Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
The flexible cross-section generation tool is Python-based software that runs the open-source Monte Carlo code OpenMC (https://docs.openmc.org/en/stable/ ) to generate and optimize crosssections for any reactor geometry. Please follow directions on the OpenMC documentation page for installation instructions. In addition, please set the environment variable “OPENMC_MG_CROSS_SECTIONS” equal to mgxs.h5. The optimization aims to choose energy group structures as well as scattering representation that maximize accuracy with respect to continuous-energy results while avoiding significant computational expense. It then outputs these cross-sections in an ISOXML format readable by the Idaho National Lab code suite MOOSE (Olin William Calvin, Mark D DeHart, “Architecture for the Performance of Nuclear Fuel Depletion Calculations”, Idaho National Laboratory report, November 2019).
The user should create geometry files and modify the main file to specify user preferences. To run code, simply run main.py in the same folder as the geometry file(s) and the rest of the source code.
© 2021. Triad National Security, LLC. All rights reserved. This program was produced under U.S. Government contract 89233218CNA000001 for Los Alamos National Laboratory (LANL), which is operated by Triad National Security, LLC for the U.S. Department of Energy/National Nuclear Security Administration. All rights in the program are reserved by Triad National Security, LLC, and the U.S. Department of Energy/National Nuclear Security Administration. The Government is granted for itself and others acting on its behalf a nonexclusive, paid-up, irrevocable worldwide license in this material to reproduce, prepare derivative works, distribute copies to the public, perform publicly and display publicly, and to permit others to do so.
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