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Proceedings Papers

Heat Sink Issue: A Specific Problematic Issue for NPP Implementation in Warm Countries With Extreme Climatic Conditions

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Andrei Rodionov, Jean-Marie Mattei
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 275-279, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54126
https://doi.org/10.1115/ICONE20-POWER2012-54126
View Paper titled, Heat Sink Issue: A Specific Problematic Issue for NPP Implementation in Warm Countries With Extreme Climatic Conditions
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Topics: Heat sinks, Nuclear power stations, Safety
Proceedings Papers

Mitigation of PWR In-Containment Iodine Source Term Under LOCA

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Khurram Mehboob, Xinrong Cao, Majid Ali, Rehan Khan
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 351-359, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54258
https://doi.org/10.1115/ICONE20-POWER2012-54258
View Paper titled, Mitigation of PWR In-Containment Iodine Source Term Under LOCA
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Topics: Containment, Pressurized water reactors
Proceedings Papers

Estimation of Thyroid Doses From Land Contamination Maps for the Fukushima Disaster

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Genn Saji
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 491-505, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55048
https://doi.org/10.1115/ICONE20-POWER2012-55048
View Paper titled, Estimation of Thyroid Doses From Land Contamination Maps for the Fukushima Disaster
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Topics: Contamination, Disasters, Fukushima nuclear disaster, Japan, 2011, Plumes (Fluid dynamics)
Proceedings Papers

Kinetic Study of Sodium-Water Reaction Phenomena by Differential Thermal Analysis

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Shin Kikuchi, Hiroshi Seino, Akikazu Kurihara, Hiroyuki Ohshima
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 281-289, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54134
https://doi.org/10.1115/ICONE20-POWER2012-54134
View Paper titled, Kinetic Study of Sodium-Water Reaction Phenomena by Differential Thermal Analysis
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Topics: Sodium, Thermal analysis, Water, Sodium fast reactors, Temperature, Heat transfer, Safety, Boilers, Chemical kinetics, Chemical reactions
Proceedings Papers

Power Coefficient of Reactivity Determination for HTPBR and its Application for Reactivity Initiated Transients

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Kushal DinkarBadgujar, Om Pal Singh, Suneet Singh, Shripad T. Rewankar
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 507-517, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55058
https://doi.org/10.1115/ICONE20-POWER2012-55058
View Paper titled, Power Coefficient of Reactivity Determination for HTPBR and its Application for Reactivity Initiated Transients
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Topics: Transients (Dynamics), Feedback, Heat, Safety, Temperature, Scram, Simulation, Steady state, Coolants, Design
Proceedings Papers

Coupled Code SOCRAT-BN Development for Safety Analysis of Sodium-Cooled Fast Reactors

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Eduard V. Usov, Ivan G. Kudashov, Sergey A. Zhigach, Anton A. Butov, Nikolay A. Pribaturin, Sergey I. Lezhnin, Ruslan V. Chalyy, Sergey E. Yakush, Uliya Vinogradova
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 361-366, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54316
https://doi.org/10.1115/ICONE20-POWER2012-54316
View Paper titled, Coupled Code SOCRAT-BN Development for Safety Analysis of Sodium-Cooled Fast Reactors
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Topics: Safety, Sodium fast reactors, Fluids, Geometry, Accidents, Computer software, Constitutive equations, Damage, Design, Flow (Dynamics)
Proceedings Papers

Semi-Analytical Study of Aerosol Washout by Rain

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Pascal Lemaitre, Amandine Nuboer, Arnaud Querel, Guillaume Depuydt, Emmanuel Porcheron
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 367-375, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54442
https://doi.org/10.1115/ICONE20-POWER2012-54442
View Paper titled, Semi-Analytical Study of Aerosol Washout by Rain
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Topics: Aerosols, Particulate matter, Accidents, Generators, Arches, Chernobyl Nuclear Accident, Chornobyl, Ukraine, 1986, Disks, Fukushima nuclear disaster, Japan, 2011, Instrumentation, Light scattering
Proceedings Papers

Development of a Safety Analysis Code SCTRAN for SCWR

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Junli Gou, Pan Wu, Jianqiang Shan, Bo Zhang, Jue Yang
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 431-438, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54847
https://doi.org/10.1115/ICONE20-POWER2012-54847
View Paper titled, Development of a Safety Analysis Code SCTRAN for SCWR
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Topics: Safety, Supercritical water reactors, Computers, Design, Industrial research, Light water reactors, Transients (Dynamics), Water
Proceedings Papers

Development of New Simulation Software System to Evaluate Radiation Dose Rates in a Wide Radioactively Contaminated Area

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Tomoharu Hashimoto, Masahiro Kondo, Ryuichi Tayama, Hideho Gamo
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 519-523, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55069
https://doi.org/10.1115/ICONE20-POWER2012-55069
View Paper titled, Development of New Simulation Software System to Evaluate Radiation Dose Rates in a Wide Radioactively Contaminated Area
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Topics: Computer software, Decontamination, Radiation (Physics), Simulation, Radiation sources, Soil, Concretes, Gamma rays, Governments, Iron
Proceedings Papers

Modeling of Dryout in Core Debris Beds of Conical and Cylindrical Geometries

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Eveliina Takasuo, Ville Hovi, Mikko Ilvonen, Stefan Holmström
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 291-300, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54159
https://doi.org/10.1115/ICONE20-POWER2012-54159
View Paper titled, Modeling of Dryout in Core Debris Beds of Conical and Cylindrical Geometries
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Topics: Modeling, Accidents, Particulate matter, Simulation, Flow (Dynamics), Geometry, Nuclear power stations, Power density, Simulation results, Vessels
Proceedings Papers

Assessing Sensitivity of Observations in Source Term Estimation for Nuclear Accidents

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Yuanwei Ma, Dezhong Wang, Wenji Tan, Zhilong Ji, Kuo Zhang
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 377-382, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54491
https://doi.org/10.1115/ICONE20-POWER2012-54491
View Paper titled, Assessing Sensitivity of Observations in Source Term Estimation for Nuclear Accidents
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Topics: Accidents, Kalman filters, Errors, Sensors, Fukushima nuclear disaster, Japan, 2011, Dynamic models, Plumes (Fluid dynamics), Radioisotopes, Stability, Statistics
Proceedings Papers

Influence of Boron Carbide on Core Degradation During Severe Accidents in LWRs

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Martin Steinbrück
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 235-242, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54026
https://doi.org/10.1115/ICONE20-POWER2012-54026
View Paper titled, Influence of Boron Carbide on Core Degradation During Severe Accidents in LWRs
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Topics: Accidents, Boron, Light water reactors, Hydrogen, Fukushima nuclear disaster, Japan, 2011, Temperature, Carbon dioxide, Cladding systems (Building), Failure, Fuels
Proceedings Papers

Simulation of the TMI-2 Accident With ATHLET-CD and Analysis of the Late-Phase Modeling

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Mathias Hoffmann, Marco K. Koch
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 439-447, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54871
https://doi.org/10.1115/ICONE20-POWER2012-54871
View Paper titled, Simulation of the TMI-2 Accident With ATHLET-CD and Analysis of the Late-Phase Modeling
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Topics: Accidents, Modeling, Simulation, Thermal hydraulics
Proceedings Papers

Highlights of Preliminary Level 1 PSA Results for a Research Reactor

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Yoon-Hwan Lee, Won-Dea Jung, Su-Ki Park, Jin-Hong Lee
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 525-529, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55171
https://doi.org/10.1115/ICONE20-POWER2012-55171
View Paper titled, Highlights of Preliminary Level 1 PSA Results for a Research Reactor
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Topics: Accidents, Conceptual design, Damage, Design, Electricity (Physics), Errors, Failure, Probabilistic safety assessment, Pumps, Reliability
Proceedings Papers

Comparison of Containment Response for a CANDU 6 Station Blackout Sequence Using MAAP4-CANDU (v4.0.7) and GOTHIC (v7.2b)

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S. M. Petoukhov, Tuan H. Nguyen, B. Awadh, P. M. Mathew
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 301-312, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54167
https://doi.org/10.1115/ICONE20-POWER2012-54167
View Paper titled, Comparison of Containment Response for a CANDU 6 Station Blackout Sequence Using MAAP4-CANDU (v4.0.7) and GOTHIC (v7.2b)
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Topics: Containment, Simulation results, Accidents, Damage, Energy resources, Lumped parameter models, Pressure, Sprays, Temperature
Proceedings Papers

Corium and Debris Coolability Studies Performed in the Severe Accident Research Network of Excellence (SARNET2)

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Alexei Miassoedov, Th. Walter Tromm, Jonathan Birchley, Florian Fichot, Weimin Ma, Georg Pohlner, Peter Matejovic
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 383-392, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54568
https://doi.org/10.1115/ICONE20-POWER2012-54568
View Paper titled, Corium and Debris Coolability Studies Performed in the Severe Accident Research Network of Excellence (SARNET2)
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Topics: Accidents, Cooling, Vessels, Modeling, Accident management, Cavities, Computers, Databases, Design, Geometry
Proceedings Papers

Study on the Core Cooling Scheme After Accident Shutdown of the Pebble-Bed Modular High Temperature Gas-Cooled Reactor

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Yanhua Zheng, Lei Shi, Fubing Chen
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 243-248, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54041
https://doi.org/10.1115/ICONE20-POWER2012-54041
View Paper titled, Study on the Core Cooling Scheme After Accident Shutdown of the Pebble-Bed Modular High Temperature Gas-Cooled Reactor
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Topics: Accidents, Cooling, Fuels, Natural convection, Scram, Temperature, Very high temperature reactors
Proceedings Papers

Underground Siting of Nuclear Power Plants: Insights From Fukushima

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Jay F. Kunze, James M. Mahar, Kellen M. Giraud, C. W. Myers
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 449-455, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54900
https://doi.org/10.1115/ICONE20-POWER2012-54900
View Paper titled, Underground Siting of Nuclear Power Plants: Insights From Fukushima
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Topics: Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Earthquakes, Fuels, Light water reactors, Natural disasters, Production facilities, Small modular reactors, Storage, Tsunamis
Proceedings Papers

TRACE/PARCS Analysis of Full Isolation Startup Test for Lungmen ABWR

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Ai-Ling Ho, Jong-Rong Wang, Hao-Tzu Lin, Chunkuan Shih
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 313-320, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54174
https://doi.org/10.1115/ICONE20-POWER2012-54174
View Paper titled, TRACE/PARCS Analysis of Full Isolation Startup Test for Lungmen ABWR
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Topics: Delays, Domes (Structural elements), Nuclear power stations, Pressure, Pumps, Relief valves, Scram, Signals, Valves, Water
Proceedings Papers

Preliminary Analysis of In-Vessel Corium Confinement and Cooling in a Large Sodium Fast Reactor

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Franco Polidoro, Flavio Parozzi
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 249-257, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54073
https://doi.org/10.1115/ICONE20-POWER2012-54073
View Paper titled, Preliminary Analysis of In-Vessel Corium Confinement and Cooling in a Large Sodium Fast Reactor
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Topics: Cooling, Sodium fast reactors, Vessels, Accidents, Coolants, Light water reactors, Liquid metal fast breeder reactors, Computer simulation, Computers, Containment