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Proceedings Papers

Validation of Evaluation Method of Feedback Reactivity for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors

Kazuo Yoshimura, Norihiro Doda, Masaaki Tanaka, Hidemasa Yamano, Kennichi Igawa
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T09A001, August 4–6, 2021
Paper No: ICONE28-62354
DOI: https://doi.org/10.1115/ICONE28-62354
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Topics: Dynamics (Mechanics), Evaluation methods, Feedback, Heat sinks, Sodium fast reactors
Proceedings Papers

Application of Best-Estimate Plus Uncertainty Analysis Method in Nuclear Safety Evaluation

Xinlu Tian, Jianping Jing, Shaoxin Zhuang, Haiying Chen
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T09A002, August 4–6, 2021
Paper No: ICONE28-64393
DOI: https://doi.org/10.1115/ICONE28-64393
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Topics: Safety, Uncertainty analysis
Proceedings Papers

Validation of Computational Fluid Dynamics Models for Industrial Applications

Milorad B. Dzodzo
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T09A008, August 4–6, 2021
Paper No: ICONE28-66712
DOI: https://doi.org/10.1115/ICONE28-66712
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Topics: Computational fluid dynamics
Proceedings Papers

Preliminary Verification Calculation and Sensitivity Analysis on PISAA Code Compared to MELCOR

Mingqiang Song, Ningna Zhang, Xiaoming Yang, Rubing Ma, Zhiyi Yang, Chao Ding
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T09A006, August 4–6, 2021
Paper No: ICONE28-64749
DOI: https://doi.org/10.1115/ICONE28-64749
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Topics: Accidents, Sensitivity analysis, Hydrogen production, Nuclear industry, China, Coolants, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Pressure
Proceedings Papers

Application of Finite Difference Jacobian Based Newton-Krylov Method for Coupled Neutronics/Thermal Conduction Problems of Nuclear Reactor

Baokun Liu, Yingjie Wu, Han Zhang, Jiong Guo, Fu Li
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T09A004, August 4–6, 2021
Paper No: ICONE28-64622
DOI: https://doi.org/10.1115/ICONE28-64622
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Topics: Heat conduction, Nonlinear systems, Nuclear reactors, Physics
Proceedings Papers

A Small PWR-Core Physical Calculation Based on PWR-Core Analysis Code CORAL

Wen Yang, Lun Zhou, Junrong Qiu, Yun Tai
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T09A007, August 4–6, 2021
Paper No: ICONE28-64912
DOI: https://doi.org/10.1115/ICONE28-64912
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Topics: Pressurized water reactors
Proceedings Papers

Verification of PWR-Core Analysis Code CORAL Using VERA Core Physics Benchmark

Wen Yang, Fei Chao, Jinrong Qiu, Xing Li, Baolin Liu
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T09A005, August 4–6, 2021
Paper No: ICONE28-64721
DOI: https://doi.org/10.1115/ICONE28-64721
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Topics: Physics, Pressurized water reactors
Proceedings Papers

Experiment on Vortex Shedding in Water Medium of Three-Way Closed Branch Pipe

Shuai Liu, Xuan Huang, ZhiPeng Feng, XiaoZhou Jiang, BiHao Wang
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T09A003, August 4–6, 2021
Paper No: ICONE28-64450
DOI: https://doi.org/10.1115/ICONE28-64450
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Topics: Pipes, Vibration, Vortex shedding, Water
Proceedings Papers

Code to Code Validation of SAC-3D Based on EBR-II Benchmark Problem

Daogang Lu, Siyu Lyu, Danting Sui
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A006, August 4–5, 2020
Paper No: ICONE2020-16666
DOI: https://doi.org/10.1115/ICONE2020-16666
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Topics: Accidents, Carbon reinforced plastics, China, Electricity (Physics), Fast neutron reactors, Feedback, Flow (Dynamics), Nuclear reactors, Safety, Scram
Proceedings Papers

Identifying the Cause of and Fixing Ill-Conditioned Matrices in Nuclear Analysis Codes

Lance C. Larsen
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A007, August 4–5, 2020
Paper No: ICONE2020-16903
DOI: https://doi.org/10.1115/ICONE2020-16903
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Topics: Errors, Nuclear industry, Physics
Proceedings Papers

Metamorphic Testing on Nuclide Inventory Tool

Meng Li, Shiyu Yan, Xiaohua Yang, Jie Liu
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A001, August 4–5, 2020
Paper No: ICONE2020-16403
DOI: https://doi.org/10.1115/ICONE2020-16403
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Topics: Nuclides, Testing, Algorithms, Approximation, Computer software, Nuclear magnetic resonance, Physics, Software development
Proceedings Papers

Sensitivity Analysis for Dynamical Response of Reactor Coolant System Based on OPTIMUS

Yuan Yanli, Ye Xianhui, Li Lijuan, Yuan Feng
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A002, August 4–5, 2020
Paper No: ICONE2020-16485
DOI: https://doi.org/10.1115/ICONE2020-16485
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Topics: Nuclear reactor coolants, Sensitivity analysis
Proceedings Papers

Applicability of Sub-Modelling Technique for Dynamic Analysis of Concrete Structures With Attached Equipment Under Missile Impact

Genadijs Sagals, Nebojsa Orbovic, Thambiayah Nitheanandan
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A003, August 4–5, 2020
Paper No: ICONE2020-16523
DOI: https://doi.org/10.1115/ICONE2020-16523
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Topics: Computer simulation, Concretes, Dynamic analysis, Missiles, Modeling, Reinforced concrete
Proceedings Papers

Design of an Innovative Moisture Separator Technology for Use in Nuclear Power Plants: Experimental Validation — Part 2

Carsten Hersberger, Elias Waldvogel, Joshua Bopp, Beat Ribi
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A004, August 4–5, 2020
Paper No: ICONE2020-16550
DOI: https://doi.org/10.1115/ICONE2020-16550
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Topics: Design, Molten salt reactors, Nuclear power stations, Steam
Proceedings Papers

Comparison of the Behavior of Different Jet Configurations in a Crossflow

Michael Lewandowski, Paul Kristo, Abdullah Weiss, Mark Kimber
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A005, August 4–5, 2020
Paper No: ICONE2020-16655
DOI: https://doi.org/10.1115/ICONE2020-16655
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Topics: Computation, Computational fluid dynamics, Coolants, Cross-flow, Flow (Dynamics), Flow control, Gas cooled reactors, Jets, Particulate matter, Statistics