Engineering
Cross Section
75%
Thermal Neutron
66%
Oak Ridge
41%
Polytechnic
25%
Measured Data
25%
Plexiglass
16%
Reactor Design
16%
Model Parameter
16%
Joints (Structural Components)
16%
Status Report
16%
Fitting Procedure
12%
Positive Temperature Coefficient
11%
Temperature Coefficient
11%
Design Iteration
11%
Low-Temperature
8%
Good Agreement
8%
Dynamic Models
8%
Covariance Matrix
8%
Gaussians
8%
Light Water
8%
Neutron Source
8%
Statistical Property
8%
High Resolution
8%
Matrix Analysis
8%
Safety Program
8%
Matrix Theory
8%
Nuclear Criticality Safety
8%
Performed Measurement
8%
Application Programming Interface
8%
Broadening
8%
Data File
8%
Global Parameter
8%
File Format
8%
Small Reactor
5%
Elevated Temperature
5%
Physics
Thermal Neutron
100%
Neutron Scattering
62%
Covariance
38%
Neutron Cross Section
33%
Polystyrene
33%
Phonon Density of State
22%
Scattering Cross Section
19%
Small-Angle Neutron Scattering
16%
Porosity
16%
Cerium Isotope
16%
Linear Accelerator
16%
Cold Neutron
16%
Spallation
12%
Density of States
11%
Light Water
11%
Inelastic Scattering
8%
Molecular Dynamics
8%
Neutron Source
8%
Monte Carlo Method
8%
Phonon
8%
Inelastic Neutron Scattering
5%
Gaussian Distribution
5%
Material Science
Hydride
66%
Yttrium
66%
Polystyrene
33%
Polyethylene
29%
Density
29%
Thermoluminescence
16%
Analytical Method
16%
Metal Hydride
8%
Uranium Dioxide
8%
Silicon Carbide
8%
