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PROGRESS IN MULTIDIMENSIONAL NEUTRON TRANSPORT COMPUTATION.
E. E. Lewis
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Corresponding author for this work
Mechanical Engineering
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Article
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peer-review
7
Scopus citations
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Keyphrases
Computational Methods
100%
Monte Carlo Method
100%
Computational Cost
100%
First-order
100%
Transport Equation
100%
Nuclear System
100%
Memory Requirements
100%
Neutron Transport Problems
100%
Even Parity
100%
Neutron Transport
100%
Integral Transport
100%
Computer Memory
100%
Order Form
100%
Mathematics
Computational Cost
100%
Transport Equation
100%
Monte Carlo
100%
Biochemistry, Genetics and Molecular Biology
Neutron Radiation
100%
Solution and Solubility
50%
Neuroscience
Monte Carlo Method
100%