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INIS
fuels
100%
simulation
59%
performance
58%
failures
58%
fuel rods
55%
reactivity-initiated accidents
53%
rods
53%
accidents
50%
loca
48%
cladding
46%
modeling
42%
applications
36%
validation
30%
thermal hydraulics
28%
sensitivity analysis
26%
nuclear power plants
25%
bwr type reactors
22%
reactors
22%
evaluation
20%
large break loss-of-coolant accident
20%
loss of coolant
19%
finland
18%
data
14%
prediction
13%
power
13%
safety
13%
design
12%
chains
12%
boundary conditions
12%
reactor fuels
11%
design basis accidents
11%
oecd
11%
nea
11%
creep
11%
safety analysis
11%
pressurized water reactors
10%
boron dilution accident
10%
reviews
10%
low temperature
10%
Keyphrases
Fuel Rod
54%
Reactivity-initiated Accident
53%
Fuel Performance Code
50%
Sensitivity Analysis
31%
SBLOCA
31%
Fuel Failure
29%
FRAPTRAN
28%
Statistical Analysis
28%
Reactor
25%
Thermal-hydraulics
24%
Accident Condition
23%
Fuel Behavior
22%
Boiling Water Reactor
22%
Global Scenario
22%
Finland
22%
Loss of Coolant Accident
20%
LOCA Analysis
20%
Wilks' Formula
18%
Nuclear Power Plant
17%
Neural Network
17%
Fuel Performance
17%
Burst Criterion
16%
FINIX
14%
Reactor Conditions
14%
Cladding Failure
13%
Technical Research
13%
Fuel pin Failure
12%
Pressurized Water Reactor
12%
Design Basis Accident
11%
Master's Thesis
11%
Safety Regulation
11%
Accident Scenario
11%
Failure Analysis
11%
Safety Analysis
11%
Adaptation
11%
Analysis Procedure
11%
Rod Failure
10%
Boron Dilution
10%
Reactor Fuel
10%
Low Temperature
10%
Fresh Fuel
10%
Engineering
Loss of Coolant Accidents
80%
Rod
71%
Fuel Rod
67%
Code Performance
49%
Thermal Hydraulics
34%
Nuclear Power Plant
25%
Burnup
21%
Boiling Water Reactor
20%
Boundary Condition
19%
Creep
17%
Pressurized Water Reactor
13%
Design Basis Accident
13%
Technical Research Centre
13%
Dilution
11%
Safety Analysis
11%
Low-Temperature
10%
