Skip to main navigation
Skip to search
Skip to main content
Northwestern Scholars Home
Help & FAQ
Home
Experts
Organizations
Research Output
Grants
Core Facilities
Research Data
Search by expertise, name or affiliation
A transient heat conduction model for reactor fuel elements
E. E. Lewis
*
*
Corresponding author for this work
Mechanical Engineering
Research output
:
Contribution to journal
›
Article
›
peer-review
5
Scopus citations
Overview
Fingerprint
Fingerprint
Dive into the research topics of 'A transient heat conduction model for reactor fuel elements'. Together they form a unique fingerprint.
Sort by
Weight
Alphabetically
Keyphrases
Fuel Element
100%
Fundamental Mode
100%
Heat Conduction Model
100%
Reactor Fuel
100%
Transient Heat Conduction
100%
Mode Model
75%
Thermal Resistance
50%
Lumped Parameter Model
50%
Analytical Results
25%
Fuel Cladding
25%
Two-region
25%
Differential Equations
25%
Heat Capacity
25%
Coolant
25%
Thermal Transient
25%
Exact Analytical Expressions
25%
Accident Transient
25%
Loss of Coolant
25%
Time-dependent Green's Function
25%
Engineering
Fuel Element
100%
Transients
100%
Fundamental Mode
100%
Lumped Parameter
50%
Parameter Model
50%
Heat Resistance
50%
Analytical Result
25%
Heat Capacity
25%
Green's Functions
25%