INIS
monte carlo method
100%
reactors
40%
burnup
34%
simulation
32%
applications
30%
performance
29%
fuels
28%
reactor physics
23%
geometry
22%
comparative evaluations
21%
pwr type reactors
19%
energy
18%
modeling
18%
coupling
18%
neutron transport
17%
physics
17%
transport
17%
neutrons
17%
cross sections
16%
levels
15%
implementation
15%
solutions
15%
benchmarks
14%
group constants
14%
validation
13%
finland
12%
power
11%
thermal hydraulics
11%
distribution
11%
district heating
10%
tools
10%
design
10%
fuel assemblies
10%
Keyphrases
Serpent
68%
Serpent 2
63%
Monte Carlo Code
51%
Reactor Physics
27%
Monte Carlo
24%
Burnup Calculation
22%
Finland
15%
Neutronics
15%
SUBCHANFLOW
15%
Monte Carlo Neutron Transport
14%
Reactor
14%
Full Core
14%
Burnup
13%
Pin-by-pin
13%
Multiphysics
12%
Fuel Behavior
11%
Continuous Energy
11%
Technical Research
10%
District Heating Reactor
10%
Engineering
Burnup
35%
Neutronics
33%
Energy Engineering
26%
Cross Section
20%
Transients
19%
Neutron Transport
19%
Thermal Hydraulics
15%
Technical Research Centre
13%
Fuel Assembly
12%
District Heating
12%