Detecting Cladding Leaks in Irradiated Fuel Elements by Neutron Radiography

AM Ross

doi:10.1520/STP33923S

SYMPOSIA PAPER Published: 01 January 1976

STP33923S

Detecting Cladding Leaks in Irradiated Fuel Elements by Neutron Radiography

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At Chalk River, performance limits for advanced fuels are established by irradiating multi-element assemblies until one or more elements develop a cladding leak. Post-irradiation identification of leaky elements is assisted by thermal neutron radiography, because marked changes in radiographic appearance occur due to the effects of light water coolant entering during operation. Radiographs illustrating these changes are given for zirconium alloy-clad UO₂ and uranium alloy fuel elements that had been irradiated in pressurized water to burnups up to 144 MWh/kg uranium.

Author Information

Ross, AM

Atomic Energy of Canada Ltd., Chalk River Nuclear Labs., Chalk River, Ontario, Canada

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Details

Developed by Committee: E07

Pages: 195–209

DOI: 10.1520/STP33923S

ISBN-EB: 978-0-8031-4668-6

ISBN-13: 978-0-8031-0535-5

Detecting Cladding Leaks in Irradiated Fuel Elements by Neutron Radiography

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