Improved solid decomposition algorithms for the CAD-to-MC conversion tool McCad

Lu, Lei; Qiu, Yuefeng; Fischer, U.

doi:10.1016/j.fusengdes.2017.02.040

Cited by 31 publications

(22 citation statements)

References 2 publications

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“…In principle, this is the favorable solution, as it is simple yet elegant and might offer the best performance during simulation. If the CSG configuration is not known, it is sometimes possible to recreate it with CSG decomposition [29]. Complex volumes can also be converted to a tessellated shape, where the surface is represented by a triangle mesh, called G4TessellatedSolid in Geant4 [30].…”

Section: Target Chambers and Cad-based Geometrymentioning

confidence: 99%

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Efficient determination of HPGe γ-ray efficiencies at high energies with ready-to-use simulation software

Mayer

Hoemann

Müllenmeister

et al. 2020

Nuclear Instruments and Methods in Physics Research Section A:

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The full-energy-peak efficiency of HPGe detectors at γ-ray energies around 10 MeV is not easily accessible with experimental methods. Monte-Carlo simulations with Geant4 can provide these efficiencies. G4Horus is a ready-to-use Geant4 application for the HORUS HPGe-detector array. Users can configure the modular parts to match their experiment with minimal knowledge of the simulation software and limited time commitment. In our case, knowing and implementing the geometry with high precision is the biggest challenge. To implement the different target chambers, we transform the existing CAD models to Geant4 geometry with CADMesh. We also found a large discrepancy between experimental and simulated efficiency for some older HPGe detectors, which could be remedied by introducing a large dead region around the inner core. This project is open source and available from https://github.com/janmayer/G4Horus [1]. We invite everyone to adapt the project or adopt parts of the code for other projects.

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Section: Target Chambers and Cad-based Geometrymentioning

confidence: 99%

“…For example, plugins have once been developed for FreeCAD [32,33] and CATIA [34]. Notable standalone projects are cad-to-geant4-converter [35], STEP-to-ROOT [36], SW2GDMLconverter [37], and McCad-Salome [29]. Some projects seem to be abandoned, having received their last update several years ago.…”

Section: Target Chambers and Cad-based Geometrymentioning

confidence: 99%

Efficient determination of HPGe γ-ray efficiencies at high energies with ready-to-use simulation software

Mayer

Hoemann

Müllenmeister

et al. 2020

Nuclear Instruments and Methods in Physics Research Section A:

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“…The conversion which would most dramatically enhance the creation of RTMC geometry is CAD to Geant4 or FLUKA without use use of a triangular or tetrahedral mesh. There are existing approaches to decompose BREP solids to Geant4 and FLUKA-like CSG geometry [18,31]. The FreeCAD/Open-CASCADE interface combined with the Geant4 and FLUKA Python API in Pyg4ometry will allow for the creation of CAD BREP decomposition algorithms.…”

Section: Conclusion and Discussionmentioning

confidence: 99%

PYG4OMETRY: a Python library for the creation of Monte Carlo radiation transport physical geometries

Boogert,

Abramov,

Nevay

et al. 2020

Preprint

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Creating and maintaining computer readable geometries for use in Monte Carlo Radiation Transport (MCRT) simulations is an error-prone and timeconsuming task. Simulating a system often requires geometry from different sources and modelling environments, including a range of MCRT codes and computer-aided design (CAD) tools. Pyg4ometry is a Python library that enables users to rapidly create, manipulate, display, read and write Geometry Description Markup Language (GDML)-based geometry used in simulations. Pyg4ometry provides importation of CAD files to GDML tessellated solids, conversion of GDML geometry to FLUKA and conversely from FLUKA to GDML. The implementation of Pyg4ometry is explained in detail along with small examples. The paper concludes with a complete example using most of the Pyg4ometry features and a discussion of extensions and future work.

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“…The second principle is to use surface-based volumes only (no TRIPOLI-4 combinatory volume nor ROOT-based volume [7], as a reminder "volume" in TRIPOLI-4 is the exact equivalent of a MCNP "cell"). Not only do these surface-based volumes speed-up computation, but in addition they can eventually supply CAD / MCNP / TRIPOLI-4 automatic converters or viewers, such as McCAD [8] or MCAM [9].…”

Section: Introductionmentioning

confidence: 99%

“…For example, the fuel in standard fuel elements and fuel-follower control rods are modeled fresh, FCs are not physically depicted into their guide tubes (the fission rates being collected into a 4 mm long water cylinder instead), etc.The second principle is to use surface-based volumes only (no TRIPOLI-4 combinatory volume nor ROOT-based volume[7], as a reminder "volume" in TRIPOLI-4 is the exact equivalent of a MCNP "cell"). Not only do these surface-based volumes speed-up computation, but in addition they can eventually supply CAD / MCNP / TRIPOLI-4 automatic converters or viewers, such as McCAD[8] or MCAM[9].The third principle is to use the point-wise nuclear cross section library supplied by default with TRIPOLI-4.11.0, CEAv5.1.2. CEAv5.1.2 is mainly based on JEFF-3.1.1[10] for transport cross-sections and contains point-wise IRDF-2002 cross-sections[11], which are used to calculate 235 U and 238 U fission rates in FCs.The fourth principle is to use the same control rods positions as the two MCNP models used to provide the MCNP results in the NEA report.The main difference between the TRIPOLI-4 and MCNP models lies in the absence of transformation matrixes in TRIPOLI-4.11.0.…”

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confidence: 99%

CEA-JSI Experimental Benchmark for validation of the modeling of neutron and gamma-ray detection instrumentation used in the JSI TRIGA reactor

et al. 2021

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Constant improvements of the computational power and methods as well as demands of accurate and reliable measurements for reactor operation and safety require a continuous upgrade of the instrumentation. In particular, nuclear sensors used in nuclear fission reactors (research or power reactors) or in nuclear fusion facilities are operated under intense mixed neutron and gamma-ray fields, and need to be calibrated and modeled to provide selective and accurate neutron and gamma-ray measurements. The French Atomic Energy and Alternative Energies Commission (CEA) and the Jožef Stefan Institute (JSI) have started an experimental program dedicated to a detailed experimental benchmark with analysis using Monte Carlo particle transport calculations and a series of neutron and gamma-ray sensor types used in the JSI TRIGA Mark II reactor. CEA has setup a simplified TRIPOLI-4® modeling scheme of the JSI TRIGA reactor based on the information available in the IRPhEP benchmark in order to facilitate analysis of future neutron and gamma-ray measurements. These allow the CEA to perform a TRIPOLI-4 instrumentation calculation scheme benchmarked with the JSI MCNP model. This paper presents the main results of this CEA calculation scheme application and the analysis of their comparison to the JSI results obtained in 2012 with the MCNP5 & ENDF/B-VII.0 calculation scheme. This paper will conclude with some information about the new experimental program to be carried out in 2022 in the TRIGA reactor core.

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Improved solid decomposition algorithms for the CAD-to-MC conversion tool McCad

Cited by 31 publications

References 2 publications

Efficient determination of HPGe γ-ray efficiencies at high energies with ready-to-use simulation software

Efficient determination of HPGe γ-ray efficiencies at high energies with ready-to-use simulation software

PYG4OMETRY: a Python library for the creation of Monte Carlo radiation transport physical geometries

CEA-JSI Experimental Benchmark for validation of the modeling of neutron and gamma-ray detection instrumentation used in the JSI TRIGA reactor

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