1 Bethel Valley Road, P.O. Box 2008, Mail Stop 608
Room B-106, Building 5700
Oak Ridge, TN 37831
United States
Government of the United States of America - Oak Ridge National Laboratory
Accident Tolerant FuelLoss of Coolant AccidentSever Accident Test Station
UN, MiniFuel, Accelerated Burnup, Accelerated Fuel Qualification
High BurnupLoss of coolant accidentFuel Fragmentation relocation and dispersalStudsvik cladding integrity projectLight water reactors
Zirconium fuel cladding, creep, isotropy, accident
accident transient behavior, Microstructural evolution, burst testing, nuclear fuel cladding, Accident Tolerant Fuel Claddings, light water reactor
FFRD, high burnup, nuclear fuel, steady state, VERA, BISON
Tension test, Plastic deformation, Metal and Alloys, 2D Quantitative Analysis
cladding rupturerupture opening modelFFRDLOCA
reactor safety analysis, loss-of-coolant accident, nuclear systems code, computational thermal hydraulics, high-burnup fuel
FFRD, high burnup, nuclear fuels, code coupling, VERA, TRACE, BISON
Boiling Water ReactorLoss of Coolant AccidentHigh Burnup
multiphysics, decay heat, loss of coolant accident
FFRDValidationcladding strainballoon
FFRD, LOCA, High-burnup, Fission Gas, Burst Release
FFRD, LOCA, high-burnup, thermal hydraulics, reactor safety
transient Fission Gas Release, LOCA, FFRD, High Burnup, microstructure
High BurnupLOCAFFRDComparisonORNLStudsvik
time at temperature, power updates, light water reactor, cladding performance, critical heat flux, dryout, departure from nuclear boiling
Fuel fragmentation relocation and dispersalgrid spacerstransient fission gas releasecladding ballooning
HT9, accident transient, austenitization, ferritic martensitic, high temperature mechanical properties
LOCA, ATF, digital image correlation, hot cell DIC, in-situ ballooning