Page 237 - Dynamics and Control of Nuclear Reactors

APPENDIX

Generation II reactor

parameters A

This Appendix contains tables of important parameters of typical pressurized
water reactors, boiling water reactors, and CANDU reactors. The tables list the
parameters for representative reactor systems.

A.1 Pressurized water reactor (PWR)

Tables A.1 and A.2 summarize important parameters of a typical four-loop
pressurized water reactor [1, 2].

Table A.1 Typical four-loop PWR nuclear steam supply system (NSSS).

Reactor thermal power 3411MW
Approximate electrical power generation 1150 MWe
Number of U-tube steam generators 4
Steam generator tube material Thermally coated Inconel-600
Steam pressure 1000 psia (69bar)
Steam flow rate per steam generator 3,813,000lb./h (480kg/s)
Steam generator overall height 67ft 8in. (20.6m)
Steam generator upper shell outer diameter 14ft 7–3/4in. (4.5m)
Steam generator lower shell outer diameter 11ft 3in. (3.4m)
Steam generator shell material Mn-Mo steel
Reactor coolant pump motor horsepower 7000
Hot leg inner diameter 29 in. (73.7cm)
Cold leg inner diameter 27.5 in. (69.9cm)
6
Total coolant flow rate 138.4 10 lb./h (17,438kg/s)
Primary coolant pressure 2250 psia (155bar)
Adapted from The Westinghouse Pressurized Water Reactor Nuclear Power Plant, Westinghouse
Electric Company, Nuclear Operations Division, Pittsburgh, 1984; M. Naghedolfeizi, B.R. Upadhyaya,
Dynamic Modeling of a Pressurized Water Reactor Plant for Diagnostics and Control, Research Report,
University of Tennessee, DOE/NE/88ER12824-02, June 1991.

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