Opencg: A Combinatorial Geometry Modeling Tool for Data Processing and Code Verification
Author(s)Boyd III, William Robert Dawson; Forget, Benoit Robert Yves; Smith, Kord S.
MetadataShow full item record
Combinatorial Geometry (CG) is one formulation for computational geometric models that is commonly used in many neutron transport simulation codes. The use of CG is advantageous since it permits an accurate yet concise representation of complex reactor models with a nominal memory footprint. OpenCG is a software package for combinatorial geometry models being developed at the Massachusetts Institute of Technology. The goal for OpenCG is to provide an easy-to-use, physics agnostic library to build geometry models of nuclear reactor cores. OpenCG is a free, open source library with an easy-to-use Python interface to provide nuclear engineers a single, powerful framework for modeling complex reactor geometries. Compatibility modules for commonly used nuclear reactor physics codes, such as OpenMC, OpenMOC, and Serpent, are being concurrently developed for rapid and easy exportation of an OpenCG model directly into the relevant input file format for each code of interest. The present work describes OpenCG and describes some of the novel and useful algorithms included with the software package.
DepartmentMassachusetts Institute of Technology. Department of Nuclear Science and Engineering
Proceedings of the ANS MC2015 - Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method
American Nuclear Society (ANS)
Boyd, William, Benoit Forget and Kord Smith. "Opencg: A Combinatorial Geometry Modeling Tool for Data Processing and Code Verification." ANS MC2015 - Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method, 19-23 April, 2015, Nashville, Tennessee, USA, American Nuclear Society, 2016.
Author's final manuscript