Page 238 - Dynamics and Control of Nuclear Reactors

238 APPENDIX A Generation II reactor parameters

Table A.2 Typical PWR pressure vessel and core parameters.
Overall length of assembled vessel 44ft, 7 in. (13.6m)
Inside diameter of vessel 173 in. (4.4m)
Average vessel thickness 8 in. (20.3cm)
Nominal vessel cladding thickness 7/32 in. (0.56cm)
Vessel material Low-alloy steel
Cladding material Stainless steel
3
3
Coolant volume in vessel 4885ft (138m )
Number of vessel material surveillance capsules 6
Number of fuel assemblies 193
Active fuel length 12ft (365.8cm)
Fuel assembly array 17 17
Fuel weight in the core (Uranium) 81,639kg
Average fuel burnup 32,000 MWd/Te of heavy metal
Equivalent core diameter 11.06ft (338cm)
Nominal core coolant inlet temperature 557.5°F (291.9°C)
Core coolant outlet temperature 618.5°F (325.8°C)
Average coolant temperature rise in vessel 61°F (33.9°C)
Heat generated in fuel 97.4%
Total number of fuel rods in core 50,952
Fuel rod cladding material Zircaloy-4
Number of rods in the control banks 25
Number of rods in the shutdown banks 28
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.

A.2 Boiling water reactor (BWR)
Important parameters of a typical boiling water reactor are listed in Tables A.3 and
A.4 [3–6].

A.3 Pressurized heavy water reactor (PHWR): CANDU reactor

Tables A.5 and A.6 summarize important parameters of a typical CANDU (CANada
Deuterium Uranium) reactor [3, 7].