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VEERA facility for studies of nuclear safety in VVER type reactors
Markku Puustinen, Jari Tuunanen, Pekka Raussi
VTT Technical Research Centre of Finland
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INIS
data
100%
pressurized water reactors
100%
reactors
100%
boundary conditions
100%
boric acid
100%
nuclear safety
100%
accidents
50%
geometry
50%
concentration
50%
computer codes
50%
accuracy
50%
thermal hydraulics
50%
testing
50%
dimensions
50%
cooling
50%
mixing
50%
neutrons
50%
crystallization
50%
data acquisition systems
50%
loss of coolant
50%
Keyphrases
Pressurized Water Reactor
100%
Boric Acid
100%
Nuclear Safety
100%
Reflood
100%
VVER-1000 Reactor
100%
Cooling Period
50%
Crystallization
50%
Computer Code
50%
Data Acquisition System
50%
Loss of Coolant Accident
50%
Modified Forms
50%
Original Form
50%
Long-term Cooling
50%
Thermal-hydraulic Analysis
50%
Neutron Poison
50%
Reflood Model
50%
Engineering
Pressurized Water Reactor
100%
Nuclear Safety
100%
Applicability
50%
Thermal Hydraulics
50%
Test Procedure
50%
Core Region
50%
Loss of Coolant Accidents
50%
Cooling Period
50%
Initial and Boundary Condition
50%
Data Acquisition System
50%
Boundary Condition
50%
Computer Programs
50%
Earth and Planetary Sciences
Nuclear Safety
100%
Boundary Condition
100%
Pressurized Water Reactor
100%
Data Acquisition
50%
Computer Programs
50%
Loss of Coolant
50%