INIS
accidents
50%
anticipated transients without scram
25%
assessments
100%
boron
25%
computer codes
25%
cooling systems
25%
correlations
100%
critical heat flux
100%
data
50%
dilution
25%
dnb
25%
dryout
25%
dynamics
25%
finland
100%
friction
25%
fuel rods
25%
heat transfer
50%
information
25%
investigations
25%
kinetics
25%
losses
25%
modeling
25%
neutrons
25%
nuclear power plants
25%
one-dimensional calculations
25%
power plants
25%
prediction
25%
range
25%
reactivity-initiated accidents
25%
reactor cores
25%
reactor kinetics
100%
reactors
50%
rod bundles
50%
safety
25%
safety analysis
50%
simulation
50%
synthesis
25%
tables
25%
transients
75%
validation
100%
wwer type reactors
50%
Keyphrases
Anticipated Transient without Scram
25%
Boron Dilution
25%
Calculation System
50%
Chernobyl Accident
25%
Computer Code
25%
Cooling System
25%
Critical Heat Flux
100%
Dynamic Model
100%
Experimental Information
25%
Finland
100%
Flux Table
25%
Friction
25%
Fuel Rod
25%
Heat Transfer
25%
Kinetic Model
25%
Neutron Kinetics
25%
Nuclear Power Plant
25%
Observed Behavior
25%
Overall Behaviors
25%
Plant Database
25%
Post-dryout Heat Transfer
25%
Power Plant
25%
Pressure Loss
25%
Reactivity-initiated Accident
25%
Reactor Core
25%
Reactor Dynamics
100%
Reactor Transient
25%
Rod Bundle
50%
Safety Analysis
50%
Specific Tests
25%
Synthesis Model
25%
Technical Research
25%
Two-point
25%
Validation Case
25%
VVER-1000 Reactor
25%
VVER-440
25%
Engineering
Chernobyl Accident
25%
Cooling System
25%
Critical Heat Flux
100%
Dilution
25%
Dynamic Models
100%
Fuel Rod
25%
Generality
25%
Kinetic Model
25%
Nuclear Power Plant
25%
One Dimensional
25%
Plant Data
25%
Pressure Loss
25%
Reactor Core
25%
Reactor Dynamics
100%
Rod Bundle
50%
Safety Analysis
50%
Technical Research Centre
25%
Transients
100%