A Neutron Transport Characteristics Method for 3D Axially Extruded Geometries Coupled with a Fine Group Self-Shielding Environment

Santandrea, Simone; Sciannandrone, Daniele; Sanchez, Richard; Mao, Li; Graziano, Laurent

doi:10.1080/00295639.2016.1273634

Cited by 15 publications

(4 citation statements)

References 2 publications

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“…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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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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“…The angular directions come from an angular quadrature which is also used to compute the angular flux moments from the angular fluxes. The latter are iteratively computed from the region wise flat sources by sweeping the domain along a prescribed set of straight parallel trajectories for each of the angular directions (Santandrea et al, 2017).…”

Section: Time Discretizationmentioning

confidence: 99%

“…In fact, starting from a critical, unperturbed condition, any deviation from the average criticality is taken into account by a "dynamic eigenvalue" defined ad hoc. The computational scheme is realized inside the TDT (Two/Three Dimensional Transport) solver (Santandrea, 2007;Santandrea et al, 2017) and implemented in the APOLLO3 R system. Another example, still based on temporal discretization, is given in Viebach et al (2018): in the framework of the DYN3D code, noise calculations are performed in the time domain and within a fully multi-physics framework, including the system feedback to establish criticality during the noise perturbation.…”

Section: Introductionmentioning

confidence: 99%

A MOC-based neutron kinetics model for noise analysis

Gammicchia

Santandrea

Zmijarevic

et al. 2020

Annals of Nuclear Energy

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A 2-D noise model is implemented in the deterministic reactor code APOLLO3 R to simulate a periodic oscillation of a structural component. The Two/Three Dimensional Transport (TDT) solver, using the Method of Characteristics, is adopted for the calculation of the case studies, constituted by a moving detector and control-rod bundle. The periodic movement is built by properly linking the geometries corresponding to the temporal positions. The calculation is entirely performed in the real time domain, without resorting to the traditional frequency approach. A specifically defined dynamic eigenvalue is used to renormalize in average the reactivity over a period. The algorithm is accelerated by the DP N synthetic method. For each cell of the domain, the time values of fission rates are analysed to determine the noise extent. Moreover we propose a systematic approach to the definition of the macroscopic cross sections to be used in dynamical calculations starting from library data. As an aside of our work we have found that even in static calculation this approach can produce significant changes.

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“…The APOLLO3 flux calculations were carried out by the two-dimensional 390 TDT method of characteristics (MOC) solver (Sanchez & Chetaine, 2000;Santandrea et al, 2017). The tracking parameters for the TDT MOC solver were 32 azimuthal angles, 4 polar angles defined by the Bickley formula (Sanchez et al, 2002), and a transverse integration step of 0.01 cm.…”

Section: Pwr Fuel Assembliesmentioning

confidence: 99%

A subgroup method based on the equivalent Dancoff-factor cell technique in APOLLO3® for thermal reactor calculations

Mao

Zmijarevic

Sanchez

2020

Annals of Nuclear Energy

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A Neutron Transport Characteristics Method for 3D Axially Extruded Geometries Coupled with a Fine Group Self-Shielding Environment

Cited by 15 publications

References 2 publications

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

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

A MOC-based neutron kinetics model for noise analysis

A subgroup method based on the equivalent Dancoff-factor cell technique in APOLLO3® for thermal reactor calculations

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