Page 169 - Dynamics and Control of Nuclear Reactors

166 CHAPTER 12 Pressurized water reactors

2rad/s). Explain why these are considered distinct regions and describe the
physical basis for the behavior shown in each region.

12.7. A PWR is a closed loop feedback system. Recall that a feedback system can be
represented as follows:

G o
G c ¼
1+ G o H
where
G c ¼closed loop transfer function
G o ¼open loop transfer function
H¼feedback transfer function
a. Show that the low frequency response is given by 1/H. What is the phys-
ical basis for this behavior?

b. Show that the high frequency response is given by G o . What is the physical
basis for this behavior?

References

[1] U.S. Nuclear Regulatory Commission, www.nrc.gov/reading-rm/basic-ref/students/for-
educators/04.pdf.
[2] Westinghouse Electric Company, The Westinghouse Pressurized Water Reactor Nuclear
Power Plant, Westinghouse Electric Company, Water Reactor Division, Pittsburgh, 1984.
[3] The Babcock & Wilcox Company, Steam: Its Generation and Use, 42nd ed., The Babcock
& Wilcox Company, 2015.
[4] T.W. Kerlin, Dynamics and control of pressurized water reactors, in: C.T. Leondes (Ed.),
Control and Dynamic Systems, Academic Press, New York, 1978, pp. 103–212.
[5] M. Naghedolfeizi, B.R. Upadhyaya, Dynamic modeling of a pressurized water reactor
plant for diagnostics and control, in: Research Report, University of Tennessee, 1991.
DOE/NE/88ER12824–02, June.

Further reading
[6] F. Bevilaqua, J.F. Gibbons, System-80 combustion engineering’s standard 3800-MWt
PWR, Combustion 45 (14) (1974).
[7] M.R. Ali, Lumped Parameter State Variable Models for U-Tube Recirculation Type
Nuclear Steam Generators, PhD dissertation, Nuclear Engineering Department, The
University of Tennessee, 1976. August.
[8] D.C. Arwood, T.W. Kerlin, A mathematical model for an integral economizer U-tube
steam generator, Nucl. Technol. 35 (1977) 12–32.