The Application of MCNP6.2 Unstructured Mesh Geometry Capabilities to the Study of Heavy Ion Single Event Effect on Microelectronic Devices and the Reactor Physics Analysis - 25691

Unstructured meshes allow irregular or complex geometries to be modeled precisely in Monte Carlo radiation transport codes. Through this capability, it is possible to share an unstructured mesh model between multiple codes that use unstructured mesh geometry and thus improving coupled multi-physics...

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Bibliographic Details
Main Authors Kowal, Peter J., McPherson, Joseph A., Ji, Wei
Format Conference Proceeding
LanguageEnglish
Published United States American Nuclear Society - ANS; La Grange Park, IL (United States) 15.08.2018
Subjects
ENERGY ABSORPTION
ENERGY LOSSES
GEOMETRY
HEAVY IONS
INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
MAPPING
MATHEMATICAL METHODS AND COMPUTING
MICROELECTRONICS
MONTE CARLO METHOD
NEUTRON FLUX
RADIATION PROTECTION AND DOSIMETRY
RADIATION TRANSPORT
REACTOR PHYSICS
REACTORS
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Summary:Unstructured meshes allow irregular or complex geometries to be modeled precisely in Monte Carlo radiation transport codes. Through this capability, it is possible to share an unstructured mesh model between multiple codes that use unstructured mesh geometry and thus improving coupled multi-physics simulations. In this work, unstructured meshes are used to model energy deposition from heavy ion strikes for single event effects on microelectronic devices as well as neutron flux mapping of nuclear reactor configurations. In each case, MCNP6.2's unstructured mesh functionality and applicability to the problem is demonstrated and analyzed. (authors)