AECL has developed the design for a next generation of CANDU® plants by marrying a set of enabling technologies to well-established successful CANDU features. The basis for the design is to replicate or adapt existing CANDU components for a new core design. By adopting slightly enriched uranium fuel, a core design with light water coolant, heavy water moderator and reflector has been defined, based on the existing CANDU fuel channel module. This paper summarizes the main features and characteristics of the reference next-generation CANDU design. The progress of the next generation of CANDU design program in meeting challenging cost, schedule and performance targets is described. AECL’s cost reduction methodology is summarized as an integral part of the design optimization process. Examples are given of cost reduction features together with enhancement of design margins.
Skip Nav Destination
10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3596-0
PROCEEDINGS PAPER
Next Generation CANDU Technology: Competitive Design for the Nuclear Renaissance
J. M. Hopwood,
J. M. Hopwood
Atomic Energy of Canada, Ltd., Mississauga, ON, Canada
Search for other works by this author on:
K. R. Hedges,
K. R. Hedges
Atomic Energy of Canada, Ltd., Mississauga, ON, Canada
Search for other works by this author on:
M. Pakan
M. Pakan
Atomic Energy of Canada, Ltd., Mississauga, ON, Canada
Search for other works by this author on:
J. M. Hopwood
Atomic Energy of Canada, Ltd., Mississauga, ON, Canada
K. R. Hedges
Atomic Energy of Canada, Ltd., Mississauga, ON, Canada
M. Pakan
Atomic Energy of Canada, Ltd., Mississauga, ON, Canada
Paper No:
ICONE10-22643, pp. 1037-1042; 6 pages
Published Online:
March 4, 2009
Citation
Hopwood, JM, Hedges, KR, & Pakan, M. "Next Generation CANDU Technology: Competitive Design for the Nuclear Renaissance." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 2. Arlington, Virginia, USA. April 14–18, 2002. pp. 1037-1042. ASME. https://doi.org/10.1115/ICONE10-22643
Download citation file:
7
Views
Related Proceedings Papers
Related Articles
Nuclear Fission, Today and Tomorrow: From Renaissance to Technological Breakthrough (Generation IV)
J. Pressure Vessel Technol (August,2011)
Effect of CANDU Bundle-Geometry Variation on Dryout Power
J. Eng. Gas Turbines Power (March,2009)
Steady-State Safety Analysis of Ghana Research Reactor-1 With Low-Enriched-Uranium Core
J. Thermal Sci. Eng. Appl (October,2020)
Related Chapters
Design of Indian Pressurized Heavy Water Reactors
Global Applications of the ASME Boiler & Pressure Vessel Code
Insights and Results of the Shutdown PSA for a German SWR 69 Type Reactor (PSAM-0028)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Nuclear Fuel Cycle
Non-Proliferation Nuclear Forensics: Canadian Perspective