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Dai M, Zhang A, Cheng M. Improvement of the 3D MOC/DD neutron transport method with thin axial meshes. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2023.109731] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 02/09/2023]
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Gammicchia A, Santandrea S, Dulla S. Cross sections polynomial axial expansion within the APOLLO3® 3D characteristics method. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2021.108673] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/01/2022]
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Brighenti A, Santandrea S, Zmijarevic I, Stankovski Z. Development and validation of a time-dependent deterministic model for neutron noise on CROCUS experimental measurements. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2021.108753] [Citation(s) in RCA: 2] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/01/2022]
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Gaston DR, Forget B, Smith KS, Harbour LH, Ridley GK, Giudicelli GG. Method of Characteristics for 3D, Full-Core Neutron Transport on Unstructured Mesh. NUCL TECHNOL 2021. [DOI: 10.1080/00295450.2021.1871995] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
Affiliation(s)
- Derek R. Gaston
- Idaho National Laboratory, 1955 N. Fremont Avenue, Idaho Falls, Idaho 83415
| | - Benoit Forget
- Massachusetts Institute of Technology, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139
| | - Kord S. Smith
- Massachusetts Institute of Technology, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139
| | - Logan H. Harbour
- Idaho National Laboratory, 1955 N. Fremont Avenue, Idaho Falls, Idaho 83415
| | - Gavin K. Ridley
- Idaho National Laboratory, 1955 N. Fremont Avenue, Idaho Falls, Idaho 83415
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Cattaneo P, Lenain R, Merle E, Patricot C, Schneider D. NUMERICAL OPTIMIZATION OF A MULTIPHYSICS CALCULATION SCHEME. EPJ WEB OF CONFERENCES 2021. [DOI: 10.1051/epjconf/202124706008] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
This work concerns the numerical optimization of a multiphysics calculation scheme. The considered application is a 5x5 Pressurized Water Reactor (PWR) assemblies mini-core surrounded by radial and axial reflectors. The scenario adopted for the analysis is steady-state nominal conditions and fission products set to the equilibrium concentration. The neutronics is modelled at the pin-cell scale and the thermal-hydraulics at the subchannel level. Depending on the scenario, the damped fixed-point algorithm might not be sufficiently robust or efficient enough. For this reason, a technique based on the partial convergence of the solvers is tested. In every multiphysic iteration, a maximum number of iterations is imposed for both the neutronics and the thermal-hydraulics solvers. In combination with that, the solver restarts from the results of the last calculation. In this way, if the method is convergent, the initialization progresses towards the fixed-point solution. The results show that such a technique improves both the robustness and the speed of the algorithm. Within this approach, the range of relaxation factors that makes the algorithm converge is significantly broadened and the importance of this parameter on the global performance is reduced. The computing time also decreases by a factor between 10 and 20. Furthermore, this gain does not strongly depend on the exact imposed maximum number of iterations. Some preliminary observations are also reported in respect with the application of such a technique to the Anderson acceleration method.
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Giudicelli G, Smith K, Forget B. Generalized Equivalence Theory Used with Spatially Linear Sources in the Method of Characteristics for Neutron Transport. NUCL SCI ENG 2020. [DOI: 10.1080/00295639.2020.1765606] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
Affiliation(s)
- Guillaume Giudicelli
- Massachusetts Institute of Technology, Nuclear Science and Engineering Department, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139
| | - Kord Smith
- Massachusetts Institute of Technology, Nuclear Science and Engineering Department, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139
| | - Benoit Forget
- Massachusetts Institute of Technology, Nuclear Science and Engineering Department, 77 Massachusetts Avenue, Cambridge, Massachusetts 02139
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Application of TULIP/STREAM code in 2-D fast reactor core high-fidelity neutronic analysis. NUCLEAR ENGINEERING AND TECHNOLOGY 2019. [DOI: 10.1016/j.net.2019.06.010] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Jarrett M, Kochunas B, Larsen E, Downar T. Polar Parity for Efficient Evaluation of Anisotropic Transverse Leakage in the 2D/1D Transport Method. NUCL SCI ENG 2019. [DOI: 10.1080/00295639.2019.1627176] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
Affiliation(s)
- Michael Jarrett
- University of Michigan, Department of Nuclear Engineering and Radiological Sciences, 2355 Bonisteel, Ann Arbor, Michigan 48109
| | - Brendan Kochunas
- University of Michigan, Department of Nuclear Engineering and Radiological Sciences, 2355 Bonisteel, Ann Arbor, Michigan 48109
| | - Edward Larsen
- University of Michigan, Department of Nuclear Engineering and Radiological Sciences, 2355 Bonisteel, Ann Arbor, Michigan 48109
| | - Thomas Downar
- University of Michigan, Department of Nuclear Engineering and Radiological Sciences, 2355 Bonisteel, Ann Arbor, Michigan 48109
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Faure B, Archier P, Vidal JF, Buiron L. A 2D/1D Algorithm for Effective Cross-Section Generation in Fast Reactor Neutronic Transport Calculations. NUCL SCI ENG 2018. [DOI: 10.1080/00295639.2018.1480190] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
Affiliation(s)
- Bastien Faure
- CEA, DEN, DER, SPRC, Cadarache, Saint-Paul-lez-Durance F-13108, France
| | - Pascal Archier
- CEA, DEN, DER, SPRC, Cadarache, Saint-Paul-lez-Durance F-13108, France
| | | | - Laurent Buiron
- CEA, DEN, DER, SPRC, Cadarache, Saint-Paul-lez-Durance F-13108, France
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The linear source approximation and particle conservation in the Method of Characteristics for isotropic and anisotropic sources. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2018.01.023] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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