Issue |
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
|
|
---|---|---|
Article Number | 04012 | |
Number of page(s) | 8 | |
Section | Monte Carlo Transport | |
DOI | https://doi.org/10.1051/epjconf/202124704012 | |
Published online | 22 February 2021 |
https://doi.org/10.1051/epjconf/202124704012
csg2csg: A TOOL TO ASSIST VALIDATION & VERIFICATION
1 United Kingdom Atomic Energy Authority Culham Abingdon Oxfordshire OX14 3DB
2 ISIS Neutron and Muon Source, Science and Technology Facilities Council, Rutherford Appleton Laboratory Didcot OX11 0QX
andrew.davis@ukaea.uk
steven.lilley@stfc.ac.uk
jonathan.shimwell@ukaea.uk
Published online: 22 February 2021
The csg2csg tool is a minimal dependency Python3 based program to facilitate the comparison of radiation transport Monte Carlo codes. The csg2csg can currently parse MCNP and OpenMC geometry descriptions, and it can subsequently export MCNP, FLUKA, PHITS, OpenMC and Serpent geometry files. This translation is achieved by reading the input geometry into a class based system of objects corresponding to surfaces, cells, materials and so on. The objects are then translated into a ‘generic’ form. This form once generalised can be converted to any of the supported code formats and then radiation transport calculations can be performed. The code has been tested on several geometries; most notably a complex JET model and a 70k cell ITER C-Model geometry.
Key words: CSG / convert / neutronics
© The Authors, published by EDP Sciences, 2021
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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