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Proceedings Papers

Codes and Methods Improvements for VVER Comprehensive Safety Assessment: The CAMIVVER H2020 Project

Denis Verrier, Barbara Vezzoni, Barbara Calgaro, Olivier Bernard, Alberto Previti, Clément Lafaurie, Artur Hashymov, Pavlin Groudev, Antoaneta Stefanova, Neli Zaharieva, Frédéric Damian, Pietro Mosca, Daniele Tomatis, Ulrich Bieder, Adrien Willien, Nicolas Dos Santos, Luigi Mercatali, Victor Hugo Sanchez-Espinoza, Nicola Forgione, Sandro Paci
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A010, August 4–6, 2021
Paper No: ICONE28-64169
DOI: https://doi.org/10.1115/ICONE28-64169
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Topics: Physics, Pressurized water reactors, Safety, Computers, Computational fluid dynamics, Maintenance, Modeling, Nuclear industry, Security, Thermal hydraulics
Proceedings Papers

Equal Forced Time Step Approach to PSA for a Dynamic System – A Case of the Holdup Tank

E. E. Taapopi, H. Wang, J. Zhou
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, V003T12A011, August 4–6, 2021
Paper No: ICONE28-64081
DOI: https://doi.org/10.1115/ICONE28-64081
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Topics: Accidents, Boilers, Computers, Dynamic systems, Errors, Failure, Failure mechanisms, Nuclear power stations, Pressure, Probability
Proceedings Papers

RELAP5-3D Sensitivity Studies of Incorporating Axial Boron Gradients Into a Heater Tube Experiment for Pool Boiling CHF Testing in TREAT

Richard Hernandez, Nicholas R. Brown, Charles P. Folsom, Nicolas E. Woolstenhulme, Colby B. Jensen
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A041, August 4–5, 2020
Paper No: ICONE2020-16758
DOI: https://doi.org/10.1115/ICONE2020-16758
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Topics: Boron, Critical heat flux, Pool boiling, Testing, Coolants, Design, Shapes, Accidents, Heat flux, Heat transfer
Proceedings Papers

Simulation of Severe Accident Progression Using ROSHNI: A New Integrated Simulation Code for PHWR Severe Accidents

Sunil Nijhawan, YongMann Song
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T01A014, August 4–5, 2020
Paper No: ICONE2020-16633
DOI: https://doi.org/10.1115/ICONE2020-16633
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Topics: Accidents, Heavy water reactors, Simulation, Fuels, Design, Modeling, Vessels, Damage, Failure, Fluids
Proceedings Papers

Study of the Ageing Effects on the Lower Head Failure in a PWR Reactor

R. Lo Frano, S. Paci, P. Darnowski, P. Mazgaj
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T01A016, August 4–5, 2020
Paper No: ICONE2020-16664
DOI: https://doi.org/10.1115/ICONE2020-16664
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Topics: Failure, Finite element methods, Pressurized water reactors, Accidents, Nuclear power stations, Reactor vessels, Boundary-value problems, Computers, Engineering simulation, Materials properties
Proceedings Papers

Evolution and Implementation of the Design Extension Conditions (DEC) Concept: Assessment of Selected Events

Pavel Kral
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A017, July 22–26, 2018
Paper No: ICONE26-82593
DOI: https://doi.org/10.1115/ICONE26-82593
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Topics: Design, Safety, Acceptance criteria, Computers, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations
Proceedings Papers

Development of an Optimized Transport Solver in SARAX for Fast Reactor Analysis

Zhitao Xu, Hongchun Wu, Youqi Zheng, Mingtao He
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A081, July 22–26, 2018
Paper No: ICONE26-82380
DOI: https://doi.org/10.1115/ICONE26-82380
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Topics: Fast neutron reactors, Geometry, Storage, China, Computers, Elastic scattering, Mean free path, Neutrons, Resonance, Simulation
Proceedings Papers

Coupling Dependence of Multiple Operating Parameters on Burnup Credit Calculations for BWR Spent Fuel Assemblies

Shang-Chien Wu, Der-Sheng Chao, Jenq-Horng Liang
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A073, July 22–26, 2018
Paper No: ICONE26-82156
DOI: https://doi.org/10.1115/ICONE26-82156
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Topics: Boiling water reactors, Spent nuclear fuels, Fuels, Blades, Computers, Density, Manufacturing, Neutrons, Polynomials, Storage
Proceedings Papers

Research of Fast Modeling and Simulating Platform for Nuclear Power Plant Secondary Loop

Meijie Gong, Minjun Peng, Haishan Zhu
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A053, July 22–26, 2018
Paper No: ICONE26-81779
DOI: https://doi.org/10.1115/ICONE26-81779
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Topics: Modeling, Nuclear power stations, Simulation, Simulation models, Computers, Design, Simulation results
Proceedings Papers

Dose Minimization Game for Smartphones

Nolan Stelter, Arnav Das, Zahra Hanifah, Rizwan Uddin
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A089, July 22–26, 2018
Paper No: ICONE26-82450
DOI: https://doi.org/10.1115/ICONE26-82450
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Topics: Computers, Education, Modeling, Nuclear power, Physics, Radiation (Physics), Radiation sources, Teaching, X-rays
Proceedings Papers

Numerical Simulation for Nuclear Engineering Education: A Case Study in a Course “Advanced Nuclear Reactor Thermal Analysis”

Shanfang Huang, Yaopeng Gong, Chao Li, Ruilong Liu, Jiageng Wang, Kan Wang
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T12A002, July 22–26, 2018
Paper No: ICONE26-81042
DOI: https://doi.org/10.1115/ICONE26-81042
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Topics: Computer simulation, Education, Nuclear engineering, Nuclear reactors, Thermal analysis, Nuclear power, China, Computer software, Computers, Experimental design
Proceedings Papers

Analyzing the Impact of Solutes on PKA Spectrum for Simulation of Neutron Induced-Radiation Damage in Zr-Based Metals

Guang-bo Cai, Ya-dong Zhang, Yu-xiang Han, Jia-pei Yu
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A041, July 22–26, 2018
Paper No: ICONE26-82132
DOI: https://doi.org/10.1115/ICONE26-82132
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Topics: Damage, Metals, Neutrons, Radiation (Physics), Simulation, Zirconium, Computer simulation, Alloys, Atoms, Spectra (Spectroscopy)
Proceedings Papers

Development of a Thermal-Hydraulic Analysis Code for Helical Coiled Once Through Steam Generator

Jun Huang, Junli Gou, Haifu Ma, Jie Fan, Jianqiang Shan
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A014, July 22–26, 2018
Paper No: ICONE26-81945
DOI: https://doi.org/10.1115/ICONE26-81945
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Topics: Boilers, Heat transfer, Computers, Databases, Fluids, Heat exchangers, Nuclear power stations, Pressurized water reactors
Proceedings Papers

Non-LWR Model Development for the MELCOR Code

Larry Humphries, Brad Beeny, David Louie, Hossein Esmaili, Michael Salay
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A056, July 22–26, 2018
Paper No: ICONE26-82415
DOI: https://doi.org/10.1115/ICONE26-82415
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Topics: Light water reactors, Model development, Fluids, Modeling, Molten salt reactors, Sodium, Sodium fast reactors, Accidents, Graphite, Very high temperature reactors
Proceedings Papers

Thermal Hydraulic Analyses for PTS Evaluation: Comparison of Temperature Fields at RPV Predicted by System TH Code and CFD Code

Pavel Kral, Ladislav Vyskocil
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A001, July 22–26, 2018
Paper No: ICONE26-81007
DOI: https://doi.org/10.1115/ICONE26-81007
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Topics: Computational fluid dynamics, Temperature, Computers, Flow (Dynamics), Nuclear power stations, Testing, Thermal shock
Proceedings Papers

The Effect of Functional Spacers on the Liquid Film Thickness and Dryout in a BWR Fuel Bundle Model

Christian Bolesch, Lukas Robers, Robert Zboray, Horst-Michael Prasser
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A060, July 22–26, 2018
Paper No: ICONE26-81602
DOI: https://doi.org/10.1115/ICONE26-81602
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Topics: Boiling water reactors, Fuels, Liquid films, Flow (Dynamics), Heating, Design, Rods, Computational fluid dynamics, Computers, Drops
Proceedings Papers

JSNT-S: A Parallel 3D Discrete Ordinates Radiation Transport Code on Structured Mesh

Tangpei Cheng, Zeyao Mo, Chao Yang, Lili Wen, Li Deng
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A017, July 22–26, 2018
Paper No: ICONE26-82252
DOI: https://doi.org/10.1115/ICONE26-82252
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Topics: Radiation (Physics), Algorithms, Computer programming, Computers, Construction
Proceedings Papers

Nuclear Facility Safety Enhancement Using Sandia National Laboratories’ Computer Codes

David L. Y. Louie
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A006, July 22–26, 2018
Paper No: ICONE26-81097
DOI: https://doi.org/10.1115/ICONE26-81097
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Topics: Computers, Safety, Fire, Physics, Chemistry, Dynamics (Mechanics), Fluid mechanics, Industrial research, Leakage, Nuclear power stations
Proceedings Papers

Extended Ultimate Response Measures for Offshore Nuclear Power Plant Under Barge-Reactor Coupled Conditions

Jue Wang, Longze Li, Chen Hu, Wang Cong
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A002, July 22–26, 2018
Paper No: ICONE26-81159
DOI: https://doi.org/10.1115/ICONE26-81159
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Topics: Nuclear power stations, Ocean engineering, Seawater, Boilers, Design, Dimensions, Hazards, Heat, Accidents, Computers
Proceedings Papers

NPP I&C Safety Assessment by Aggregation of Formal Techniques

Eugene Babeshko, Vyacheslav Kharchenko, Kostiantyn Leontiiev, Oleg Odarushchenko, Oleksiy Strjuk
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T04A016, July 22–26, 2018
Paper No: ICONE26-82270
DOI: https://doi.org/10.1115/ICONE26-82270
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Topics: Nuclear power stations, Safety, Computer software, Failure mode and effects analysis, Computers, Control systems, Design, Failure mechanisms, Flow (Dynamics), Hardware