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monte carlo method
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reactors
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burnup
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applications
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simulation
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fuels
27%
performance
27%
reactor physics
22%
geometry
22%
comparative evaluations
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pwr type reactors
18%
physics
18%
neutron transport
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energy
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16%
coupling
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15%
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implementation
14%
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14%
benchmarks
13%
group constants
13%
validation
12%
thermal hydraulics
11%
finland
11%
tools
10%
distribution
10%
power
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10%
Keyphrases
Serpent
64%
Serpent 2
64%
Monte Carlo Code
52%
Reactor Physics
25%
Monte Carlo
24%
Burnup Calculation
20%
Neutronics
15%
SUBCHANFLOW
14%
Finland
14%
Reactor
14%
Monte Carlo Neutron Transport
13%
Full Core
13%
Multiphysics
12%
Pin-by-pin
12%
Burnup
12%
Fuel Behavior
11%
Continuous Energy
10%
Engineering
Neutronics
38%
Burnup
34%
Cross Section
19%
Neutron Transport
19%
Thermal Hydraulics
17%
Fuel Assembly
13%
Technical Research Centre
12%
District Heating
11%
Subchannel
10%
Good Agreement
10%