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Shemon E, Miao Y, Kumar S, Mo K, Jung YS, Oaks A, Richards S, Giudicelli G, Harbour L, Stogner R. MOOSE Reactor Module: An Open-Source Capability for Meshing Nuclear Reactor Geometries. NUCL SCI ENG 2023. [DOI: 10.1080/00295639.2022.2149231] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 02/11/2023]
Affiliation(s)
- Emily Shemon
- Argonne National Laboratory, Nuclear Science and Engineering Division, Lemont, Illinois
| | - Yinbin Miao
- Argonne National Laboratory, Chemical and Fuel Cycle Technologies Division, Lemont, Illinois
| | - Shikhar Kumar
- Argonne National Laboratory, Nuclear Science and Engineering Division, Lemont, Illinois
| | - Kun Mo
- Argonne National Laboratory, Chemical and Fuel Cycle Technologies Division, Lemont, Illinois
| | - Yeon Sang Jung
- Argonne National Laboratory, Nuclear Science and Engineering Division, Lemont, Illinois
| | - Aaron Oaks
- Argonne National Laboratory, Chemical and Fuel Cycle Technologies Division, Lemont, Illinois
| | - Scott Richards
- Argonne National Laboratory, Nuclear Science and Engineering Division, Lemont, Illinois
| | | | - Logan Harbour
- Idaho National Laboratory, Computational Frameworks Group, Idaho Falls, Idaho
| | - Roy Stogner
- Idaho National Laboratory, Computational Frameworks Group, Idaho Falls, Idaho
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Liu C, Zhang B, Wei J, Tan S. Verification of multilevel octree grid algorithm of S transport calculation with the Balakovo-3 VVER-1000 neutron dosimetry benchmark. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2022.10.017] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/06/2022]
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Kong B, Zhu K, Zhang H, Hao C, Guo J, Li F. A Discontinuous Galerkin Finite Element Method based axial SN for the 2D/1D transport method. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104391] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Liu C. Doppler broadening using discrete cosine transform and kernel reconstruction for spatially variable media. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109150] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/01/2022]
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Reactor physics study of square and hexagonal lattice cell using MANTRA ( ethod of Ch racteristics based eutron nsport Code) coupled with resonance treated multi energy group cross section library. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109072] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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Investigation and Validation of Unstructured Mesh Methodologies for Modeling Experimental Reactors. ENERGIES 2022. [DOI: 10.3390/en15041512] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
Abstract
This paper summarizes a methodology developed at École Polytechnique Fédérale de Lausanne for the neutronic modeling of the CROCUS experimental reactor and proposes solutions to the challenges one may face while modeling a research reactor with a complex geometry. Indeed, the double-lattice configuration of CROCUS makes it difficult to use codes for neutron diffusion and transport relying on a structured mesh description. For this reason, and based on the available in-house competences, we decided to make use of the neutronic capabilities of the GeN-Foam multiphysics solver, which takes advantage of general finite volume methodologies on unstructured meshes to provide sufficient flexibility for the study of unconventional reactor designs. In this work, GeN-Foam is used to build a first SP3 model of CROCUS based on an unstructured mesh to have an explicit modeling of the double lattice and the water gap between the two lattices. Form functions are then used to reconstruct the intra-pin fission rates for validation against measured distributions. We also discuss the limitations of the SP3 approximation of neutron transport in regions with steep neutron flux gradients and the planned future developments.
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