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Grant: Collaborative Research and Development Grants

Queen's University

$55,500.00

Investigation of irradiated spacer materials (X750 and Zr-Nb-Cu)

EF 2021-22

Résumé
The purpose of this project is to develop an understanding of the embrittlement behaviour of one of the key mechanical components in a CANDU nuclear power reactor: the spacer, which is located between the calandria tube and the pressure tube. This project is aiming at evaluating radiation induced degradation of spacer material as well as developing a basic science understanding of irradiation damage in an industrially relevant Ni based alloy. The focus of this project will be to examine the effects of helium bubble induced cavitation of grain boundaries in irradiated materials, either using energetic ions or neutron irradiation. The short and long term results are directly applicable to understanding the effect of aging on the integrity of CANDU spacers. The techniques and analysis methods applied here to ion irradiated materials will help in the characterization and interpretation of measurements on neutron irradiated materials being studied at the Canadian Nuclear Laboratory (CNL) in parallel.The experimental results will also be used to support the image simulation models, to establish the intrinsic relationship between irradiation induced nano cavities and its induced mechanical degradation. In addition, thanks to this project, we will provide a high level of HQP training for the new generation of nuclear engineers.
Programme
Collaborative Research and Development Grants
Bénéficiaire
Emplacement
Ontario, Canada
Type de bénéficiaire
Academia
Type
Grant
Source
NSERC's Awards Data

Tel que publié

Application id
532182-2018
Name nom
Yao, Zhongwen
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
2021
Competition year année de concours
2018
Award amount
55500
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
2400
Research subject group en
Nuclear engineering
Research subject group fr
Génie nucléaire
Research subject en
Nuclear engineering
Research subject fr
Génie nucléaire
Installment
inst:4
Partie
1
Nb partie
4
Application title
Investigation of irradiated spacer materials (X750 and Zr-Nb-Cu)
Keyword
NSERC
Application summary
The purpose of this project is to develop an understanding of the embrittlement behaviour of one of the key mechanical components in a CANDU nuclear power reactor: the spacer, which is located between the calandria tube and the pressure tube. This project is aiming at evaluating radiation induced degradation of spacer material as well as developing a basic science understanding of irradiation damage in an industrially relevant Ni based alloy. The focus of this project will be to examine the effects of helium bubble induced cavitation of grain boundaries in irradiated materials, either using energetic ions or neutron irradiation. The short and long term results are directly applicable to understanding the effect of aging on the integrity of CANDU spacers. The techniques and analysis methods applied here to ion irradiated materials will help in the characterization and interpretation of measurements on neutron irradiated materials being studied at the Canadian Nuclear Laboratory (CNL) in parallel.The experimental results will also be used to support the image simulation models, to establish the intrinsic relationship between irradiation induced nano cavities and its induced mechanical degradation. In addition, thanks to this project, we will provide a high level of HQP training for the new generation of nuclear engineers.