Abstract
Constructive solid geometry (CSG) has traditionally been sufficient for Monte Carlo (MC) neutron transport simulations of standard light-water reactors (LWRs). Advanced reactor designs, as well as demand for multiphysics coupling and ex-core analysis, have created opportunities to use computer-aided design (CAD) to model a subset of reactor components. For scenarios where it is necessary to combine CAD and CSG models, a layered geometry method has been implemented in the Shift MC code. With this method, multiple CSG and/or CAD models can be arbitrarily clipped, translated, rotated, and placed in overlapping layers with assigned precedence to form transport-ready geometries. This is demonstrated with an MC k-eigenvalue calculation using a layered geometry model of the Transformational Challenge Reactor (TCR) consisting of complex CAD fuel elements placed in a CSG core model.
| Original language | English |
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| Title of host publication | Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022 |
| Publisher | American Nuclear Society |
| Pages | 3230-3239 |
| Number of pages | 10 |
| ISBN (Electronic) | 9780894487873 |
| DOIs | |
| State | Published - 2022 |
| Event | 2022 International Conference on Physics of Reactors, PHYSOR 2022 - Pittsburgh, United States Duration: May 15 2022 → May 20 2022 |
Publication series
| Name | Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022 |
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Conference
| Conference | 2022 International Conference on Physics of Reactors, PHYSOR 2022 |
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| Country/Territory | United States |
| City | Pittsburgh |
| Period | 05/15/22 → 05/20/22 |
Funding
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.
Keywords
- CAD geometry
- Monte Carlo radiation transport
- advanced reactors