Selecting and qualifying a fuel cladding material for the Canadian supercritical water-cooled reactor (SCWR) concept remains the most significant materials challenge to be overcome. The peak cladding temperature in the Canadian SCWR concept is predicted to be as high as 800°C. While advanced materials show promise for future deployment, currently, the best options available are austenitic stainless steels and nickel-based alloys. Many of these alloys were extensively studied for use as fuel cladding materials in the 1960s, as part of programs to develop nuclear superheated steam reactors. After extensive out-of-pile testing and consideration of the existing data, five alloys (347 SS, 310 SS, Alloy 800H, Alloy 625, and Alloy 214) were selected for more detailed assessment using a combination of literature surveys and targeted testing to fill in major knowledge gaps. Wherever possible, performance criteria were developed for key materials properties. This paper summarizes the methodology used for the assessment and presents the key results, which show that 310 SS, Alloy 800H, and Alloy 625 would all be expected to give acceptable performance in the Canadian SCWR concept.
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e-mail: david.guzonas@cnl.ca
e-mail: matthew.edwards@cnl.ca
e-mail: Wenyue.Zheng@NRCan-RNCan.gc.ca
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January 2016
Research Papers
Assessment of Candidate Fuel Cladding Alloys for the Canadian Supercritical Water-Cooled Reactor Concept
D. Guzonas,
e-mail: david.guzonas@cnl.ca
D. Guzonas
Chalk River Laboratories, Canadian Nuclear Laboratories
, Chalk River, ON K0J 1J0
, Canada
e-mail: david.guzonas@cnl.ca
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M. Edwards,
e-mail: matthew.edwards@cnl.ca
M. Edwards
Chalk River Laboratories, Canadian Nuclear Laboratories
, Chalk River, ON K0J 1J0
, Canada
e-mail: matthew.edwards@cnl.ca
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W. Zheng
e-mail: Wenyue.Zheng@NRCan-RNCan.gc.ca
W. Zheng
CanmetMATERIALS, Natural Resources Canada
, 183 Longwood Road South, Hamilton, ON L8P 0A5
, Canada
e-mail: Wenyue.Zheng@NRCan-RNCan.gc.ca
Search for other works by this author on:
D. Guzonas
Chalk River Laboratories, Canadian Nuclear Laboratories
, Chalk River, ON K0J 1J0
, Canada
e-mail: david.guzonas@cnl.ca
M. Edwards
Chalk River Laboratories, Canadian Nuclear Laboratories
, Chalk River, ON K0J 1J0
, Canada
e-mail: matthew.edwards@cnl.ca
W. Zheng
CanmetMATERIALS, Natural Resources Canada
, 183 Longwood Road South, Hamilton, ON L8P 0A5
, Canada
e-mail: Wenyue.Zheng@NRCan-RNCan.gc.ca
Manuscript received May 27, 2015; final manuscript received August 14, 2015; published online December 9, 2015. Assoc. Editor: Thomas Schulenberg.
ASME J of Nuclear Rad Sci. Jan 2016, 2(1): 011016 (8 pages)
Published Online: December 9, 2015
Article history
Received:
May 27, 2015
Revision Received:
August 14, 2015
Accepted:
August 29, 2015
Citation
Guzonas, D., Edwards, M., and Zheng, W. (December 9, 2015). "Assessment of Candidate Fuel Cladding Alloys for the Canadian Supercritical Water-Cooled Reactor Concept." ASME. ASME J of Nuclear Rad Sci. January 2016; 2(1): 011016. https://doi.org/10.1115/1.4031502
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