Grant: Collaborative Research and Development Grants
Ryerson University
$46,600.00
Development of a computer model for predicting CANDU fuel string vibration induced by turbulent coolant flow
EF 2010-11
Résumé
Fuel endplate failures and severe pressure tube wear were discovered in some CANDU reactors only a few years after their commercial operations. Investigations revealed that (i) the fuel endplate failure was caused by the acoustics originated at the primary heat transport pump and (ii) the presence of moderate to severe fretting marks on the inside surfaces of the pressure tubes was caused by the excessive movement (vibration) of the bearing pads. Further investigations showed that fretting of varying degrees was present in all fuel channels. Fuel string fretting thus becomes an integrity concern for the CANDU reactors.
The objectives of the proposed research project are to (i) develop efficient, accurate and reliable algorithms for predicting vibration of a CANDU fuel string under reactor conditions, (ii) implement the algorithm into a computer code for assessment of fretting and wear for existing and new CANDU fuels, (iii) test the code against experimental data documented in the Canadian nuclear industry. This is enormously challenging research area where a large number of bodies, large scale dynamic contact and solid-fluid interaction must be dealt with accurately.
Completion of the proposed research program will allow the Canadian nuclear industry to advance their understanding of flow-induced vibrations and dynamic contact in a fuel string under operating conditions. The modeling work and the computer program will directly help the Canadian nuclear industry to conduct assessments of fuel bundle fretting and pressure tube wear in fuel design and qualifications. The methodology and algorithms developed in dealing with the vibrations of multibody systems involving contact and interaction with fluid may be used by researchers and engineers in other industries such as power and process industries. In addition, the proposed work is significant in designing future CANDU reactor fuel to meet the wear specifications that are compatible with the overall reactor life and maintenance schedules.
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
396148-2009
Name nom
Yu, Shudong
Department département
Mechanical and Industrial Engineering
Organization id
43
Institution établissement
Ryerson University
Province en
Ontario
Province fr
Ontario
Country en
CANADA
Country fr
CANADA
Fiscal year exercice financier
2010
Competition year année de concours
2009
Award amount
46600
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
Partie
1
Nb partie
3
Application title
Development of a computer model for predicting CANDU fuel string vibration induced by turbulent coolant flow
Keyword
NSERC
Application summary
Fuel endplate failures and severe pressure tube wear were discovered in some CANDU reactors only a few years after their commercial operations. Investigations revealed that (i) the fuel endplate failure was caused by the acoustics originated at the primary heat transport pump and (ii) the presence of moderate to severe fretting marks on the inside surfaces of the pressure tubes was caused by the excessive movement (vibration) of the bearing pads. Further investigations showed that fretting of varying degrees was present in all fuel channels. Fuel string fretting thus becomes an integrity concern for the CANDU reactors.
The objectives of the proposed research project are to (i) develop efficient, accurate and reliable algorithms for predicting vibration of a CANDU fuel string under reactor conditions, (ii) implement the algorithm into a computer code for assessment of fretting and wear for existing and new CANDU fuels, (iii) test the code against experimental data documented in the Canadian nuclear industry. This is enormously challenging research area where a large number of bodies, large scale dynamic contact and solid-fluid interaction must be dealt with accurately.
Completion of the proposed research program will allow the Canadian nuclear industry to advance their understanding of flow-induced vibrations and dynamic contact in a fuel string under operating conditions. The modeling work and the computer program will directly help the Canadian nuclear industry to conduct assessments of fuel bundle fretting and pressure tube wear in fuel design and qualifications. The methodology and algorithms developed in dealing with the vibrations of multibody systems involving contact and interaction with fluid may be used by researchers and engineers in other industries such as power and process industries. In addition, the proposed work is significant in designing future CANDU reactor fuel to meet the wear specifications that are compatible with the overall reactor life and maintenance schedules.