Page 241 - Dynamics and Control of Nuclear Reactors

APPENDIX A Generation II reactor parameters 241

Table A.6 CANDU pressure vessel and core parameters. Continued
Fuel weight in the core 95,000kg
(Uranium)
Average fuel burnup 7000 MWd/Te of Uranium
Equivalent core diameter 248 in. (6.3m)
Nominal core coolant inlet 512°F (267°C)
temperature
Core coolant outlet 594°F (312°C)
temperature
Average coolant temperature 82°F (45°C)
rise in core
Moderator Heavy water (99.75% D 2 O)
6
Total heavy water inventory 1.02 10 lb. (463,000kg)
Moderator inlet temperature 110°F (43°C)
Moderator outlet temperature 160°F (71°C)
Moderator pressure Approximately atmospheric (1bar)
Total number of fuel rods in 168,720
core
Fuel rod cladding material Zircaloy-4
Number of control rods or Between 4 and 21 of each of light water compartments,
compartments adjustable absorbers, shutdown absorber rods or
poison injection ports.
W.J. Garland (Editor-in-Chief), The Essential CANDU: A textbook on the CANDU Nuclear Power Plant
Technology, University Network of Excellence in Nuclear Engineering (UNENE), McMaster University,
Retrieved from https://www.unene.ca/education/candu-textbook, 2019.
Adapted from A.V. Nero, Jr., A Guidebook to Nuclear Reactors, University of California Press, Berkeley,
1979.

References
[1] The Westinghouse Pressurized Water Reactor Nuclear Power Plant, Westinghouse Elec-
tric Company, Nuclear Operations Division, Pittsburgh, 1984.
[2] M. Naghedolfeizi and B.R. Upadhyaya, Dynamic Modeling of a Pressurized Water Reac-
tor Plant for Diagnostics and Control, Research Report, University of Tennessee, DOE/
NE/88ER12824-02, June 1991.
[3] A.V. Nero Jr., A Guidebook to Nuclear Reactors, University of California Press, Berkeley,
1979.
[4] General Electric Company, BWR/6: General Description of a Boiling Water Reactor, San
Jose, 1980.
[5] U.S. NRC Technical Training Center, Boiling Water Reactor (BWR) Systems, Chapter 3,
Revisions 0200, 0400, 2018.
[6] J. Buongiorno, BWR Description, MIT OpenCourseWear, 22.06: Engineering of Nuclear
Systems, Massachusetts Institute of Technology, Cambridge, MA, 2010.
[7] W.J. Garland, Editor-in-Chief, The Essential CANDU: A Textbook on the CANDU
Nuclear Power Plant Technology, University Network of Excellence in Nuclear Engineer-
ing (UNENE), McMaster University, 2019. Retrieved from, https://www.unene.ca/educa
tion/candu-textbook.