Layered CAD/CSG geometry for spatially complex radiation transport scenarios

Elliott Biondo; Gregory Davidson; Brian Ade

doi:10.1016/j.anucene.2022.109569

Layered CAD/CSG geometry for spatially complex radiation transport scenarios

Elliott Biondo, Gregory Davidson, Brian Ade

Research output: Contribution to journal › Article › peer-review

1 Scopus citations

Abstract

Many spatially complex fission, fusion, and national security Monte Carlo (MC) radiation transport scenarios involve combining computer-aided design (CAD) models with constructive solid geometry (CSG) models. A layered geometry method has been implemented in the Shift MC code to address this need. With layered geometry, multiple CAD and/or CSG models can be clipped, translated, rotated, and placed in overlapping layers to form transport-ready geometries. The utility of this method is demonstrated with two problems: (1) a fixed-source simulation with a layered geometry consisting of a LiDAR-generated CAD model of the Combined Arms Collective Training Facility urban environment overlaid with CSG models of a mock hotel and a detector apparatus, and (2) a k-eigenvalue calculation using a layered geometry model of the Transformational Challenge Reactor consisting of CAD fuel elements placed in a CSG core. Tallied particle flux distributions match expectations, but tracking robustness must be improved prior to general-purpose use.

Original language	English
Article number	109569
Journal	Annals of Nuclear Energy
Volume	181
DOIs	https://doi.org/10.1016/j.anucene.2022.109569
State	Published - Feb 2023

Funding

The authors would like to thank Douglas Peplow for his help with the models used in the CACTF problem in Section 4 . This work was supported by the Laboratory Directed Research and Development (LDRD) program of Oak Ridge National Laboratory , which is managed and operated by UT-Battelle LLC for the US Department of Energy (DOE) under contract no. DEAC05-00OR22725 .

Funders	Funder number
U.S. Department of Energy	DEAC05-00OR22725
Oak Ridge National Laboratory
UT-Battelle

Keywords

CAD geometry
LiDAR
Monte Carlo radiation transport

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10.1016/j.anucene.2022.109569

Cite this

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abstract = "Many spatially complex fission, fusion, and national security Monte Carlo (MC) radiation transport scenarios involve combining computer-aided design (CAD) models with constructive solid geometry (CSG) models. A layered geometry method has been implemented in the Shift MC code to address this need. With layered geometry, multiple CAD and/or CSG models can be clipped, translated, rotated, and placed in overlapping layers to form transport-ready geometries. The utility of this method is demonstrated with two problems: (1) a fixed-source simulation with a layered geometry consisting of a LiDAR-generated CAD model of the Combined Arms Collective Training Facility urban environment overlaid with CSG models of a mock hotel and a detector apparatus, and (2) a k-eigenvalue calculation using a layered geometry model of the Transformational Challenge Reactor consisting of CAD fuel elements placed in a CSG core. Tallied particle flux distributions match expectations, but tracking robustness must be improved prior to general-purpose use.",

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AB - Many spatially complex fission, fusion, and national security Monte Carlo (MC) radiation transport scenarios involve combining computer-aided design (CAD) models with constructive solid geometry (CSG) models. A layered geometry method has been implemented in the Shift MC code to address this need. With layered geometry, multiple CAD and/or CSG models can be clipped, translated, rotated, and placed in overlapping layers to form transport-ready geometries. The utility of this method is demonstrated with two problems: (1) a fixed-source simulation with a layered geometry consisting of a LiDAR-generated CAD model of the Combined Arms Collective Training Facility urban environment overlaid with CSG models of a mock hotel and a detector apparatus, and (2) a k-eigenvalue calculation using a layered geometry model of the Transformational Challenge Reactor consisting of CAD fuel elements placed in a CSG core. Tallied particle flux distributions match expectations, but tracking robustness must be improved prior to general-purpose use.

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Layered CAD/CSG geometry for spatially complex radiation transport scenarios

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Keywords

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