MOCUM: A two-dimensional method of characteristics code based on constructive solid geometry and unstructured meshing for general geometries

Yang, Xueming; Satvat, Nader

doi:10.1016/j.anucene.2012.03.009

Cited by 28 publications

(5 citation statements)

References 10 publications

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“…As this benchmark is intended to serve as a reference to developers of methods which model block-level heterogeneity, the aim has been to create an accessible benchmark with enough detail to present a challenging test to a new method, but simplified enough so as to be useful; for instance, very few methods, at present, resolve pin-level heterogeneity in their full-core calculations, and a problem which maintains such minute detail is unlikely to serve much immediate purpose to the community. A similar approach was taken with a benchmark in the style of Japan's high temperature test reactor (Zhang et al, 2011), which has been a valuable model for methods testing (Yang and Satvat, 2012).…”

Section: Stylized Core Model Developmentmentioning

confidence: 99%

Prismatic VHTR neutronic benchmark problems

Connolly

Rahnema

Tsvetkov

2015

Nuclear Engineering and Design

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h i g h l i g h t s• High temperature gas-cooled reactor neutronics benchmark problems.• Description of a whole prismatic VHTR core in its full heterogeneity.• Modeled using continuous energy nuclear data at a representative hot operating temperature.• Benchmark results for core eigenvalue, block-averaged power, and some selected pin fission density results. a b s t r a c tThis paper aims to fill an apparent scarcity of benchmarks based on high temperature gas-cooled reactors. Within is a description of a whole prismatic VHTR core in its full heterogeneity and modeling using continuous energy nuclear data at a representative hot operating temperature. Also included is a core which has been simplified for ease in modeling while attempting to preserve as faithfully as possible the neutron physics of the core. Fuel and absorber pins have been homogenized from the particle level, however, the blocks which construct the core remain strongly heterogeneous. A six group multigroup (discrete energy) cross section set has been developed via Monte Carlo using the original heterogeneous core as a basis.Several configurations of the core have been solved using these two cross section sets; eigenvalue results, block-averaged power results, and some selected pin fission density results are presented in this paper, along with the six-group cross section data, so that method developers may use these problems as a standard reference point.

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Section: Stylized Core Model Developmentmentioning

confidence: 99%

Prismatic VHTR neutronic benchmark problems

Connolly

Rahnema

Tsvetkov

2015

Nuclear Engineering and Design

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“…36 Several other research efforts have also utilized unstructured mesh with MOC. The MOC on Unstructured Mesh 37 (MOCUM) project is heavily focused on automatically converting CSG geometry into triangular elements. A Delaunay triangulation algorithm was created, allowing for simplified workflow from reactor geometry discretization to MOC solution.…”

Section: Iib Unstructured Mesh Moc State Of the Artmentioning

confidence: 99%

“…However, many aspects still remain unsolved. These include accurate reflective boundary condition treatment, 31,40 memory issues, 32 parallelization, 33,37,38 and parallel track generation. 33 This project aims to alleviate these issues through the development of MOCkingbird.…”

Section: Iib Unstructured Mesh Moc State Of the Artmentioning

confidence: 99%

Method of Characteristics for 3D, Full-Core Neutron Transport on Unstructured Mesh

et al. 2021

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A myriad of nuclear reactor designs are currently being considered for next-generation power production. These designs utilize unique geometries and materials and can rely on multiphysics effects for safety and operation. This work develops a neutron transport tool, MOCkingbird, capable of three-dimensional (3D), full-core reactor simulation for previously intractable geometries. The solver is based on the method of characteristics, utilizing unstructured mesh for the geometric description. MOCkingbird is built using the MOOSE multiphysics framework, allowing for straightforward linking to other physics in the future. A description of the algorithms and implementation is given, and solutions are computed for two-dimensional/3D C5G7 and the Massachusetts Institute of Technology BEAVRS benchmark. The final result shows the application of MOCkingbird to a 3D, full-core simulation utilizing 1.4 billion elements and solved using 12 000 processors.

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“…In order to better understand MOC’s viability for future whole core nuclear reactor analysis, MOC’s ability to efficiently utilize systems with large degrees of on-node parallelism must be demonstrated. Although MOC has been parallelized with OpenMP (Kochunas, 2013; Yang and Satvat, 2012) and CUDA (Boyd et al, 2013), to the authors’ knowledge, no published work presents a comprehensive evaluation of the parallel performance of MOC on multicore platforms.…”

Section: Introductionmentioning

confidence: 99%

Parallel performance results for the OpenMOC neutron transport code on multicore platforms

Boyd

Siegel

et al. 2016

The International Journal of High Performance Computing Applica

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The shift towards multi-core architectures has ushered in a new era of shared memory parallelism for scientific applications. This transition has introduced challenges for the nuclear engineering community as it seeks to design high-fidelity full-core reactor physics simulation tools. This paper describes the parallel transport sweep algorithm in the OpenMOC method of characteristics (MOC) neutron transport code for multi-core platforms using OpenMP. Strong and weak scaling studies are performed for both Intel Xeon and IBM Blue Gene/Q multi-core processors. The results demonstrate 100% parallel efficiency for 12 threads on 12 cores on Intel Xeon platforms, and over 90% parallel efficiency with 64 threads on 16 cores on the IBM Blue Gene/Q. These results illustrate the potential for hardware acceleration for MOC neutron transport on modern multi-core and future many-core architectures. In addition, this work highlights the pitfalls of programming for multi-core architectures, with a focal point on false sharing.

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MOCUM: A two-dimensional method of characteristics code based on constructive solid geometry and unstructured meshing for general geometries

Cited by 28 publications

References 10 publications

Prismatic VHTR neutronic benchmark problems

Prismatic VHTR neutronic benchmark problems

Method of Characteristics for 3D, Full-Core Neutron Transport on Unstructured Mesh

Parallel performance results for the OpenMOC neutron transport code on multicore platforms

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