Grant: NSERC/NRCan/AECL Generation IV Energy Technologies Program
University of Alberta
$100,000.00
Identification of Suitable Materials and Appropriate Chemistry for SCC Resistant Pressure Tube SCWR Design
EF 2008-09
Résumé
The proposed project is directed to providing data on suitable materials and chemistry with immediate applicability in design of SCW. It will generate new knowledge, provide insights on nuclear materials and chemistry, and develop skills of HQP essential to Canada's nuclear industrial capability.
The Generation (GEN) IV supercritical water reactor (SCWR) is an advanced concept offering advantages compared to light water reactors. However, no current alloy is identified that meets SCWR operational requirements and avoids high temperature corrosion and stress corrosion cracking (SCC). Material performance will need to be demonstrated in the key areas of corrosion and SCC, including identification of appropriate water chemistry that will minimize corrosion rates and SCC.
The proposed research, in active collaboration with AECL and NRCan, addresses these priorities with the following objectives: (a) identify and improve SCC materials' resistance to corrosion/SCC through surface modification, and (b) quantify effects of oxygen, hydrogen peroxide, and hydrogen on SCC to define water chemistries and generate new knowledge/technology to strengthen Canada's nuclear industry, and help fulfill Canada's obligations under the GEN IV International Forum (GIF) agreement.
Susceptibility of candidate materials will be determined under SCW conditions. We will correlate metallurgical factors (compositions and microstructure of the selected alloys) with composition and structure of the corrosion film, and their effect on SCC in SCWRs and mechanisms. The application of surface modification will be explored with the aim of developing a cost-effective technique for Gen IV candidate materials to increase the inherent resistance of the alloys to SCC. SCC susceptibility of the candidate materials will be investigated under a wide range of oxygen and hydrogen concentrations. SCC tests will also be conducted in SCW with different concentrations of H2O2 to mimic the changes in water chemistry that occur due to radiolysis and elucidate mechanism(s). SCC susceptibility of alloys will be studied as a function of the density of SCW.
Programme
NSERC/NRCan/AECL Generation IV Energy Technologies Program
Bénéficiaire
Emplacement
Alberta, Canada
Type de bénéficiaire
Academia
Type
Grant
Source
NSERC's Awards Data
Tel que publié
Application id
376364-2008
Name nom
Luo, Jingli
Department département
Chemical and Materials Engineering
Organization id
9
Institution établissement
University of Alberta
Province en
Alberta
Province fr
Alberta
Country en
CANADA
Country fr
CANADA
Fiscal year exercice financier
2008
Competition year année de concours
2008
Award amount
1e+05
Program id
NNAPJ
Program nane 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
602
Area of application group en
Construction, urban and rural planning
Area of application group fr
Construction, urbanisme et aménagement rural
Area of application en
Materials performance
Area of application fr
Performance des matériaux
Research subject code
2001
Research subject group en
Materials science and technology
Research subject group fr
Science et technologie des matériaux
Research subject en
Materials structure, properties and testing
Research subject fr
Structure, propriétés et essais des matériaux
Partie
1
Nb partie
3
Application title
Identification of Suitable Materials and Appropriate Chemistry for SCC Resistant Pressure Tube SCWR Design
Keyword
NA
Application summary
The proposed project is directed to providing data on suitable materials and chemistry with immediate applicability in design of SCW. It will generate new knowledge, provide insights on nuclear materials and chemistry, and develop skills of HQP essential to Canada's nuclear industrial capability.
The Generation (GEN) IV supercritical water reactor (SCWR) is an advanced concept offering advantages compared to light water reactors. However, no current alloy is identified that meets SCWR operational requirements and avoids high temperature corrosion and stress corrosion cracking (SCC). Material performance will need to be demonstrated in the key areas of corrosion and SCC, including identification of appropriate water chemistry that will minimize corrosion rates and SCC.
The proposed research, in active collaboration with AECL and NRCan, addresses these priorities with the following objectives: (a) identify and improve SCC materials' resistance to corrosion/SCC through surface modification, and (b) quantify effects of oxygen, hydrogen peroxide, and hydrogen on SCC to define water chemistries and generate new knowledge/technology to strengthen Canada's nuclear industry, and help fulfill Canada's obligations under the GEN IV International Forum (GIF) agreement.
Susceptibility of candidate materials will be determined under SCW conditions. We will correlate metallurgical factors (compositions and microstructure of the selected alloys) with composition and structure of the corrosion film, and their effect on SCC in SCWRs and mechanisms. The application of surface modification will be explored with the aim of developing a cost-effective technique for Gen IV candidate materials to increase the inherent resistance of the alloys to SCC. SCC susceptibility of the candidate materials will be investigated under a wide range of oxygen and hydrogen concentrations. SCC tests will also be conducted in SCW with different concentrations of H2O2 to mimic the changes in water chemistry that occur due to radiolysis and elucidate mechanism(s). SCC susceptibility of alloys will be studied as a function of the density of SCW.
