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Numerical methods for nuclear fuel burnup calculations: Dissertation
Maria Pusa
VTT Technical Research Centre of Finland
VTT (former employee or external)
Aalto University
Research output
:
Thesis
›
Dissertation
›
Collection of Articles
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Dive into the research topics of 'Numerical methods for nuclear fuel burnup calculations: Dissertation'. Together they form a unique fingerprint.
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Keyphrases
Burnup Calculation
100%
Numerical Methods
100%
Burnup Equations
100%
Nuclear Fuel Burnup
100%
Burnup
75%
Perturbation Theory
50%
Equation-based
50%
Matrix Exponential
50%
Real Axis
50%
Criticality Equation
50%
Uncertainty Analysis
25%
Mathematical Model
25%
Uncertain Data
25%
Interaction Data
25%
Numerical Solution
25%
Neutron
25%
Neutron Transport
25%
Computation Time
25%
Neutron Interactions
25%
Fuel Assembly
25%
Nuclear Fuel
25%
Chebyshev Rational Approximation Method
25%
Material Composition
25%
Radioactive Decay
25%
Eigenvalues
25%
Adjoint System
25%
Sensitivity Profile
25%
Rational Approximation
25%
Number of Parameters
25%
Robust Solution
25%
Accurate Solution
25%
Forward Problem
25%
Mathematical Properties
25%
Transmutation Reactions
25%
Assembly-level
25%
Nuclide Concentration
25%
First Order Differential System
25%
Mathematics
Nuclides
100%
Mathematical Method
100%
Matrix
50%
Negative Real Axis
50%
Perturbation Theory
50%
Exponential Matrix
50%
Rational Approximation
25%
Chebyshev
25%
Time Step
25%
Adjoint System
25%
Mathematical Modeling
25%
Approximation Method
25%
Eigenvalue
25%
Numerical Solution
25%
INIS
burnup
100%
nuclear fuels
100%
equations
54%
matrices
36%
nuclides
36%
approximations
18%
variations
18%
perturbation theory
18%
neutrons
18%
criticality
18%
solutions
9%
levels
9%
data
9%
interactions
9%
concentration
9%
calculation methods
9%
sensitivity
9%
mathematical models
9%
half-life
9%
numerical solution
9%
neutron transport
9%
differential equations
9%
fuel assemblies
9%
eigenvalues
9%
nuclear decay
9%
transmutation
9%
Physics
Nuclear Fuel
100%
Mathematical Method
100%
Nuclides
100%
Perturbation Theory
50%
Half-Life
25%
Neutron Transport
25%
Operators (Mathematics)
25%
Numerical Solution
25%
Mathematical Model
25%
Radioactive Decay
25%
Engineering
Burnup
100%
Numerical Methods
100%
Nuclear Fuel
100%
Matrix Exponential
18%
Real Axis
18%
Eigenvalue
9%
Fuel Assembly
9%
Material Composition
9%
Computation Time
9%
Accurate Solution
9%
Robust Solution
9%
Mathematical Property
9%
Order Differential Equation
9%
Neutron Transport
9%
Numerical Solution
9%
Mathematical Model
9%