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Development of a New Monte Carlo Reactor Physics code: Dissertation
Jaakko Leppänen
Research output
:
Thesis
›
Dissertation
›
Monograph
1
Citation (Scopus)
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Dive into the research topics of 'Development of a New Monte Carlo Reactor Physics code: Dissertation'. Together they form a unique fingerprint.
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Keyphrases
Monte Carlo Method
100%
Transport Code
100%
Reactor Physics
100%
Monte Carlo
100%
Reactor Simulator
100%
Group Constants
66%
CASMO-5
66%
Neutron Transport Code
66%
Monte Carlo Calculation
66%
Nodal Diffusion
66%
Monte Carlo Neutron Transport
66%
Finland
33%
Monte Carlo Code
33%
Two Dimensional
33%
Reactor Systems
33%
Technical Research
33%
Group Constant Generation
33%
Calculation Method
33%
Continuous Energy
33%
Radiation Shielding
33%
Lattice Calculation
33%
Fuel Assembly
33%
Diffusion Calculation
33%
Reaction Cross Section
33%
Few-group Constants
33%
Code Development
33%
Reference Results
33%
Parallel Calculation
33%
Criticality Safety Analysis
33%
Deterministic Transport
33%
Complicated System
33%
Physics Applications
33%
Transport Theory
33%
Computer Capacity
33%
Special Techniques
33%
Nuclear Technology
33%
Capacity Calculation
33%
High Burnup Fuel
33%
Next Generation Reactors
33%
Detection Model
33%
Model Geometry
33%
Full-wave Analysis
33%
Neutron Diffusion Coefficients
33%
Model Interaction
33%
Keep up
33%
Assembly-level
33%
Main Application
33%
Shielding Problem
33%
Engineering
Simulators
100%
Neutron Transport
66%
Reactor System
33%
Technical Research Centre
33%
Burnup
33%
Input Parameter
33%
Radiation Shielding
33%
Two Dimensional
33%
Main Application
33%
Fuel Assembly
33%
Future Application
33%
Input Data
33%
Main Advantage
33%
Main Problem
33%
Advanced Fuel
33%
Tasks
33%
Energy Engineering
33%
Core Analysis
33%
Model Geometry
33%
Cross Section
33%
Diffusion Coefficient
33%
Safety Analysis
33%
INIS
monte carlo method
100%
reactor physics
100%
applications
50%
group constants
40%
transport
30%
reactor simulators
30%
comparative evaluations
20%
data
20%
modeling
20%
diffusion
20%
neutron transport
20%
solutions
10%
levels
10%
finland
10%
interactions
10%
geometry
10%
energy
10%
approximations
10%
calculation methods
10%
fuels
10%
physics
10%
reactors
10%
validation
10%
radiations
10%
capacity
10%
safety analysis
10%
cross sections
10%
burnup
10%
computers
10%
shielding
10%
criticality
10%
fuel assemblies
10%
transport theory
10%
neutron diffusion equation
10%
Chemical Engineering
Diffusion
100%