ca

Jin Jiang

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, Chinajjiang@eng.uwo.ca

J. Eng. Gas Turbines Power 133(5), 052915 (Dec 21, 2010) (9 pages) doi:10.1115/1.4002870 History: Received July 23, 2010; Revised July 26, 2010; Published December 21, 2010; Online December 21, 2010

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.

FIGURES IN THIS ARTICLE
<>
Copyright © 2011 by American Society of Mechanical Engineers
Your Session has timed out. Please sign back in to continue.

References

Figures

Grahic Jump Location
Figure 1

Positions of zone control detectors with respect to zone compartments (viewed from the opposite of the pressurizer’s end)

Grahic Jump Location
Figure 2

Nine neutron flux harmonic modes ψI(R) (CANDU6 type), I=1−9

Grahic Jump Location
Figure 3

SIMULINK module of reactor kinetic modeling

Grahic Jump Location
Figure 4

Simplified reactor regulating system block diagram

Grahic Jump Location
Figure 5

Simulation result of reactor bulk power control (1.0–0.9 FPU at a rate of 1% FP/s)

Grahic Jump Location
Figure 6

Simulation result of reactor power spatial control (1.0–0.9 FPU at a rate of 1% FP/s)

Grahic Jump Location
Figure 7

LZU water level transient simulation result (xenon effect excluded)

Grahic Jump Location
Figure 8

LZU water level transient simulation result (xenon effect included)

Grahic Jump Location
Figure 9

Simulation result of xenon dynamic reactivity

Grahic Jump Location
Figure 10

Comparison of four power transients’ simulations at different power changing rates

Grahic Jump Location
Figure 11

Neutron flux distribution within the first layer (end face) along the axial direction

Grahic Jump Location
Figure 12

Neutron flux distribution within the second layer along the axial direction

Grahic Jump Location
Figure 13

Neutron flux distribution within the third layer along the axial direction

Grahic Jump Location
Figure 14

Neutron flux distribution within the fourth layer along the axial direction

Grahic Jump Location
Figure 15

Neutron flux distribution within the fifth layer along the axial direction

Grahic Jump Location
Figure 16

Neutron flux distribution within the sixth layer (central plane) along the axial direction

Grahic Jump Location
Figure 17

Neutron flux distribution along a fuel channel next to the central axis

Tables

Errata

Discussions

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In