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Discrete modeling of early-life thermal fracture in ceramic nuclear fuel
Benjamin W Spencer
, Hai Huang
, John E Dolbow
,
Jason D Hales
Nuclear Fuels & Materials
Scientific Computing & AI
Research output
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Dive into the research topics of 'Discrete modeling of early-life thermal fracture in ceramic nuclear fuel'. Together they form a unique fingerprint.
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Keyphrases
Discrete Element Method
100%
Ceramic Fuel
100%
Thermal Fracture
100%
Discrete Modeling
100%
Light Water Reactor Fuel
75%
Finite Element Method
50%
Thermal Gradient
50%
Fuel Behavior
50%
Fuel Pellets
50%
Circumferential Crack
50%
Radial Crack
50%
Nuclear Fuel
25%
Extended Finite Element Method
25%
Microcracks
25%
Fuel Performance
25%
Modeling Capability
25%
Crack Pattern
25%
Crack Location
25%
Idaho National Laboratory
25%
Burnup
25%
Temperature Field
25%
Modeling Techniques
25%
Thermal Conductance
25%
Bulk Thermal Conductivity
25%
X-FEM
25%
Physically-based
25%
Power Ramp
25%
Coupled Thermo-mechanical
25%
Heat Conduction
25%
Hoop Stress
25%
Axial Stress
25%
Power Cycle
25%
Pellet-cladding Gap
25%
Solid Mechanics
25%
Thermal Crack
25%
Random Initiation
25%
Coupled Heat
25%
Abnormal Conditions
25%
Fracture Modeling
25%
Outer Region
25%
Displacement Field
25%
Crack Form
25%
Life Behavior
25%
Effective Conductivity
25%
Axial Crack
25%
Thermally Driven
25%
Displacement Discontinuity
25%
Fracture Criterion
25%
Discontinuous Behaviour
25%
Continuous Interpolation
25%
Random Propagation
25%
Discrete Displacement
25%
Scale Formation
25%
Crack Causes
25%
Discontinuous Phenomena
25%
Engineering
Discrete Element
100%
Element Method
100%
Nuclear Fuel
100%
Early Life
100%
Finite Element Analysis
75%
Light Water Reactors
75%
Thermal Gradient
50%
Fuel Pellet
50%
Circumferential Crack
50%
Initial Power
50%
Burnup
25%
Length Scale
25%
Tensiles
25%
Temperature Distribution
25%
Thermal Conductivity
25%
Hoop Stress
25%
Power Cycle
25%
Solid Mechanics
25%
Outer Region
25%
Displacement Field
25%
Fuel Model
25%
Axial Stress
25%
Fracture Criterion
25%