Page 239 - Dynamics and Control of Nuclear Reactors

APPENDIX A Generation II reactor parameters 239

Table A.3 Typical BWR nuclear steam supply system (NSSS).
Reactor thermal power 3579M W
x 1220 MWe
Coolant pressure (two-phase) 1040 psia (70bar)
Feedwater flow rate 14,414,400lb./h (1,820kg/s)
6
Total core coolant flow rate 104 10 lb./h (13,131kg/s)
Steam (coolant) temperature 551°F (288°C)
Feedwater temperature 420°F (216°C)
Steam flow rate 14,414,400lb./h (1,820kg/s)
General Electric Company, BWR/6: General Description of a Boiling Water Reactor, San Jose, 1980;
U.S. NRC Technical Training Center, Boiling Water Reactor (BWR) Systems, Chapter 3, Revisions
0200, 0400.
Adapted from A.V. Nero, Jr., A Guidebook to Nuclear Reactors, University of California Press, Berkeley,
1979; J. Buongiorno, BWR Description, MIT OpenCourseWear, 22.06: Engineering of Nuclear Systems,
Massachusetts Institute of Technology, Cambridge, MA, 2010.

Table A.4 Typical BWR pressure vessel and core parameters.
Overall vessel height 71ft (21.7m)
Inside diameter of vessel 238 in. (6.05m)
Average vessel thickness 6 in. (15.4cm)
Nominal vessel cladding thickness 1/8 in. (0.32cm)
Vessel material Mn-Mo-Ni steel
Vessel cladding material Austenitic stainless steel
3
3
Coolant volume in vessel 4520ft (128m )
Number of fuel assemblies 748
Core (fuel rod) active length 150 in. (381cm)
Fuel assembly array 8 8 (enclosed fuel array)
Fuel weight in the core (Uranium) 155,000kg
Average fuel burnup 28,400 MWd/Te of heavy metal
Equivalent core diameter 15ft 13 in. (490cm)
Heat generated in fuel 97.4%
Total number of fuel rods in core 46,376
Fuel rod cladding material Zircaloy-4
Number of rods (drives) 185 (193 in BWR-6)
General Electric Company, BWR/6: General Description of a Boiling Water Reactor, San Jose, 1980;
U.S. NRC Technical Training Center, Boiling Water Reactor (BWR) Systems, Chapter 3, Revisions
0200, 0400.
Adapted from A.V. Nero, Jr., A Guidebook to Nuclear Reactors, University of California Press, Berkeley,
1979; J. Buongiorno, BWR Description, MIT OpenCourseWear, 22.06: Engineering of Nuclear Systems,
Massachusetts Institute of Technology, Cambridge, MA, 2010.