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Zhang A, Dai M, Cheng M, Wu J, Chen J. Development of a GPU-based three-dimensional neutron transport code. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109156] [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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2
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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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3
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Oshima Y, Endo T, Yamamoto A. Impact of Angular and Spatial Source Distribution Approximations on Convergence Performance of Nonlinear Acceleration Methods for MOC in Slab Geometry. NUCL SCI ENG 2021. [DOI: 10.1080/00295639.2021.1982549] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
Affiliation(s)
- Yoshiki Oshima
- Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8603, Japan
| | - Tomohiro Endo
- Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8603, Japan
| | - Akio Yamamoto
- Nagoya University, Furo-cho, Chikusa-ku, Nagoya 464-8603, Japan
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Shen Q, Choi S, Kochunas B. A Robust, Relaxation-Free Multiphysics Iteration Scheme for CMFD-Accelerated Neutron Transport k-Eigenvalue Calculations—II: Numerical Results. NUCL SCI ENG 2021. [DOI: 10.1080/00295639.2021.1906586] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
Affiliation(s)
- Qicang Shen
- University of Michigan, Department of Nuclear Engineering and Radiological Sciences, Ann Arbor, Michigan 48109-2104
| | - Sooyoung Choi
- University of Michigan, Department of Nuclear Engineering and Radiological Sciences, Ann Arbor, Michigan 48109-2104
| | - Brendan Kochunas
- University of Michigan, Department of Nuclear Engineering and Radiological Sciences, Ann Arbor, Michigan 48109-2104
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Marvin: A parallel three-dimensional transport code based on the discrete ordinates method for reactor shielding calculations. PROGRESS IN NUCLEAR ENERGY 2021. [DOI: 10.1016/j.pnucene.2021.103786] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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6
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A linearized coarse mesh finite difference preconditioner for the within-group Krylov subspace iteration based on two-dimensional method of characteristics. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2020.107889] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Zhang G, Yang WS. IMPLEMENTATION OF QUADRATIC AXIAL TRIAL FUNCTIONS IN THE HIGH-FIDELITY TRANSPORT CODE PROTEUS-MOC. EPJ WEB OF CONFERENCES 2021. [DOI: 10.1051/epjconf/202124703015] [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
PROTEUS-MOC is a pin-resolved high-fidelity transport code, in which the axial variation of angular flux is represented in terms of orthogonal polynomials. Currently, PROTEUS-MOC employs linear functions and requires relatively fine axial meshes to achieve high accuracy, which increases the number of axial meshes and hence the memory requirement. In this study, aiming to reduce the memory requirement and potentially the computational time by allowing larger axial meshes, we have extended the PROTEUS-MOC transport solution method to quadratic trial functions. Preliminary tests for the performance of quadratic trial functions have been performed using the 3-D C5G7 benchmark problem. Test results showed that for the same axial mesh configuration with relatively large sizes, the quadratic approximation yields about 2 to 5 times more accurate pin powers than the linear approximation, depending on the degree of axial variation of angular fluxes. The quadratic approximation also allows the use of about 3 times coarser axial meshes than the linear approximation for comparable pin power accuracy, which consequently reduces the memory requirement by about 2 times. The memory reduction is not proportional because of the increased number of coefficients in each element from 2 to 3. However, the quadratic approximation did not reduce the computational time as expected because of the deteriorated performance of the pCMFD acceleration scheme due to large axial mesh sizes.
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Zhang G, Yang WS. Quadratic axial expansion function with sub-plane acceleration scheme for the high-fidelity transport code PROTEUS-MOC. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107713] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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10
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Hsieh A, Zhang G, Yang WS. Consistent Transport Transient Solvers of the High-Fidelity Transport Code PROTEUS-MOC. NUCL SCI ENG 2020. [DOI: 10.1080/00295639.2020.1746619] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
Affiliation(s)
- Albert Hsieh
- University of Michigan, Department of Nuclear Engineering and Radiological Sciences, 2355 Bonisteel Boulevard, Ann Arbor, Michigan 48109
| | - Guangchun Zhang
- University of Michigan, Department of Nuclear Engineering and Radiological Sciences, 2355 Bonisteel Boulevard, Ann Arbor, Michigan 48109
| | - Won Sik Yang
- University of Michigan, Department of Nuclear Engineering and Radiological Sciences, 2355 Bonisteel Boulevard, Ann Arbor, Michigan 48109
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Chan Y, Xiao S. A Linear Prolongating Coarse Mesh Finite Difference Acceleration of Discrete Ordinate Neutron Transport Calculation Based on Discontinuous Galerkin Finite Element Method. NUCL SCI ENG 2020. [DOI: 10.1080/00295639.2020.1752045] [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)
- Yimeng Chan
- National University of Singapore, Singapore Nuclear Research and Safety Initiative, 1 CREATE Way, CREATE Tower #04-01, Singapore 138602, Singapore
| | - Sicong Xiao
- National University of Singapore, Singapore Nuclear Research and Safety Initiative, 1 CREATE Way, CREATE Tower #04-01, Singapore 138602, Singapore
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Kang L, Hao C, Zhao Q, Xu Y. Two-level time-dependent GET based CMFD acceleration for 3D whole core transient transport simulation using 2D/1D method. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107405] [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]
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13
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Tsujita K, Endo T, Yamamoto A. Application of the multigrid amplitude function method for time-dependent MOC based on the linear source approximation. J NUCL SCI TECHNOL 2020. [DOI: 10.1080/00223131.2019.1709993] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
Affiliation(s)
- Kosuke Tsujita
- Design and Analysis Group, Design Service Division, Nuclear Engineering, Ltd, Osaka, Japan
| | - Tomohiro Endo
- Department of Applied Energy, Nagoya University, Nagoya-shi, Japan
| | - Akio Yamamoto
- Department of Applied Energy, Nagoya University, Nagoya-shi, Japan
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