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Grant: Collaborative Research and Development Grants

University of Western Ontario

$116,000.00

Radiolytic corrosion of copper

FY 2016-17

Summary
The present management scenario for the permanent disposal of high level nuclear waste is to bury it in sealed metallic containers buried in a deep stable geologic repository. The primary function of the waste container is to isolate the radioactive waste form from groundwater until radioactivity levels have decayed to innocuous levels. For the present thick-walled container design gamma radiation fields on the outside of the container would have a negligible influence on container corrosion. However, to overcome a number of fabrication and welding issues, thinner walled containers are being contemplated making a reassessment of the influence of gamma radiation on container corrosion a potential licensing requirement. This project addresses this issue by proposing a study of radiation effects on corrosion under simulated repository conditions, which will evolve from initially hot and dry to warm, aerated, and humid and eventually cool, aqueous and anoxic. A program of electrochemical, analytical and corrosion experiments will be employed to determine the mechanistic features of the corrosion process and to determine the evolution of corrosion damage as waste repository conditions evolve and radiation fields decay. A model will be developed to assess the extent to which the container wall can be thinned without compromising container corrosion performance.
Program
Collaborative Research and Development Grants
Location
Ontario, Canada
Recipient Type
Academia
Type
Grant
Source
NSERC's Awards Data

As published

Application id
469090-2014
Name nom
Shoesmith, David
Department département
Chemistry
Organization id
36
Institution établissement
University of Western Ontario
Province en
Ontario
Province fr
Ontario
Country en
CANADA
Country fr
CANADA
Fiscal year exercice financier
2016
Competition year année de concours
2014
Award amount
116000
Program id
CRDPJ
Program name en
Collaborative Research and Development Grants
Program name fr
Subventions de recherche et développement coopérative
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
2402
Research subject group en
Nuclear engineering
Research subject group fr
Génie nucléaire
Research subject en
Radioactive materials
Research subject fr
Matériaux radioactifs
Partie
3
Nb partie
3
Application title
Radiolytic corrosion of copper
Keyword
NSERC
Application summary
The present management scenario for the permanent disposal of high level nuclear waste is to bury it in sealed metallic containers buried in a deep stable geologic repository. The primary function of the waste container is to isolate the radioactive waste form from groundwater until radioactivity levels have decayed to innocuous levels. For the present thick-walled container design gamma radiation fields on the outside of the container would have a negligible influence on container corrosion. However, to overcome a number of fabrication and welding issues, thinner walled containers are being contemplated making a reassessment of the influence of gamma radiation on container corrosion a potential licensing requirement. This project addresses this issue by proposing a study of radiation effects on corrosion under simulated repository conditions, which will evolve from initially hot and dry to warm, aerated, and humid and eventually cool, aqueous and anoxic. A program of electrochemical, analytical and corrosion experiments will be employed to determine the mechanistic features of the corrosion process and to determine the evolution of corrosion damage as waste repository conditions evolve and radiation fields decay. A model will be developed to assess the extent to which the container wall can be thinned without compromising container corrosion performance.