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Grant: Collaborative Research and Development Grants

Royal Military College of Canada

$19,070.00

Use of neutron-absorbers to improve CANDU reactor operating margins

FY 2012-13

Summary
The proposed application of burnable poisons to existing CANDU Natural Uranium (NU) fuel design is a novel approach and is currentlyfunded under the CANDU Owners Group (COG). Because of low excess reactivityfor NU fuel, the amount of neutron-absorber is expected to be restricted to small quantities. This implies the impact on neutron economywould be relativelyminimal, but the fuel performance would be significantlyimproved. Small amounts and appropriate mixtures of neutron absorbers were selected (approximately500 mg of absorbers in a CANDU fuel bundle having a nominal weight of 24 kg). Preliminary results indicate that the fuelling transient for the initial reactivitypeak can be lowered long enough to improve the reactor's operating margins. This result was presented at the CNS Conference in Saskatoon in June 2012. A redesign of the CANDU NU fuel bundle with an appropriate combination of elements, with some including neutron-absorbers, could well address the issue of the xenon-free effects while lowering the plutonium-peak that occurs shortlythereafter. The proposed NSERC project is to further exploit the use of this conceptual design. The use of fuel bundles containing neutron absorbers offers an opportunityto redistribute approximately1 to 2 % power to lower powered channels i.e. power redistribution across the core. One of the recommended fuel designs is to locate neutron-absorbers at bundle ends, as end pellets or end discs. Hence thesecond part of this proposal is use the proposed design to mitigate end-flux peaking during refueling and to qualify(if any) its incremental benefit to safetymargins. Fuel safety and performance are always important topics to a nuclear utility. If this project is successful, benefits of improving fuel utilization (byfurther optimizing the fuelling strategy) and safetymargins (by lowering the maximum channel and bundle powers) could be realized for a reasonable simple change.
Program
Collaborative Research and Development Grants
Location
Ontario, Canada
Recipient Type
Academia
Type
Grant
Source
NSERC's Awards Data

As published

Application id
436050-2012
Name nom
Chan, Paul
Department département
Chemistry and Chemical Engineering
Organization id
30
Institution établissement
Royal Military College of Canada
Province en
Ontario
Province fr
Ontario
Country en
CANADA
Country fr
CANADA
Fiscal year exercice financier
2012
Competition year année de concours
2012
Award amount
19070
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
Use of neutron-absorbers to improve CANDU reactor operating margins
Keyword
NSERC
Application summary
The proposed application of burnable poisons to existing CANDU Natural Uranium (NU) fuel design is a novel approach and is currentlyfunded under the CANDU Owners Group (COG). Because of low excess reactivityfor NU fuel, the amount of neutron-absorber is expected to be restricted to small quantities. This implies the impact on neutron economywould be relativelyminimal, but the fuel performance would be significantlyimproved. Small amounts and appropriate mixtures of neutron absorbers were selected (approximately500 mg of absorbers in a CANDU fuel bundle having a nominal weight of 24 kg). Preliminary results indicate that the fuelling transient for the initial reactivitypeak can be lowered long enough to improve the reactor's operating margins. This result was presented at the CNS Conference in Saskatoon in June 2012. A redesign of the CANDU NU fuel bundle with an appropriate combination of elements, with some including neutron-absorbers, could well address the issue of the xenon-free effects while lowering the plutonium-peak that occurs shortlythereafter. The proposed NSERC project is to further exploit the use of this conceptual design. The use of fuel bundles containing neutron absorbers offers an opportunityto redistribute approximately1 to 2 % power to lower powered channels i.e. power redistribution across the core. One of the recommended fuel designs is to locate neutron-absorbers at bundle ends, as end pellets or end discs. Hence thesecond part of this proposal is use the proposed design to mitigate end-flux peaking during refueling and to qualify(if any) its incremental benefit to safetymargins. Fuel safety and performance are always important topics to a nuclear utility. If this project is successful, benefits of improving fuel utilization (byfurther optimizing the fuelling strategy) and safetymargins (by lowering the maximum channel and bundle powers) could be realized for a reasonable simple change.
Royal Military College of Canada - $19,070 Grant (201… | Canada Spends