Hybrid super homogenization and discontinuity factor method for continuous finite element diffusion

Labouré, Vincent; Wang, Yaqi; Ortensi, Javier; Gleicher, Frederick; Martineau, Richard

doi:10.1016/j.anucene.2019.01.003

Cited by 27 publications

(15 citation statements)

References 12 publications

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“…This approach is still guaranteed to preserve the multiplication factor and the integrated leakage out of the SPH regions as long as all the fuel is corrected, as demonstrated in Ref. 68, and leveraged on full-core, multiphysics applications such as the hightemperature test reactor. 69 Super-homogenization was also successfully applied for modeling steady-state and transient simulations of TREAT (Ref.…”

Section: Iib3 Homogenization Equivalencementioning

confidence: 99%

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Rattlesnake: A MOOSE-Based Multiphysics Multischeme Radiation Transport Application

et al. 2021

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Advanced reactor concepts span the spectrum from heat pipe-cooled microreactors, through thermal and fast molten-salt reactors, to gas-and salt-cooled pebble bed reactors. The modeling and simulation of each of these reactor types comes with their own geometrical complexities and multiphysics challenges. However, the common theme for all nuclear reactors is the necessity to be able to accurately predict neutron distribution in the presence of multiphysics feedback. We argue that the current standards of modeling and simulation, which couple single-physics, single-reactor-focused codes via ad hoc methods, are not sufficiently flexible to address the challenges of modeling and simulation for advanced reactors. In this work, we present the Multiphysics Object Oriented Simulation Environment (MOOSE)-based radiation transport application Rattlesnake. The use of Rattlesnake for the modeling and simulation of nuclear reactors represents a paradigm shift away from makeshift data exchange methods, as it is developed based on the MOOSE platform with its very natural form of shared data distribution. Rattlesnake is well equipped for addressing the geometric and multiphysics challenges of advanced reactor concepts because it is a flexible finite element tool that leverages the multiphysics capabilities inherent in MOOSE. This paper focuses on the concept and design of Rattlesnake. We also demonstrate the capabilities and performance of Rattlesnake with a set of problems including a microreactor, a molten-salt reactor, a pebble bed reactor, the Advanced Test Reactor at the Idaho National Laboratory, and two benchmarks: a multiphysics version of the C5G7 benchmark and the LRA benchmark.

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Section: Iib3 Homogenization Equivalencementioning

confidence: 99%

“…66,67 Rattlesnake also allows SPH and DFs to coexist for preserving leakage across a domain that cannot be preserved with traditional SPH (Ref. 68). This extension allows the application of homogenization equivalence on subdomains to support mixed homogeneous and heterogeneous multischeme calculations.…”

Section: Iib3 Homogenization Equivalencementioning

confidence: 99%

Rattlesnake: A MOOSE-Based Multiphysics Multischeme Radiation Transport Application

et al. 2021

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“…In addition, it supports full-core homogenization equivalence techniques in order to preserve reference quantities of interest, such as multiplication factor and reaction rates, while using coarsely homogenized geometries. 29,30 MC2-3 is a FORTRAN multigroup cross-section generation code for fast reactor analysis, relying on advanced resonance self-shielding and spectrum calculation methods. 31 PROTEUS is a FORTRAN neutron transport code offering different solving strategies, including nodal, S N , and the method of characteristics (MOC), which combines a two-dimensional (2-D) MOC with the discontinuous Galerkin FEM for the axial direction.…”

Section: Iiia2 Griffinmentioning

confidence: 99%

Coupled Multiphysics Simulations of Heat Pipe Microreactors Using DireWolf

et al. 2021

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program, the DireWolf software application's objective is to provide the nuclear community with a design and safety analysis simulation capability. Based upon the NEAMS program Multiphysics Object-Oriented Simulation Environment (MOOSE) computational framework, DireWolf tightly couples nuclear microreactor physics, reactor physics, radiation transport, nuclear fuel performance, heat pipe thermal hydraulics, power generation, and structural mechanics to resolve the interdependent nonlinearities. DireWolf is capable of simulating both steady and transient normal reactor operation and several postulated failure scenarios. We will present the fundamental physics of heat pipe-cooled nuclear microreactors and the MOOSE-based software employed in DireWolf. Both steady and transient results for coupled reactor physics, radiation transport, and nuclear fuel performance are demonstrated.

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“…Alternatively, the angular dependence of the neutron scattering cross section could be used to describe macroscopic neutron transport behavior. For example, using an equivalence technique similar to SuPer Homogenization (SPH), one could develop a method by which neutron streaming effects were described by an angularly dependent neutron scattering cross section [7,8]. Such a method would allow for the preservation of neutron streaming typically lost during spatial homogenization.…”

Section: Nature Of Anisotropic Neutron Scatteringmentioning

confidence: 99%

Comparison of Generation of Higher-Order Neutron Scattering Cross Sections

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Ortensi

DeHart

et al. 2020

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The generation of high scattering order neutron scattering cross sections consistent with high-fidelity simulations remains an area of active research. Popular options include generating cross sections from continuous energy Monte Carlo calculations or from a deterministic neutron transport calculation with high-fidelity tabulated cross sections. Both options present challenges. Monte Carlo simulations can naturally process continuous energy cross-section data and allow for the general description of anisotropic neutron scattering given a scattering law. However, Monte Carlo simulations are inherently related to particle weighting and it has been suggested that this may be unacceptable for generating high-order neutron scattering cross sections. Deterministic neutron transport calculations can easily calculate high-order moments of the flux to appropriately calculate higher-order neutron scattering cross sections but are generally limited by discretization of space, energy, and angle. In this work, the trade-offs between generation of high-order neutron scattering cross sections via Monte Carlo and deterministic neutron transport methods are investigated. The methods implemented in the Monte Carlo computer program Serpent 2 and the deterministic fast reactor neutron cross section generator MC 2-3 are compared. Cross sections resulting from these methods are used in Rattlesnake, a deterministic neutron transport code developed by Idaho National Laboratory, and results are compared to a reference continuous energy Monte Carlo calculation. Whereas previous work investigating the effects of anisotropic neutron scattering has focused on light water reactor simulations, this work focuses on high-order neutron scattering cross sections as they relate to fast reactor simulations. To investigate the consequences of the Serpent 2 and MC 2-3 methodologies, a test problem is developed. The test problem is a one-dimensional geometry with fast reactor materials designed to demonstrate deep penetration and exacerbate the effects of high-order neutron scattering. Based on the results of the deep penetration test problem, it is concluded that P 3 neutron scattering cross sections are sufficient to describe anisotropic scattering in fast reactor materials. Any neutron scattering of order higher than P 3 offers negligible change in the eigenvalue of the test problem. Additionally, it is determined that the methodology as implemented in Serpent 2 is applicable for generating high-order neutron scattering cross sections through at least P 3 in fast reactor materials. List of Figures 1 Ultrafine Group (UFG) to Broad Group (BG) Group Condensation in MC 2-3

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Hybrid super homogenization and discontinuity factor method for continuous finite element diffusion

Cited by 27 publications

References 12 publications

Rattlesnake: A MOOSE-Based Multiphysics Multischeme Radiation Transport Application

Rattlesnake: A MOOSE-Based Multiphysics Multischeme Radiation Transport Application

Coupled Multiphysics Simulations of Heat Pipe Microreactors Using DireWolf

Comparison of Generation of Higher-Order Neutron Scattering Cross Sections

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