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A transient heat conduction model for reactor fuel elements
E. E. Lewis
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Corresponding author for this work
Mechanical Engineering
Research output
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Article
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peer-review
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Engineering
Models
100%
Transients
66%
Fundamental Mode
66%
Fuel
50%
Reactor
33%
Fuel Element
33%
Lumped Parameter
33%
Parameter Model
33%
Thermal Resistance
33%
Analytical Result
16%
Greens Function
16%
Heat Capacity
16%
Codes
16%
Losses
16%
Accidents
16%
Physics
Model
100%
Cladding
66%
Transients
66%
Region
50%
Fuel
50%
Thermal Resistance
33%
Specific Heat
16%
Green's Functions
16%
Operators (Mathematics)
16%
Gaps
16%
Approximation
16%
Heat
16%
Conductive Heat Transfer
16%
INIS
cladding
66%
fuels
50%
transients
50%
reactor fuel elements
33%
interfaces
16%
comparative evaluations
16%
time dependence
16%
approximations
16%
heat
16%
accidents
16%
differential equations
16%
loss of coolant
16%
thermal conduction
16%
heat capacity
16%
coolants
16%
green function
16%
Chemistry
Cladding
66%
Fuel
50%
Coolant
33%
Thermal Resistance
33%
Reactor
33%
Debye Temperature
16%
Tight Binding Model
16%
Thermal Conductivity
16%
Accident
16%
Number
16%
Time
16%
Heat
16%