Engineering
Cross Section
100%
Eigenvalue
68%
Sensitivity Coefficient
64%
Radiation Shielding
54%
Oak Ridge
53%
Safety Analysis
53%
Nuclear Safety Analysis
50%
Reactor Safety
48%
Graphical User Interface
41%
Similarities
38%
Desired Result
32%
Enriched Uranium
28%
Multiplication Factor
22%
Nuclear Criticality Safety
22%
Analysis Code
19%
Burnup
16%
Monte Carlo Sampling Technique
16%
Nuclear Energy
16%
Spent Fuels
16%
Least Square
14%
Limitations
14%
Sodium-Cooled Fast Reactor
14%
Parallel Computer
12%
Fuel Rod
12%
Hard Disk
12%
Relative Performance
12%
Nuclear Fuel
12%
Metrics
12%
State-of-the-Art Method
12%
Alarm System
12%
Progression
12%
Neutron Transport
11%
Project Evaluation
11%
Department of Energy
10%
Fuel Assembly
10%
Adjoint Response λ
10%
Fission Product
9%
Neutron Flux
9%
Experimental Uncertainty
9%
Material Composition
9%
Text Editor
9%
Illustrates
9%
Software Systems
9%
Project Team
9%
Power Engineering
8%
Data File
7%
Complete Set
7%
Neutronics
7%
Design Concept
6%
Product Yield
6%
Computer Science
Criticality
77%
Modeling and Simulation
22%
Graphical User Interface
19%
Monte Carlo Code
14%
Underlying Architecture
12%
Hard Disk
12%
Functional Module
12%
Reusable Component
12%
Software Infrastructure
12%
Fortran
12%
Programming Language
12%
Computer Analysis
12%
Quality Management
11%
Desired Solution
9%
Parallel Computer
9%
Academic Institution
6%
Underlying Assumption
6%
Variance Reduction
6%
Code Analysis
6%
Location Information
6%
Computational Method
6%
Input Validation
6%
Correlated Data
6%
Data Adjustment
6%
Software Frameworks
6%
Interactive Visualization
6%
User Interface
6%
Scattering Cross
6%
Modern Software
6%
Research Organization
6%
