Stabilization of multi-group neutron transport with transport-corrected cross-sections

Gunow, Geoffrey Alexander; Forget, Benoit; Smith, Kord

doi:10.1016/j.anucene.2018.10.036

Cited by 6 publications

(1 citation statement)

References 4 publications

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“…Transport-corrected cross sections have been shown to sometimes cause the source iteration scheme outlined previously to diverge. 56 The transport correction is a modification to the cross sections to take anisotropic effects into account. 57 Using ΔΣ tr;g as the correction, it is applied through modification of the total and scattering cross sections:…”

Section: Ivd Transport Correction and Stabilizationmentioning

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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Section: Ivd Transport Correction and Stabilizationmentioning

confidence: 99%