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Integrated KENO Monte Carlo transport for 3-D depletion with scale
Stephen M. Bowman
, Mark D. Dehart
, Lester M. Petrie
Research output
:
Contribution to conference
›
Paper
›
peer-review
5
Scopus citations
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Keyphrases
Transport Method
100%
Monte Carlo Transport
100%
Coding Sequence
100%
Oak Ridge National Laboratory
50%
Modeling Capability
50%
Nuclear Materials
50%
Evolutionary Concepts
50%
Monte Carlo
50%
Nonproliferation
50%
KENO-VI
50%
Neutron Transport
50%
Reactor Design
50%
Neutron Flux Distribution
50%
Increasing Complexity
50%
Computer Analysis
50%
Deterministic Transport
50%
Accurate Calculation
50%
Software System
50%
Geometrical Model
50%
Monte Carlo Transport Code
50%
Complex Configuration
50%
Computer Software
50%
Neutron Flux Density
50%
Flexibility Characteristics
50%
Engineering
Oak Ridge
100%
Data Show
100%
Nuclear Material
100%
Measured Data
100%
Nonproliferation
100%
Neutron Transport
100%
Reactor Design
100%
Neutron Flux
100%
Flux Density
100%
Accurate Calculation
100%
Software System
100%
Computer Science
Code Sequence
100%
Software System
50%
Security Safeguard
50%
Computer Analysis
50%
Material Science
Density
100%