The Canadian Supercritical Water-Cooled Reactor (SCWR) is a 1200 MW(e) channel-type nuclear reactor. The reactor core includes 336 vertical pressurized fuel channels immersed in a low-pressure heavy water moderator and calandria vessel containment. The supercritical water (SCW) coolant flows into the fuel channels through a common inlet plenum and exits through a common outlet header. One of the main features of the Canadian SCWR concept is the high-pressure (25 MPa) and high-temperature (350°C at the inlet, 625°C at the outlet) operating conditions that result in an estimated thermal efficiency of 48%. This is significantly higher than the thermal efficiency of the present light water reactors, which is about 33%. This paper presents a description of the Canadian SCWR core design concept; various numerical analyses performed to understand the temperature, flow, and stress distributions of various core components; and how the analyses results provided input for improved concept development.
Skip Nav Destination
Article navigation
January 2016
Research Papers
Various Design Aspects of the Canadian Supercritical Water-Cooled Reactor Core
Metin Yetisir,
Metin Yetisir
Fluid Sealing Technology,
Canadian Nuclear Laboratories Limited,
e-mail:metin.yetisir@cnl.ca
Canadian Nuclear Laboratories Limited,
Chalk River Laboratories
, 286 Plant Road, Chalk River, ON K0J 1J0
, Canada
e-mail:metin.yetisir@cnl.ca
Search for other works by this author on:
Rui Xu,
Rui Xu
Fluid Sealing Technology,
Canadian Nuclear Laboratories Limited,
e-mail: rui.xu@cnl.ca
Canadian Nuclear Laboratories Limited,
Chalk River Laboratories
, 286 Plant Road, Chalk River, ON K0J 1J0
, Canada
e-mail: rui.xu@cnl.ca
Search for other works by this author on:
Michel Gaudet,
Michel Gaudet
Fluid Sealing Technology,
Canadian Nuclear Laboratories Limited,
e-mail: michel.gaudet@cnl.ca
Canadian Nuclear Laboratories Limited,
Chalk River Laboratories
, 286 Plant Road, Chalk River, ON K0J 1J0
, Canada
e-mail: michel.gaudet@cnl.ca
Search for other works by this author on:
Mohammad Movassat,
Mohammad Movassat
Fluid Sealing Technology,
Canadian Nuclear Laboratories Limited,
e-mail: mo.movassat@cnl.ca
Canadian Nuclear Laboratories Limited,
Chalk River Laboratories
, 286 Plant Road, Chalk River, ON K0J 1J0
, Canada
e-mail: mo.movassat@cnl.ca
Search for other works by this author on:
Holly Hamilton,
Holly Hamilton
Fuel Development Branch,
Canadian Nuclear Laboratories Limited,
Canadian Nuclear Laboratories Limited,
Chalk River Laboratories
, 286 Plant Road, Chalk River, ON K0J 1J0
, Canada
Search for other works by this author on:
Mohammedhossein Nimrouzi,
Mohammedhossein Nimrouzi
Mechanical and Aerospace Engineering,
e-mail: mh.nimrouzi@gmail.com
Carleton University
, 1125 Colonel By Dr., Ottawa, ON K1S 5B6
, Canada
e-mail: mh.nimrouzi@gmail.com
Search for other works by this author on:
John A. Goldak
John A. Goldak
Mechanical and Aerospace Engineering,
e-mail: jgoldak@mrco2.carleton.ca
Carleton University
, 1125 Colonel By Dr., Ottawa, ON K1S 5B6
, Canada
e-mail: jgoldak@mrco2.carleton.ca
Search for other works by this author on:
Metin Yetisir
Fluid Sealing Technology,
Canadian Nuclear Laboratories Limited,
e-mail:metin.yetisir@cnl.ca
Canadian Nuclear Laboratories Limited,
Chalk River Laboratories
, 286 Plant Road, Chalk River, ON K0J 1J0
, Canada
e-mail:metin.yetisir@cnl.ca
Rui Xu
Fluid Sealing Technology,
Canadian Nuclear Laboratories Limited,
e-mail: rui.xu@cnl.ca
Canadian Nuclear Laboratories Limited,
Chalk River Laboratories
, 286 Plant Road, Chalk River, ON K0J 1J0
, Canada
e-mail: rui.xu@cnl.ca
Michel Gaudet
Fluid Sealing Technology,
Canadian Nuclear Laboratories Limited,
e-mail: michel.gaudet@cnl.ca
Canadian Nuclear Laboratories Limited,
Chalk River Laboratories
, 286 Plant Road, Chalk River, ON K0J 1J0
, Canada
e-mail: michel.gaudet@cnl.ca
Mohammad Movassat
Fluid Sealing Technology,
Canadian Nuclear Laboratories Limited,
e-mail: mo.movassat@cnl.ca
Canadian Nuclear Laboratories Limited,
Chalk River Laboratories
, 286 Plant Road, Chalk River, ON K0J 1J0
, Canada
e-mail: mo.movassat@cnl.ca
Holly Hamilton
Fuel Development Branch,
Canadian Nuclear Laboratories Limited,
Canadian Nuclear Laboratories Limited,
Chalk River Laboratories
, 286 Plant Road, Chalk River, ON K0J 1J0
, Canada
Mohammedhossein Nimrouzi
Mechanical and Aerospace Engineering,
e-mail: mh.nimrouzi@gmail.com
Carleton University
, 1125 Colonel By Dr., Ottawa, ON K1S 5B6
, Canada
e-mail: mh.nimrouzi@gmail.com
John A. Goldak
Mechanical and Aerospace Engineering,
e-mail: jgoldak@mrco2.carleton.ca
Carleton University
, 1125 Colonel By Dr., Ottawa, ON K1S 5B6
, Canada
e-mail: jgoldak@mrco2.carleton.ca
Manuscript received May 25, 2015; final manuscript received July 14, 2015; published online December 9, 2015. Assoc. Editor: Thomas Schulenberg.
ASME J of Nuclear Rad Sci. Jan 2016, 2(1): 011007 (8 pages)
Published Online: December 9, 2015
Article history
Received:
May 25, 2015
Revision Received:
July 14, 2015
Accepted:
August 5, 2015
Citation
Yetisir, M., Xu, R., Gaudet, M., Movassat, M., Hamilton, H., Nimrouzi, M., and Goldak, J. A. (December 9, 2015). "Various Design Aspects of the Canadian Supercritical Water-Cooled Reactor Core." ASME. ASME J of Nuclear Rad Sci. January 2016; 2(1): 011007. https://doi.org/10.1115/1.4031247
Download citation file:
Get Email Alerts
Cited By
Heat Flux Correlations for Condensation From Steam and Air Mixtures on Vertical Flat Plates
ASME J of Nuclear Rad Sci (April 2025)
Radiation Monitoring for Volatilized Zinc Contamination Using Gamma-Ray Imaging and Spectroscopy
ASME J of Nuclear Rad Sci (April 2025)
Related Articles
European Project “Supercritical Water Reactor–Fuel Qualification Test”: Overview, Results, Lessons Learned, and Future Outlook
ASME J of Nuclear Rad Sci (January,2016)
Design of an In-Pile SCWR Fuel Qualification Test Loop
ASME J of Nuclear Rad Sci (January,2016)
Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept
ASME J of Nuclear Rad Sci (July,2020)
Concept of a Small Modular SCWR With Horizontal Fuel Assemblies
ASME J of Nuclear Rad Sci (July,2022)
Related Proceedings Papers
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 Materials and Basic Properties
Fundamentals of Nuclear Fuel