The Mechanical Response of Advanced Claddings during Proposed Reactivity Initiated Accident Conditions

Conference · Sun Jan 01 04:00:00 EST 2017

OSTI ID:1346655

Cinbiz, Mahmut N ^[1]; Brown, Nicholas R ^[1]; Terrani, Kurt A ^[1]; Lowden, Rick R ^[1]; ERDMAN, III, DONALD L ^[1]

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1. ORNL

This study investigates the failure mechanisms of advanced nuclear fuel cladding of FeCrAl at high-strain rates, similar to design basis reactivity initiated accidents (RIA). During RIA, the nuclear fuel cladding was subjected to the plane-strain to equibiaxial tension strain states. To achieve those accident conditions, the samples were deformed by the expansion of high strength Inconel alloy tube under pre-specified pressure pulses as occurring RIA. The mechanical response of the advanced claddings was compared to that of hydrided zirconium-based nuclear fuel cladding alloy. The hoop strain evolution during pressure pulses were collected in situ; the permanent diametral strains of both accident tolerant fuel (ATF) claddings and the current nuclear fuel alloys were determined after rupture.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: NE USDOE - Office of Nuclear Energy
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1346655
• Country of Publication: United States
• Language: English

Related Subjects

Accident tolerant fuel
FeCrAl alloys
Reactivity initiated accident
high strain rate
modified burst test