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Showing 1 to 18 of 18 for “"Openmc"”.
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Implementation and validation of OpenMC depletion capabilities in SaltProc
Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2024-03-01 without embargo terms
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Memory efficient indexing algorithm for physical properties in OpenMC
OpenMC is an open source Monte Carlo code designed at MIT with a focus on parallel scalability for large nuclear reactor simulations. The target problem for OpenMC is a full core high-fidelity multi-physics coupled simulation. This encompasses not only nuclear physics, but also material science and …
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CAD-Based Geometry Representations for Monte Carlo Fusion Neutronics Methods and CSG vs. DAGMC Performance Tradeoffs in OpenMC
… comparison between CSG and DAGMC geometries in OpenMC is analyzed by evaluating particle simulation rates and memory usage across four progressively complex fusion-like models. Performance results reflect positively on DAGMC transport, but areas of future work are identified for more …
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Parallel algorithms for Monte Carlo particle transport simulation on exascale computing architectures
… was proposed and subsequently implemented in the OpenMC Monte Carlo code. A theoretical analysis of the communication pattern shows that the expected cost is O([square root]N) whereas traditional fission bank algorithms are O(N) at best. The algorithm was tested on two supercomputers, the Intrepid …
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Computational treatments for neutron resonance elastic scattering in Monte Carlo nuclear simulations
… correction (DBRC) treatment in the open-source OpenMC Monte Carlo neutron transport code being developed at the Massachusetts Institute of Technology. In an effort to improve computational efficiency, the optimal energy limits where this phenomenon should be treated are determined and compared …
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On-node performance optimization of a Monte-Carlo transport code for leadership architectures
… of a Monte Carlo neutron transport code (i.e., OpenMC) and implemented several optimizations to address the major bottlenecks. First, a comprehensive profiling analysis was carried out on modern Intel micro-architectures (i.e., Intel Xeon Phi and Intel Xeon Platinum 8180) to understand what …
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Evaluating the use of surface source banking to accelerate Monte Carlo transport simulations of far-field particle fluxes
… materials. The completion of a test case with an OpenMC model of an MK2 TRIGA facility indicated agreement between the two criteria. Effects of oversampling a surface source that met the stationarity criteria, as well as potential limitations of the surface source banking method itself were also …
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Computational methods for efficient nuclear data management in Monte Carlo neutron transport simulations
… neutron transport code simulations. Using the OpenMC code, profiling studies are conducted in order to determine the types of nuclear data that are used in realistic reactor physics simulations, as well as the frequencies with which those data are accessed. The results of the profiling studies …
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Neutronic Analysis of Horizontal-Compact High Temperature Gas-cooled Reactor
… with power >100MWt. Parametric studies using OpenMC were carried out to ensure its feasibility. With a uniform enriched core, 12 rotating control drums with an outer radius of 23.4407cm, 0.5cm thickness of 90% enriched B₄C, and 0.3cm incoloy cross supports, achieved the highest shutdown margin …
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A Monte Carlo framework for nuclear data uncertainty propagation via the windowed multipole formalism
… on the CLUTCH-FM methodology was implemented in OpenMC. Several methods for obtaining the windowed multipole covariance matrix from the resonance parameter covariance matrix were explored, and ultimately an approach based on random-sampling was selected. Along the way, an analytical benchmark was …
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Full core 3D neutron transport simulation using the method of characteristics with linear sources
… studies and comparisons with reference OpenMC Monte Carlo solutions show that converged full core 3D MOC simulations are feasible on modern supercomputers for the first time.
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Monte Carlo and thermal hydraulic coupling using low-order nonlinear diffusion acceleration
… was implemented in the continuous-energy MC code OpenMC. When employing this technique, the number of inactive generations was reduced by a factor of 10. Realistic reactor calculations also require thermal hydraulic (TH) feedback which was integrated into the source convergence process. The use of …
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Flux-Independent Uncertainty Propagation of Nuclear Cross Section Data Using the Windowed Multipole Formalism
… sensitivities produced by the CLUTCH method in OpenMC to calculate resulting eigenvalue uncertainties in a partial BWR assembly as well as a plutonium nitrate solution criticality benchmark. This new method of producing WMP uncertainties enables the creation of a WMP parameter covariance library …
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Acceleration methods for Monte Carlo particle transport simulations
… in the continuous energy Monte Carlo code, OpenMC, and tested in 2D PWR benchmarks. The Low Order Operator (LOO) acceleration method is a deterministic transport method based on the Method of Characteristics. Similar to Coarse Mesh Finite Difference (CMFD), the other acceleration method …
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Improvements and applications of the Uniform Fission Site method in Monte Carlo
… Both techniques have been implemented into OpenMC, a continuous energy Monte Carlo code. The UFS method uses weights to alter the number of neutrons born at a fission site. It operates on a superimposed mesh, in which each mesh cell contains a different weight. These weights use an estimate …
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Domain decomposition for Monte Carlo particle transport simulations of nuclear reactors
… implemented in the full-physics Monte Carlo code OpenMC, and tested for a highly-detailed PWR benchmark: BEAVRS. The proposed domain decomposition implementation incorporates efficient algorithms for scalable inter-domain particle communication in a manner that is reproducible with any …
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GPU-Oriented Algorithms for Continuous Energy Monte Carlo Neutron Transport
… development of a CUDA-based version of OpenMC, an open-source continuous energy MC neutron and photon transport code. Fortunately, the historical event-based MC simulation modality developed extensively through the 1980s for vector computers provides an excellent basis for GPU computing. …
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Fluoride-salt-cooled high-temperature reactor generative design optimization with evolutionary algorithms
Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2023-04-12 without embargo terms