Keyphrases
Accident Prevention
27%
ATHLET
55%
Commercial Utilisation
27%
Containment
41%
Decomposition Method
27%
Design Approach
27%
Design Quality
27%
Discrete Ordinates
37%
Fast Transient
41%
Federal Republic of Germany
34%
Finite Difference Method
27%
Fort
27%
FRM II
37%
Fuel Temperature
37%
Fully Implicit Time Integration
50%
Germany
83%
Human Factors
27%
Increased Safety
27%
International Cooperation
27%
Long-term Simulation
27%
Matrix Decomposition
27%
Neutron Transport Code
55%
New Reactors
27%
Nuclear Energy
27%
Nuclear Facilities
27%
Nuclear Power Plant
100%
Nuclear Safety
41%
Nuclear Technology
27%
Operating Experience
62%
Physical Principles
27%
Power Reactor
27%
Probabilistic Risk Assessment
27%
Radiation Exposure
27%
Reactor Concept
41%
Reactor Safety
55%
Research Reactor
50%
Risk Analysis
27%
Risk Study
55%
Safety Characteristics
27%
Safety Concept
47%
Safety Research
55%
Severe Core Damage
27%
Slow Transient
41%
Sodium-cooled Reactor
27%
Space-time Effect
27%
Space-time Kinetics
27%
Thermal-hydraulic Code
55%
Three-dimensional Calculations
27%
Time-dependent Neutron Transport
55%
Two Dimensional
27%
Engineering
Absorption Cross
27%
Accident Prevention
13%
Arbitrary Number
18%
Chernobyl Accident
6%
Control Rod
16%
Convergence Criterion
18%
Core Damage
27%
Cross Section
53%
Design Basis Accident
16%
Design Quality
27%
Design Stage
13%
Discretization
18%
Fast Transient
9%
Fission Product
13%
Germany
97%
Hydraulic Parameter
6%
Hydraulic System
25%
Illustrates
13%
Implicit Time
43%
Industrial Applications
13%
Light Water Reactors
13%
Limitations
27%
Main Result
13%
Neutron Flux
27%
Neutron Transport
83%
Neutronics
25%
Nuclear Engineering
27%
Nuclear Facility
27%
Nuclear Power Plant
93%
Nuclear Reactor
74%
Nuclear Safety
41%
Outages
13%
Physical Principle
27%
Power Density
9%
Power Reactor
27%
Reactor Pressure Vessel
13%
Reactor Safety
13%
Research Reactors
6%
Rod
27%
Safety Engineering
41%
Safety Objective
13%
Seismic Design
27%
Sodium-Cooled Fast Reactor
27%
Strong Emphasis
13%
System Parameter
9%
Temperature Distribution
27%
Thermal Hydraulics
64%
Transient Analysis
9%
Transients
50%
Water Cooled Reactor
13%