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Liu Y, Hu R, Kraus A, Balaprakash P, Obabko A. Data-driven modeling of coarse mesh turbulence for reactor transient analysis using convolutional recurrent neural networks. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111716] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Zhang W, Wang D. Development of the reactor core isolation cooling system model for the extended station black-out accident. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111139] [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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Bao H, Dinh N, Lin L, Youngblood R, Lane J, Zhang H. Using deep learning to explore local physical similarity for global-scale bridging in thermal-hydraulic simulation. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107684] [Citation(s) in RCA: 14] [Impact Index Per Article: 2.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Lin L, Montanari N, Prescott S, Sampath R, Bao H, Dinh N. Adequacy evaluation of smoothed particle hydrodynamics methods for simulating the external-flooding scenario. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110720] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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System code evaluation of near-term accident tolerant claddings during boiling water reactor short-term and long-term station blackout accidents. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2019.110362] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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Wang J, Yeom H, Humrickhouse P, Sridharan K, Corradini M. Effectiveness of Cr-Coated Zr-Alloy Clad in Delaying Fuel Degradation for a PWR During a Station Blackout Event. NUCL TECHNOL 2019. [DOI: 10.1080/00295450.2019.1649566] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
Affiliation(s)
- J. Wang
- University of Wisconsin-Madison, Department of Nuclear Engineering and Engineering Physics, Madison, Wisconsin
| | - H. Yeom
- University of Wisconsin-Madison, Department of Nuclear Engineering and Engineering Physics, Madison, Wisconsin
| | | | - K. Sridharan
- University of Wisconsin-Madison, Department of Nuclear Engineering and Engineering Physics, Madison, Wisconsin
| | - M. Corradini
- University of Wisconsin-Madison, Department of Nuclear Engineering and Engineering Physics, Madison, Wisconsin
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Bao H, Dinh NT, Lane JW, Youngblood RW. A data-driven framework for error estimation and mesh-model optimization in system-level thermal-hydraulic simulation. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.04.023] [Citation(s) in RCA: 19] [Impact Index Per Article: 3.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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