Grant: NSERC/NRCan/AECL Generation IV Energy Technologies Program
Queen's University
$129,226.00
Creep and DHC of In-core Pressure Boundary materials for SCWR
FY 2010-11
Summary
In the insulated fuel channel design of a CANDU super critical water reactor (CANDU-SCWR) the pressure boundary operates at about ~100-150°C. There is very little information on the irradiation-induced deformation and mechanical properties of Zr-alloys or the effects of irradiation in this temperature range.
The reference material for the pressure boundary is the high strength, creep resistant Zr alloy Excel (Zr-3.5%Sn-0.8%Nb-0.8%Mo). The design of the pressure boundary for the CANDU-SWCR would be based on short term mechanical properties, but the life will be limited by irradiation induced deformation, susceptibility to delayed hydride cracking (DHC) and degradation of the properties by irradiation. The crystallographic texture and grain structure of Zr alloy tubes control their in-reactor deformation and also DHC characteristics. These microstructural features are primarily controlled by extrusion variables and subsequent heat treatment. The PI's will collaborate with Nu-Tech Precision Metals (manufacturer of the Zr-2.5Nb CANDU tubes for current generation CANDU reactors) to manufacture Excel alloy tubes with a range of microstructures and textures to assess the optimum metallurgical condition for use in the proposed SCWR design. This work is being carried out by Nu-Tech as ""work-in-kind"" as part of the NSERC/UNENE/Nu-Tech Industrial Research Chair program in Nuclear Materials at Queen's. Billet material has already been procured in collaboration with AECL from ATI Wah Chang, one of the probable suppliers of ingot material for SCWR materials. In collaboration with AECL, in-reactor testing of selected candidate materials will be carried out at a suitable temperature (~100°C) in the high flux SM reactor at RIAR in Dimitrovgrad Russia.
The current project addresses the long term future of both the domestic and export reactor market by providing Atomic Energy of Canada Ltd. with an important enabling technology for the CANDU SCWR, and developing expertise with Nu-Tech Precision Metals Inc. It also will provide several highly qualified personel to meet the growing needs of the Ontario Nuclear Industry.
Program
NSERC/NRCan/AECL Generation IV Energy Technologies Program
Recipient
Location
Ontario, Canada
Recipient Type
Academia
Type
Grant
Source
NSERC's Awards Data
As published
Application id
376332-2008
Name nom
Holt, Richard
Department département
Mechanical and Materials Engineering
Organization id
29
Institution établissement
Queen's University
Province en
Ontario
Province fr
Ontario
Country en
CANADA
Country fr
CANADA
Fiscal year exercice financier
2010
Competition year année de concours
2008
Award amount
129226
Program id
NNAPJ
Program name en
NSERC/NRCan/AECL Generation IV Energy Technologies Program
Program name fr
Programme des technologies énergétiques de quatrième génération CRSNG RNCan EACL
Group en
Research partnerships programs
Group fr
Programmes de partenariat
Committee code
96
Committee name en
RPP Internal Decision Cttee
Committee name fr
Cté de décision interne - PPR
Area of application code
302
Area of application group en
Energy resources
Area of application group fr
Ressources d'énergie
Area of application en
Nuclear energy
Area of application fr
Énergie nucléaire
Research subject code
2000
Research subject group en
Materials science and technology
Research subject group fr
Science et technologie des matériaux
Research subject en
Materials science and technology
Research subject fr
Science et technologie des matériaux
Partie
2 & 3
Nb partie
3
Application title
Creep and DHC of In-core Pressure Boundary materials for SCWR
Keyword
NSERC
Application summary
In the insulated fuel channel design of a CANDU super critical water reactor (CANDU-SCWR) the pressure boundary operates at about ~100-150°C. There is very little information on the irradiation-induced deformation and mechanical properties of Zr-alloys or the effects of irradiation in this temperature range.
The reference material for the pressure boundary is the high strength, creep resistant Zr alloy Excel (Zr-3.5%Sn-0.8%Nb-0.8%Mo). The design of the pressure boundary for the CANDU-SWCR would be based on short term mechanical properties, but the life will be limited by irradiation induced deformation, susceptibility to delayed hydride cracking (DHC) and degradation of the properties by irradiation. The crystallographic texture and grain structure of Zr alloy tubes control their in-reactor deformation and also DHC characteristics. These microstructural features are primarily controlled by extrusion variables and subsequent heat treatment. The PI's will collaborate with Nu-Tech Precision Metals (manufacturer of the Zr-2.5Nb CANDU tubes for current generation CANDU reactors) to manufacture Excel alloy tubes with a range of microstructures and textures to assess the optimum metallurgical condition for use in the proposed SCWR design. This work is being carried out by Nu-Tech as ""work-in-kind"" as part of the NSERC/UNENE/Nu-Tech Industrial Research Chair program in Nuclear Materials at Queen's. Billet material has already been procured in collaboration with AECL from ATI Wah Chang, one of the probable suppliers of ingot material for SCWR materials. In collaboration with AECL, in-reactor testing of selected candidate materials will be carried out at a suitable temperature (~100°C) in the high flux SM reactor at RIAR in Dimitrovgrad Russia.
The current project addresses the long term future of both the domestic and export reactor market by providing Atomic Energy of Canada Ltd. with an important enabling technology for the CANDU SCWR, and developing expertise with Nu-Tech Precision Metals Inc. It also will provide several highly qualified personel to meet the growing needs of the Ontario Nuclear Industry.
