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Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64721
https://doi.org/10.1115/ICONE28-64721
View Paper titled, Verification of PWR-Core Analysis Code CORAL Using VERA Core Physics Benchmark
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Topics: Physics, Pressurized water reactors
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64450
https://doi.org/10.1115/ICONE28-64450
View Paper titled, Experiment on Vortex Shedding in Water Medium of Three-Way Closed Branch Pipe
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Topics: Pipes, Vibration, Vortex shedding, Water
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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-62354
https://doi.org/10.1115/ICONE28-62354
View Paper titled, Validation of Evaluation Method of Feedback Reactivity for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64393
https://doi.org/10.1115/ICONE28-64393
View Paper titled, Application of Best-Estimate Plus Uncertainty Analysis Method in Nuclear Safety Evaluation
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Topics: Safety, Uncertainty analysis
Proceedings Papers

Validation of Computational Fluid Dynamics Models for Industrial Applications

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-66712
https://doi.org/10.1115/ICONE28-66712
View Paper titled, Validation of Computational Fluid Dynamics Models for Industrial Applications
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Topics: Computational fluid dynamics
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64749
https://doi.org/10.1115/ICONE28-64749
View Paper titled, Preliminary Verification Calculation and Sensitivity Analysis on PISAA Code Compared to MELCOR
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64622
https://doi.org/10.1115/ICONE28-64622
View Paper titled, Application of Finite Difference Jacobian Based Newton-Krylov Method for Coupled Neutronics/Thermal Conduction Problems of Nuclear Reactor
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64912
https://doi.org/10.1115/ICONE28-64912
View Paper titled, A Small PWR-Core Physical Calculation Based on PWR-Core Analysis Code CORAL
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Topics: Pressurized water reactors
Proceedings Papers

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

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Daogang Lu, Siyu Lyu, Danting Sui
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A006, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16666
https://doi.org/10.1115/ICONE2020-16666
View Paper titled, Code to Code Validation of SAC-3D Based on EBR-II Benchmark Problem
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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

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Lance C. Larsen
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A007, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16903
https://doi.org/10.1115/ICONE2020-16903
View Paper titled, Identifying the Cause of and Fixing Ill-Conditioned Matrices in Nuclear Analysis Codes
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Topics: Errors, Nuclear industry, Physics
Proceedings Papers

Metamorphic Testing on Nuclide Inventory Tool

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16403
https://doi.org/10.1115/ICONE2020-16403
View Paper titled, Metamorphic Testing on Nuclide Inventory Tool
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16485
https://doi.org/10.1115/ICONE2020-16485
View Paper titled, Sensitivity Analysis for Dynamical Response of Reactor Coolant System Based on OPTIMUS
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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

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Genadijs Sagals, Nebojsa Orbovic, Thambiayah Nitheanandan
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A003, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16523
https://doi.org/10.1115/ICONE2020-16523
View Paper titled, Applicability of Sub-Modelling Technique for Dynamic Analysis of Concrete Structures With Attached Equipment Under Missile Impact
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16550
https://doi.org/10.1115/ICONE2020-16550
View Paper titled, Design of an Innovative Moisture Separator Technology for Use in Nuclear Power Plants: Experimental Validation — Part 2
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16655
https://doi.org/10.1115/ICONE2020-16655
View Paper titled, Comparison of the Behavior of Different Jet Configurations in a Crossflow
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Topics: Computation, Computational fluid dynamics, Coolants, Cross-flow, Flow (Dynamics), Flow control, Gas cooled reactors, Jets, Particulate matter, Statistics