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Engineering
Neutronics
100%
Nuclear Power Plant
87%
Reactor Core
85%
Nuclear Reactor
82%
Accident Prevention
72%
Cladding System
71%
Neutronic Analysis
70%
Cladding Material
68%
Advanced-High Temperature Reactor
56%
Fuel Assembly
48%
Pressurized Water Reactor
45%
Fuel Rod
43%
Nuclear Energy
43%
Alloy
40%
Thermal Hydraulics
39%
Cycle Length
37%
Fuel System
36%
Performance Analysis
35%
Nuclear Fuel
35%
Heat Storage
32%
Loss of Coolant Accidents
31%
Optical Spectrum
30%
Fuel Cycle
29%
Burnup
27%
Reactor Design
26%
Severe Accident
25%
Outer Surface
25%
Fits and Tolerances
25%
Layer Coating
22%
Multiplication Factor
22%
Energy Storage
21%
Computational Fluid Dynamics
20%
Uranium Dioxide
20%
Comprehensive Review
18%
Control Rod
18%
Adhesive Layer
18%
Cross Section
18%
Two Dimensional
17%
Metrics
16%
Thermooxidation
16%
Phase Change Material
15%
Power Distribution
15%
Coupled System
15%
Reactor Safety
15%
Molten Salt
14%
Operational Condition
14%
Thermal Conductivity
14%
Small Modular Reactor
13%
Core Analysis
13%
Mixed Convection
13%
Material Science
Zircaloy
51%
Chromium
34%
Carbon Nanofiber
32%
Hydraulics
27%
Density
25%
Silicon Carbide
24%
Nuclear Fuel
21%
Zirconium Alloy
21%
Uranium Dioxide
21%
Alloy
21%
Actinide
20%
Coolant
20%
Porous Carbon
18%
Capacitance
17%
Zirconium
17%
Niobium
16%
Molybdenum
16%
Supercapacitors
16%
Oxide Compound
14%
Plutonium
12%
Electrochemical Reaction
10%
Symmetric Supercapacitor
10%
Conceptual Design
10%
Microsphere
10%
Boron
10%
Nitric Oxide
10%
Alkaline Electrolyte
10%
Conducting Polymer
10%
Oxide Surface
10%
Graphene
10%
Corrosion Resistance
10%
Nuclear Fuel System
10%
Activated Carbon
10%
Activated Charcoal
10%
Anisotropy
10%
Homogenization
10%
Thermal Conductivity
9%
Tantalum
8%
Thermomechanical Property
8%
Nanostructure
7%
Supercapacitors Performance
5%
Turbulent Flow
5%
Thermal Analysis
5%
Design Principle
5%
Damage Evolution
5%
Nuclear Fuel Element
5%
Hydrogen
5%
Stainless Steel
5%
Embrittlement
5%
Strength of Materials
5%
Physics
Nuclear Reactor
54%
Neutronics
54%
Monte Carlo
43%
Neutron Radiation
41%
Nuclear Power Plant
36%
Cladding
36%
Reactor Physics
27%
Hydraulics
21%
Coolant
18%
Nuclear Fuel
17%
Fuel System
17%
Transportation
16%
Neutron Cross Section
13%
Neutron Physics
13%
Absorption Cross Sections
12%
Charge Flow Device
10%
Nuclear Engineering
10%
Homogenizing
10%
Reynolds Number
10%
Safety Analysis
10%
Strouhal Number
10%
Molten Salt
10%
Monte Carlo Method
10%
Fast Reactor
10%
Computational Fluid Dynamics
10%
Neutron Transport
10%
Probability Theory
10%
Uranium Dioxide
7%
Random Forest
7%
Xgboost
7%
Reynolds' Number
7%
Actinide
5%
Active Galactic Nuclei
5%
Angular Distribution
5%
Angular Velocity
5%
Iodine
5%
Tincture of Iodine
5%
Measurement Method
5%
Nuclear Security
5%
Anisotropy
5%
Health Physics
5%
Transport Theory
5%
Graphical User Interface
5%
Nuclear Reactor Physics
5%
Alloy
5%
