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Proceedings Papers

Propagation of Nuclear Data Uncertainties in PWR Pin-Cell Burnup Calculations via Stochastic Sampling

Luigi Mercatali, Yousef Alzaben, Victor Hugo Sanchez Espinoza
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A033, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81711
https://doi.org/10.1115/ICONE26-81711
View Paper titled, Propagation of Nuclear Data Uncertainties in PWR Pin-Cell Burnup Calculations via Stochastic Sampling
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Topics: Pressurized water reactors, Uncertainty, Safety, Design, Economics , Light water reactors, Manufacturing, Modeling, Nuclear reactor safety, Nuclear research
Proceedings Papers

15 Years of the European Nuclear Education Network (ENEN Association)

Leon Cizelj, Jörg Starflinger, Veronique Decobert, Behrooz Bazargan-Sabet, Filip Tuomisto, Michèle Coeck, Pascal Anzieu, John Roberts, Tzanny Kokalova Wheldon, Pedro Dieguez Porras
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T12A007, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82611
https://doi.org/10.1115/ICONE26-82611
View Paper titled, 15 Years of the European Nuclear Education Network (ENEN Association)
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Topics: Education, Collaboration, Engineering disciplines, Engineering teachers, Knowledge management, Nuclear engineering, Nuclear industry, Nuclear power, Nuclear research, Preservation
Proceedings Papers

Development and Preliminary Validation of a STH-CFD Coupling Method for Multiscale Thermal-Hydraulic Simulations of the MYRRHA Reactor

A. Toti, J. Vierendeels, F. Belloni
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T10A018, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60438
https://doi.org/10.1115/ICONE24-60438
View Paper titled, Development and Preliminary Validation of a STH-CFD Coupling Method for Multiscale Thermal-Hydraulic Simulations of the MYRRHA Reactor
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Topics: Computational fluid dynamics, Simulation, Flow (Dynamics), Transients (Dynamics), Design, Fluids, Modeling, Nuclear power stations, Nuclear research, Safety
Proceedings Papers

Decommissioning of Obsolete Nuclear Facilities in the UJV Rez, a. s.

Milan Tous, Josef Podlaha
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T08A021, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31155
https://doi.org/10.1115/ICONE22-31155
View Paper titled, Decommissioning of Obsolete Nuclear Facilities in the UJV Rez, a. s.
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Topics: Nuclear decommissioning, Nuclear power stations, Blasting, Decontamination, Ice, Nuclear research, Radioactive wastes, Water
Proceedings Papers

MELCOR Study of VVER-1000 Behavior in Case of Overheated Reactor Core Quenching

Pavlin P. Groudev, Antoaneta E. Stefanova, Petya I. Vryashkova
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A040, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30941
https://doi.org/10.1115/ICONE22-30941
View Paper titled, MELCOR Study of VVER-1000 Behavior in Case of Overheated Reactor Core Quenching
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Topics: Quenching (Metalworking), Fuels, Accidents, Reactor vessels, Accident management, Cladding systems (Building), Melting, Modeling, Porosity, Temperature
Proceedings Papers

RELAP5-3D Assessment Using a Qualified Experimental Database

F. Fiori, A. Kovtonyuk, A. Petruzzi, M. Kovtonyuk, F. D’Auria
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A114, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16749
https://doi.org/10.1115/ICONE21-16749
View Paper titled, RELAP5-3D Assessment Using a Qualified Experimental Database
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Topics: Databases, Transients (Dynamics), Uncertainty, Accidents, Licensing, Modeling, Nuclear power stations, Nuclear research, Pressurized water reactors, Quality control
Proceedings Papers

Dynamic Behavior Analysis of a Supercritical Water Cooled System Using Modified ATHLET

Chong Zhou, Xu Cheng, Yanhua Yang
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 599-607, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54429
https://doi.org/10.1115/ICONE20-POWER2012-54429
View Paper titled, Dynamic Behavior Analysis of a Supercritical Water Cooled System Using Modified ATHLET
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Topics: Water, Coolants, Design, Accidents, Fuels, Licensing, Manufacturing, Nuclear research, Pumps, Safety
Proceedings Papers

Estimation of Emergency Planning Zones (EPZs) for Nuclear Research Reactor Using Plume Dispersion Code

Mazzammal Hussain, Salah Ud-Din Khan, Waqar A. Adil Syed
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 479-483, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54964
https://doi.org/10.1115/ICONE20-POWER2012-54964
View Paper titled, Estimation of Emergency Planning Zones (EPZs) for Nuclear Research Reactor Using Plume Dispersion Code
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Topics: Accidents, Emergency management, Nuclear research, Plumes (Fluid dynamics)
Proceedings Papers

Development of a Core Management Tool for MYRRHA: Work in Progress

David Jaluvka, Gert Van den Eynde, Stefan Vandewalle
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 625-631, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54542
https://doi.org/10.1115/ICONE20-POWER2012-54542
View Paper titled, Development of a Core Management Tool for MYRRHA: Work in Progress
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Topics: Design, Education, Fuel management, Fuels, Irradiation (Radiation exposure), Machinery, Nuclear research, Optimization, Radioisotopes, Silicon
Proceedings Papers

National Technical University of Ukraine “Kiev Politechnical Institute” and its Nuclear Education Programs

M. Z. Zgurovskiy, E. N. Pis’mennyi, V. G. Razumovskiy, I. L. Pioro
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 873-878, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55265
https://doi.org/10.1115/ICONE20-POWER2012-55265
View Paper titled, National Technical University of Ukraine “Kiev Politechnical Institute” and its Nuclear Education Programs
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Topics: Aircraft, Aviation, Computer simulation, Education, Energy engineering, Engineering mechanics, Engineers, Heat, Helicopters, Industrial research
Proceedings Papers

IDEA: An Integrated Set of Tools for Sustainable Nuclear Decommissioning Projects

Pierre Cnapelinckx, Fanny Castillo
Proc. ASME. ICONE17, Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 139-147, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75699
https://doi.org/10.1115/ICONE17-75699
View Paper titled, IDEA: An Integrated Set of Tools for Sustainable Nuclear Decommissioning Projects
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Topics: Nuclear decommissioning, Sustainability, Computers, Nuclear power stations, Radioactive wastes, Computer software, Nuclides, Radioisotopes, Algorithms, Computer-aided design
Proceedings Papers

Nuclear Disciplines in Response to Industry and Regulatory Needs Through the European Nuclear Education Network Association

Joseph Safieh, Peter P. De Regge, Ryoko Ksuumi
Proc. ASME. ICONE17, Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 869-884, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75275
https://doi.org/10.1115/ICONE17-75275
View Paper titled, Nuclear Disciplines in Response to Industry and Regulatory Needs Through the European Nuclear Education Network Association
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Topics: Education, Engineering disciplines, Nuclear industry, Nuclear research, Preservation
Proceedings Papers

Advanced Test Reactor: A National Scientific User Facility

Clifford J. Stanley, Frances M. Marshall
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 367-372, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48426
https://doi.org/10.1115/ICONE16-48426
View Paper titled, Advanced Test Reactor: A National Scientific User Facility
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Topics: Chemistry, Coolants, Design, Flow (Dynamics), Fuels, Irradiation (Radiation exposure), Life extension, Materials testing, Neutron flux, Neutrons
Proceedings Papers

Development of Three-Dimensional Virtual Plant Vibration Simulator on Grid Computing Environment ITBL-IS/AEGIS

Yoshio Suzuki, Norihiro Nakajima, Fumimasa Araya, Osamu Hazama, Akemi Nishida, Noriyuki Kushida, Taku Akutsu, Naoya Teshima, Kohei Nakajima, Makoto Kondo, Sachiko Hayashi, Tetsuo Aoyagi
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 149-157, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48478
https://doi.org/10.1115/ICONE16-48478
View Paper titled, Development of Three-Dimensional Virtual Plant Vibration Simulator on Grid Computing Environment ITBL-IS/AEGIS
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Topics: Vibration, Simulation, Nuclear power stations, Computers, Cooling systems, Elastic analysis, Nuclear power, Nuclear research, Reactor vessels, Scientific computing
Proceedings Papers

Implications of Quench Bundle Test Simulations for Plant Applications With MELCOR Code

Jirˇi´ Duspiva
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 585-593, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48168
https://doi.org/10.1115/ICONE16-48168
View Paper titled, Implications of Quench Bundle Test Simulations for Plant Applications With MELCOR Code
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Topics: Fuels, Hydrogen, Simulation, Temperature, Heat, Accidents, Heat losses, Modeling, Cladding systems (Building), Design
Proceedings Papers

RELAP5-3D Analysis of OECD-NEA/NRC BFBT Benchmark

Andriy Kovtonyuk, Alessandro Petruzzi, Carlo Parisi, Francesco D’Auria
Proc. ASME. ICONE16, Volume 3: Thermal Hydraulics; Instrumentation and Controls, 849-858, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48797
https://doi.org/10.1115/ICONE16-48797
View Paper titled, RELAP5-3D Analysis of OECD-NEA/NRC BFBT Benchmark
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Topics: Boiling, Boiling water reactors, Computational fluid dynamics, Errors, Fuels, Heat, Manufacturing, Nuclear engineering, Nuclear research, Porosity
Proceedings Papers

RELAP5/MOD3.2 Investigation of a VVER-1000 MCP Switching on Problem

Pavlin Groudev, Malinka Pavlova
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 287-294, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22443
https://doi.org/10.1115/ICONE10-22443
View Paper titled, RELAP5/MOD3.2 Investigation of a VVER-1000 MCP Switching on Problem
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Topics: Computers, Coolants, Design, Feedback, Flow (Dynamics), Neutrons, Nuclear power, Nuclear power stations, Nuclear reactors, Nuclear research
Proceedings Papers

The REBUS Experimental Programme for Burn-Up Credit

Pierre D’hondt, Klaas van der Meer, Peter Baeten, Daniel Marloye, Benoit Lance, Jacques Basselier
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 227-234, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22022
https://doi.org/10.1115/ICONE10-22022
View Paper titled, The REBUS Experimental Programme for Burn-Up Credit
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Topics: Fuels, Gamma ray spectrometry, Light water reactors, Nuclear fission, Nuclear research, Physics, Pressurized water reactors, Public utilities, Rods, Spent nuclear fuels
Proceedings Papers

The Renewal of HTR Development in Europe

Dominique Hittner
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 815-823, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22423
https://doi.org/10.1115/ICONE10-22423
View Paper titled, The Renewal of HTR Development in Europe
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Topics: Cycles, Fuels, Irradiation (Radiation exposure), Manufacturing, Natural resources, Nuclear research, Particulate matter, Physics, Safety, Sustainable development
Proceedings Papers

A Computer Program Predicting Steady-State Performance of a Nuclear Research Reactor’s Cooling System

Kamel Sidi Ali
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 3, 1-6, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22009
https://doi.org/10.1115/ICONE10-22009
View Paper titled, A Computer Program Predicting Steady-State Performance of a Nuclear Research Reactor’s Cooling System
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Topics: Computer software, Cooling systems, Cooling towers, Nuclear research, Simulation, Steady state, Nuclear reactors, Climate, Cooling, Heat