Volumes | International Conference on Nuclear Engineering | American Society of Mechanical Engineers Digital Collection

Topics: Failure , Instrumentation , Computer software , Control systems , Computers , Feedwater , Flow (Dynamics) , Simulation , Accidents , Corrective actions

An Evaluation of the Hydrogen Flammability and the Hydrogen Concentration in the Reactor Building for Wolsong 2

See Darl Kim, Youngho Jin, Soo Yong Park, Yong Man Song

ICONE 2006; 49-54https://doi.org/10.1115/ICONE14-89126

Abstract

View Articletitled, An Evaluation of the Hydrogen Flammability and the Hydrogen Concentration in the Reactor Building for Wolsong 2

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Topics: Hydrogen

Integration of Passive System Reliability in PSA Studies

Luciano Burgazzi, Michel Marques

ICONE 2006; 55-62https://doi.org/10.1115/ICONE14-89129

Abstract

View Articletitled, Integration of Passive System Reliability in PSA Studies

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Topics: Accidents , Condensed matter , Cooling , Failure , Failure mechanisms , Heat , Heat exchangers , Heat sinks , Light water reactors , Pressure vessels

The DBA Analysis of One Control Rod Withdrawal Out of the HTR-10GT Core

Mingang Lang, Yujie Dong

ICONE 2006; 63-68https://doi.org/10.1115/ICONE14-89172

Abstract

View Articletitled, The DBA Analysis of One Control Rod Withdrawal Out of the HTR-10GT Core

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Topics: Accidents , Boilers , Cycles , Design , Errors , Fuels , Gas turbines , Helium , High temperature , Neutron flux

Development of a Probabilistic Tsunami Hazard Analysis in Japan

Toshiaki Sakai, Tomoyoshi Takeda, Hiroshi Soraoka, Ken Yanagisawa, Tadashi Annaka

ICONE 2006; 69-75https://doi.org/10.1115/ICONE14-89183

Abstract

View Articletitled, Development of a Probabilistic Tsunami Hazard Analysis in Japan

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Topics: Hazard analysis , Tsunamis , Hazards , Design , Systems analysis , Uncertainty , Earthquake resistant design , Evaluation methods , Probability , Risk

Isolation and Damping of Shocks, Vibrations, Impact Load and Seismic Movements at Buildings, Equipment and Pipe Networks by SERB-SITON Method

A. Panait, V. Serban

ICONE 2006; 77-84https://doi.org/10.1115/ICONE14-89189

Abstract

View Articletitled, Isolation and Damping of Shocks, Vibrations, Impact Load and Seismic Movements at Buildings, Equipment and Pipe Networks by SERB-SITON Method

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Topics: Damping , Pipes , Shock (Mechanics) , Stress , Structures , Vibration , Aircraft , Computation , Construction , Construction equipment

Preliminary Analysis of Phebus FPT3 Experiment with the Severe Accident ICARE2 Code

Olivier de Luze, Georges Repetto, Nathalie Seiler, Christina Dominguez

ICONE 2006; 85-94https://doi.org/10.1115/ICONE14-89191

Abstract

View Articletitled, Preliminary Analysis of Phebus FPT3 Experiment with the Severe Accident ICARE2 Code

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Topics: Accidents , Boiling water reactors , Boron , Cladding systems (Building) , Fuels , Modeling , Nuclear fission , Oxidation , Power stations , Pressurized water reactors

Air Ingress Accident in a High Temperature Reactor with Prismatic Fuel

H. Haque, G. Brinkmann

ICONE 2006; 95-103https://doi.org/10.1115/ICONE14-89205

Abstract

View Articletitled, Air Ingress Accident in a High Temperature Reactor with Prismatic Fuel

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Topics: Accidents , Fuels , High temperature , Graphite , Temperature , Air flow , Heat , Safety , Chemical reactions , Corrosion

Experience and Results of Calculations in Case of Vertical Cable Tray Fires

M. Ro¨wekamp, W. Klein-Heßling, O. Riese, H. P. Berg

ICONE 2006; 105-114https://doi.org/10.1115/ICONE14-89218

Abstract

View Articletitled, Experience and Results of Calculations in Case of Vertical Cable Tray Fires

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Topics: Cables , Fire , Failure , Nuclear power stations , Modeling , Reliability , Simulation

Analyses of High Pressure Molten Debris Dispersion for a Typical PWR Plant

Osamu Kawabata, Mitsuhiro Kajimoto

ICONE 2006; 115-123https://doi.org/10.1115/ICONE14-89232

Abstract

View Articletitled, Analyses of High Pressure Molten Debris Dispersion for a Typical PWR Plant

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Topics: Accidents , High pressure (Physics) , Pressurized water reactors

Fire Risk Analysis for Armenian NPP Confinement

Shahen Poghosyan, Albert Malkhasyan, Surik Bznuni, Armen Amirjanyan

ICONE 2006; 125-129https://doi.org/10.1115/ICONE14-89251

Abstract

View Articletitled, Fire Risk Analysis for Armenian NPP Confinement

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Topics: Fire risk , Nuclear power stations , Fire , Damage , Risk , Accidents , Cables , Coolants , Failure , Probabilistic safety assessment

Axial Burnup Profile Influence on Criticality Safety of WWER Spent Fuel

Surik Bznuni, Armen Amirjanyan, Shahen Poghosyan

ICONE 2006; 131-134https://doi.org/10.1115/ICONE14-89252

Abstract

View Articletitled, Axial Burnup Profile Influence on Criticality Safety of WWER Spent Fuel

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Topics: Safety , Spent nuclear fuels , Spent fuel storage , Accidents , Fuel storage , Fuels , Neutrons , Nuclear fission , Nuclear power stations , Radiation (Physics)

Development and Validation of the ECART Code for the Safety Analysis of Nuclear Installations

F. Parozzi, S. Paci

ICONE 2006; 135-144https://doi.org/10.1115/ICONE14-89275

Abstract

View Articletitled, Development and Validation of the ECART Code for the Safety Analysis of Nuclear Installations

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Topics: Safety , Accidents , Accounting , Fire , Aerosols , Chemical processes , Combustion , Cooling , Dust , Fusion reactors

Assessment of ICARE/CATHARE V1 Severe Accident Code

Patrick Chatelard, Joe¨lle Fleurot, Olivier Marchand, Patrick Drai

ICONE 2006; 145-154https://doi.org/10.1115/ICONE14-89307

Abstract

View Articletitled, Assessment of ICARE/CATHARE V1 Severe Accident Code

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Topics: Accidents , Circuits , Hydraulics , Pressurized water reactors , Probabilistic safety assessment , Simulation , Thermal hydraulics

Results of the QUENCH-L2, DISCO-L2, and COMET-L2 Experiments Performed Within the LACOMERA Project at the Forschungszentrum Karlsruhe

Alexei Miassoedov, Hans Alsmeyer, Leonhard Meyer, Martin Steinbrueck, Pavlin Groudev, Ivan Ivanov, Gert Sdouz

ICONE 2006; 155-162https://doi.org/10.1115/ICONE14-89343

Abstract

View Articletitled, Results of the QUENCH-L2, DISCO-L2, and COMET-L2 Experiments Performed Within the LACOMERA Project at the Forschungszentrum Karlsruhe

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Topics: Accidents , Boiling , Cavities , Chemical processes , Concretes , Design , Fluids , Heat , High temperature , Oxidation

Management of Ultimate Risk of Nuclear Power Plants by Source Terms: Lessons Learned from the Chernobyl Accident

Genn Saji

ICONE 2006; 163-172https://doi.org/10.1115/ICONE14-89351

Abstract

View Articletitled, Management of Ultimate Risk of Nuclear Power Plants by Source Terms: Lessons Learned from the Chernobyl Accident

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Topics: Chernobyl Nuclear Accident, Chornobyl, Ukraine, 1986 , Nuclear power stations , Risk , Accidents , Safety , Nuclear fission , Probability , Accident management , Containment , Contamination

ATWS Frequency Evaluation of FBR MONJU

Masutake Sotsu, Kenichi Kurisaka

ICONE 2006; 173-179https://doi.org/10.1115/ICONE14-89377

Abstract

View Articletitled, ATWS Frequency Evaluation of FBR MONJU

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Topics: Breeder reactors , Engineering prototypes , Scram , Sodium , Transients (Dynamics)

Sustained Heating Experiments for the Investigation of the Boiling Heat Removal at the Upper Surface of Metallic Layer

Kyoung-Ho Kang, Rae-Joon Park, Sang-Baik Kim, Hee-Dong Kim

ICONE 2006; 181-186https://doi.org/10.1115/ICONE14-89396

Abstract

View Articletitled, Sustained Heating Experiments for the Investigation of the Boiling Heat Removal at the Upper Surface of Metallic Layer

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Topics: Boiling , Coolants , Heat , Heating , Vessels , Temperature , Heat transfer , Shapes

Assessment of Thermal and Hydrodynamic Fragmentation in Molten Fuel Coolant Interaction With Simulant System

K. S. Narayanan, S. K. Das, A. Jasmin Sudha, E. V. H. M. Rao, G. Lydia, S. S. Murthy, M. Kumaresan, J. Harvey, N. Kasinathan, M. Rajan

ICONE 2006; 187-195https://doi.org/10.1115/ICONE14-89404

Abstract

View Articletitled, Assessment of Thermal and Hydrodynamic Fragmentation in Molten Fuel Coolant Interaction With Simulant System

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Topics: Coolants , Fuels , Temperature , Boiling , Metals , Water , Alloys , Breeder reactors , Density , Film boiling

Numerical and Experimental Model Studies on Thermal Hydraulic Behavior of FBR Internal Core Catcher Assembly

Sanjay Kumar Das, Anil Kumar Sharma, A. Jasmin Sudha, G. Punitha, G. Lydia, P. A. Somayajulu, S. S. Murthy, B. Malarvizhi, V. Gopalakrishnan, J. Harvey, N. Kasinathan, M. Rajan

ICONE 2006; 197-203https://doi.org/10.1115/ICONE14-89406

Abstract

View Articletitled, Numerical and Experimental Model Studies on Thermal Hydraulic Behavior of FBR Internal Core Catcher Assembly

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Topics: Manufacturing , Geometry , Heat , Temperature , Vessels , Breeder reactors , Convection , Creep , Design , Flow (Dynamics)

First Results of the Phebus FPT3 Test

Philippe March, Bruno Biard, Christelle Manenc, Fre´de´ric Payot, Claude Gaillard, Je´roˆme Guillot, Michel Janot, Bruno Morassano, Michel Pepino, Be´atrice Simondi-Teisseire, Yves Garnier, Gilles Gre´goire, Ve´ronique Masson, Laurent Pantera

ICONE 2006; 205-214https://doi.org/10.1115/ICONE14-89432

Abstract

View Articletitled, First Results of the Phebus FPT3 Test

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Topics: Aerosols , Boron , Chemistry , Circuits , Containment , Containment vessels , Failure , Fuels , Instrumentation , Irradiation (Radiation exposure)

Recent Progress in Risk Consideration and Issues on Developing Risk Informed Regulations in Japan

Akihide Hidaka

ICONE 2006; 215-221https://doi.org/10.1115/ICONE14-89449

Abstract

View Articletitled, Recent Progress in Risk Consideration and Issues on Developing Risk Informed Regulations in Japan

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Topics: Risk , Risk-based regulations , Safety

Investigation of the Fission Product Release From Molten Pools Under Oxidizing Conditions With the Code RELOS

Ingo D. Kleinhietpaß, Hermann Unger, Hermann-Josef Wagner, Marco K. Koch

ICONE 2006; 223-232https://doi.org/10.1115/ICONE14-89456

Abstract

View Articletitled, Investigation of the Fission Product Release From Molten Pools Under Oxidizing Conditions With the Code RELOS

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Topics: Nuclear fission , Oxygen , Radioisotopes , Accidents , Energy / power systems , Modeling , Nuclear power stations , Oxidation , Aerosols , Density

The Development of Severe Accident Codes at IRSN and Their Application to Support the Safety Assessment of EPR

Cataldo Caroli, Alexandre Bleyer, Ahmed Bentaib, Patrick Chatelard, Michel Cranga, Jean-Pierre Van Dorsselaere

ICONE 2006; 233-242https://doi.org/10.1115/ICONE14-89461

Abstract

View Articletitled, The Development of Severe Accident Codes at IRSN and Their Application to Support the Safety Assessment of EPR

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Topics: Accidents , Safety , Pressurized water reactors , Hydrogen , Combustion , Computational fluid dynamics , Containment , Flow (Dynamics) , Heat transfer , Steam

The Human Bathtub: Safety and Risk Predictions Including the Dynamic Probability of Operator Errors

Romney B. Duffey, John W. Saull

ICONE 2006; 243-248https://doi.org/10.1115/ICONE14-89476

Abstract

View Articletitled, The Human Bathtub: Safety and Risk Predictions Including the Dynamic Probability of Operator Errors

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Topics: Errors , Probability , Risk , Safety , Failure , Performance , Accidents , Fittings , Reliability , Transients (Dynamics)

Numerical and Experimental Studies on Impact Loaded Concrete Structures

Arja Saarenheimo, Ilkka Hakola, Tuomo Ka¨rna¨, Juhani Hyva¨rinen, Markku Tuomala

ICONE 2006; 249-261https://doi.org/10.1115/ICONE14-89477

Abstract

View Articletitled, Numerical and Experimental Studies on Impact Loaded Concrete Structures

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Topics: Aircraft , Analytical methods , Calibration , Computer simulation , Concretes , Damage , Deformation , Finite element analysis , Flammable liquids , Fuels

Emergency Operating Procedures (EOPs) for the AP1000 Simulator

Yuichi Hayashi, Gianfranco Saiu, Richard F. Wright

ICONE 2006; 263-272https://doi.org/10.1115/ICONE14-89508

Abstract

View Articletitled, Emergency Operating Procedures (EOPs) for the AP1000 Simulator

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Topics: Emergencies , Pressurized water reactors , Safety , Accidents , Design , Nuclear reactor coolants , Boilers , Cooling , Emergency response , Leakage

Expedition to the 30-km Chernobyl Exclusion Zone and the Utilization of Its Experience in Education and Communication

Attila Aszo´di, Bogda´n Yamaji, Judit Silye, Tama´s Pa´zma´ndi

ICONE 2006; 273-278https://doi.org/10.1115/ICONE14-89510

Abstract

View Articletitled, Expedition to the 30-km Chernobyl Exclusion Zone and the Utilization of Its Experience in Education and Communication

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Topics: Chernobyl Nuclear Accident, Chornobyl, Ukraine, 1986 , Education

Estimation of the Alpha Factor Parameters for the Emergency Diesel Generators of Ulchin Unit 3

Dae Il Kang, Sang Hoon Han

ICONE 2006; 279-286https://doi.org/10.1115/ICONE14-89559

Abstract

View Articletitled, Estimation of the Alpha Factor Parameters for the Emergency Diesel Generators of Ulchin Unit 3

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Topics: Diesel generators , Emergencies , Failure

Analysis of Sodium Fire in the Containment Building of Prototype Fast Breeder Reactor Under the Scenario of Core Disruptive Accident

P. M. Rao, N. Kasinathan, S. E. Kannan

ICONE 2006; 287-291https://doi.org/10.1115/ICONE14-89566

Abstract

View Articletitled, Analysis of Sodium Fire in the Containment Building of Prototype Fast Breeder Reactor Under the Scenario of Core Disruptive Accident

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Topics: Accidents , Breeder reactors , Containment buildings , Engineering prototypes , Fire , Sodium , Pressure , Liquid pool fires , Sprays , Combustion

Insights from a Full Scope Level 2 PSA Model for a PWR Plant With Spherical Shell Containment

Jens U. Klu¨gel, Michael Xing, Shobha B. Rao, Ken Deremer

ICONE 2006; 293-300https://doi.org/10.1115/ICONE14-89589

Abstract

View Articletitled, Insights from a Full Scope Level 2 PSA Model for a PWR Plant With Spherical Shell Containment

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Topics: Containment , Pressurized water reactors , Spherical shells , Accidents , Accident management , Failure , Hydrogen , Thermal hydraulics

Experimental Evaluation of Pool Fire Suppression Performance of Sodium Leak Collection Tray in Open Air

F. C. Parida, P. M. Rao, S. S. Ramesh, B. Malarvizhi, V. Gopalakrishnan, E. H. V. M. Rao, N. Kasinathan, S. E. Kannan

ICONE 2006; 301-307https://doi.org/10.1115/ICONE14-89592

Abstract

View Articletitled, Experimental Evaluation of Pool Fire Suppression Performance of Sodium Leak Collection Tray in Open Air

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Topics: Leakage , Liquid pool fires , Sodium , Pipes , Fire , Flames , Smoke , Vents , Boats , Breeder reactors

Sodium Exposure Tests on Limestone Concrete Used as Sacrificial Protection Layer in FBR

F. C. Parida, S. K. Das, A. K. Sharma, P. M. Rao, S. S. Ramesh, P. A. Somayajulu, B. Malarvizhi, N. Kasinathan

ICONE 2006; 309-318https://doi.org/10.1115/ICONE14-89593

Abstract

View Articletitled, Sodium Exposure Tests on Limestone Concrete Used as Sacrificial Protection Layer in FBR

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Topics: Concretes , Sodium , Cavities , Concrete blocks , Hammers , Water , Compressive strength , Damage , Cements (Adhesives) , Combustion

Spatially Informed Plant PRA Models for Security Assessment

Timothy A. Wheeler, Willard Thomas, Eric Thornsbury

ICONE 2006; 319-325https://doi.org/10.1115/ICONE14-89598

Abstract

View Articletitled, Spatially Informed Plant PRA Models for Security Assessment

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Topics: Damage , Failure , Fire , Floods , Probabilistic risk assessment , Risk , Security , Shock (Mechanics) , Vibration

On the Development of the ISAAC Graphic Model

K. R. Kim, S. D. Kim, Y. M. Song

ICONE 2006; 327-332https://doi.org/10.1115/ICONE14-89599

Abstract

View Articletitled, On the Development of the ISAAC Graphic Model

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Topics: Accidents , Containment , Fuels , Heavy water reactors , Nuclear fission , Pumps , Valves

A Comprehensive Evaluation Method of Human-Machine Interface for Indicator-Meters Based on Gray Theory

Sheng-Yuan Yan, Zhi-Jian Zhang, Min-Jun Peng, Ming Yang

ICONE 2006; 333-336https://doi.org/10.1115/ICONE14-89602

Abstract

View Articletitled, A Comprehensive Evaluation Method of Human-Machine Interface for Indicator-Meters Based on Gray Theory

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Topics: Evaluation methods , Machinery , Design , Human-machine systems , Nuclear power stations

The TACIS Nuclear Programme: Assistance in Upgrading Russian Nuclear Power Stations —An Overview of the Individual Projects in the Internet

Michel Bie`th, Hubert Schoels

ICONE 2006; 337-339https://doi.org/10.1115/ICONE14-89635

Abstract

View Articletitled, The TACIS Nuclear Programme: Assistance in Upgrading Russian Nuclear Power Stations —An Overview of the Individual Projects in the Internet

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Topics: Internet , Nuclear power stations , Safety , Databases , Design , Embrittlement , Industrial wastes , Reactor vessels

Mitigation of Anticipated Transients Without Scram in the ESBWR

Wayne Marquino, Bharat Shiralkar, Shivakumar Sitaraman

ICONE 2006; 341-353https://doi.org/10.1115/ICONE14-89661

Abstract

View Articletitled, Mitigation of Anticipated Transients Without Scram in the ESBWR

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Topics: Acceptance criteria , Boron , Computers , Condensers (steam plant) , Control systems , Feedwater , Flow (Dynamics) , High pressure (Physics) , Jets , Motion control

A Novel, Safe, and Environmentally Friendly Technology for Water Production Through Recovery of Rejected Thermal Energy From Nuclear Power Plants

Yehia F. Khalil, Menachem Elimelech

ICONE 2006; 355-364https://doi.org/10.1115/ICONE14-89663

Abstract

View Articletitled, A Novel, Safe, and Environmentally Friendly Technology for Water Production Through Recovery of Rejected Thermal Energy From Nuclear Power Plants

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Topics: Nuclear power stations , Thermal energy , Water , Design , Heat , Seawater , Water treatment , Steam , Temperature programmed desorption , Amperes

An Integration of the Restructured MELCOR for the MIDAS Computer Code

Sunhee Park, Dong Ha Kim, Ko Ryu Kim, Song-Won Chol

ICONE 2006; 365-370https://doi.org/10.1115/ICONE14-89712

Abstract

View Articletitled, An Integration of the Restructured MELCOR for the MIDAS Computer Code

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Topics: Accidents , Computers , Maintainability , Nuclear power stations , Simulation , Steady state

Inherent Boron Dilution Safety Issue in the French Pressurized Water Reactor: CFD Approach

Estelle Graffard, Fre´de´ric Goux

ICONE 2006; 371-378https://doi.org/10.1115/ICONE14-89715

Abstract

View Articletitled, Inherent Boron Dilution Safety Issue in the French Pressurized Water Reactor: CFD Approach

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Topics: Boron , Computational fluid dynamics , Pressurized water reactors , Safety , Boilers , Boiling , Risk , Slug flows , Water

Application of MELCOR Code to a French PWR 900 MWe Severe Accident Sequence and Evaluation of Models Performance Focusing on In-Vessel Thermal Hydraulic Results

Felice De Rosa

ICONE 2006; 379-387https://doi.org/10.1115/ICONE14-89731

Abstract

View Articletitled, Application of MELCOR Code to a French PWR 900 MWe Severe Accident Sequence and Evaluation of Models Performance Focusing on In-Vessel Thermal Hydraulic Results

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Topics: Accidents , Pressurized water reactors , Vessels , Feedwater , Scram , Boilers , Coolants , Delays , Nuclear fission , Pressure

The Application of Time-Related Event Tree During the HTR-PM Design Phase

Ping Min, Jiejuan Tong, Xuhong He

ICONE 2006; 389-392https://doi.org/10.1115/ICONE14-89785

Abstract

View Articletitled, The Application of Time-Related Event Tree During the HTR-PM Design Phase

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Topics: Design , Probabilistic safety assessment

Safety Design and Mock-Up Tests on the Combustion of Hydrogen-Air Mixture in the Vertical CNS Channel of the CARR-CNS

Qingfeng Yu, Quanke Feng

ICONE 2006; 393-398https://doi.org/10.1115/ICONE14-89815

Abstract

View Articletitled, Safety Design and Mock-Up Tests on the Combustion of Hydrogen-Air Mixture in the Vertical CNS Channel of the CARR-CNS

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Topics: Combustion , Design , Hydrogen , Safety , Helium , Condensers (steam plant) , Pressure , Accidents , Cooling , Aluminum alloys

Recent IAEA Activities in Support of Safety Assessment Capabilities

S. Michael Modro, Mamdouh El-Shanawany, Sukho Lee

ICONE 2006; 399-403https://doi.org/10.1115/ICONE14-89828

Abstract

View Articletitled, Recent IAEA Activities in Support of Safety Assessment Capabilities

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Topics: Safety , Computational fluid dynamics , Nuclear power , Collaboration , Maintenance , Uncertainty

Evaluation and Numerical Simulation of Tsunami for Coastal Nuclear Power Plants of India

Pavan K. Sharma, B. Ghosh, R. K. Singh, A. K. Ghosh, H. S. Kushwaha

ICONE 2006; 405-416https://doi.org/10.1115/ICONE14-89849

Abstract

View Articletitled, Evaluation and Numerical Simulation of Tsunami for Coastal Nuclear Power Plants of India

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Topics: Computer simulation , Nuclear power stations , Shorelines , Tsunamis , Earthquakes , Underwater vehicles , Design , Landslides , Waves , Displacement

Spent Nuclear Fuel Transportation Risk Assessment Methodology for Homeland Security

Grant A. Teagarden, Kenneth T. Canavan, Robert E. Nickell

ICONE 2006; 417-424https://doi.org/10.1115/ICONE14-89855

Abstract

View Articletitled, Spent Nuclear Fuel Transportation Risk Assessment Methodology for Homeland Security

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Topics: Homeland security , Risk assessment , Spent nuclear fuels , Transportation systems , Risk , Critical Asset Protection , Decision making , Risk analysis , Risk management , Risk-based decision making

Development, Application, and Implementation of RAMCAP to Characterize Nuclear Power Plant Risk From Terrorism

John P. Gaertner, Grant A. Teagarden

ICONE 2006; 425-431https://doi.org/10.1115/ICONE14-89858

Abstract

View Articletitled, Development, Application, and Implementation of RAMCAP to Characterize Nuclear Power Plant Risk From Terrorism

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Topics: Critical Asset Protection , Nuclear power stations , Risk , Design , Homeland security , Security , Spent nuclear fuels , Accident management , Accidents , Computer software

International Training Program in Support of Safety Analysis: 3D S.UN.COP—Scaling, Uncertainty and 3D Thermal-Hydraulics/Neutron-Kinetics Coupled Codes Seminars

Alessandro Petruzzi, Francesco D’Auria, Tomislav Bajs, Francesc Reventos

ICONE 2006; 433-442https://doi.org/10.1115/ICONE14-89902

Abstract

View Articletitled, International Training Program in Support of Safety Analysis: 3D S.UN.COP—Scaling, Uncertainty and 3D Thermal-Hydraulics/Neutron-Kinetics Coupled Codes Seminars

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Topics: Certainty , Computers , Education , Engineering teachers , Industrial engineering , Neutrons , Nuclear fuels , Nuclear power stations , Public utilities , Safety

Low Level Waste Management, Decontamination and Decommissioning

Study for Nuclide Transfer Ratio of Particles Generated by Thermal Cutting

Yukihiro Iguchi, Tsutomu Baba, Hiroto Kawakami

ICONE 2006; 443-449https://doi.org/10.1115/ICONE14-89139

Abstract

View Articletitled, Study for Nuclide Transfer Ratio of Particles Generated by Thermal Cutting

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Topics: Cutting , Nuclides , Particulate matter , Pressure , Aerosols , Metals , Vapor pressure , Zirconium , Alloys , Dust

Metal Surface Decontamination by the PFC Solution

Hui-Jun Won, Gye-Nam Kim, Wang-Kyu Choi, Chong-Hun Jung, Won-Zin Oh

ICONE 2006; 451-456https://doi.org/10.1115/ICONE14-89210

Abstract

View Articletitled, Metal Surface Decontamination by the PFC Solution

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Topics: Decontamination , Metal surfaces , Sprays

Methodology for Determining the Radiological Status of a Process: Application to Decommissioning of a Fuel Reprocessing Facility

Ph. Girone`s, C. Ducros, C. Legoaller, F. Lamadie, J.-M. Fulconis, V. Thiebaut, C. Mahe´

ICONE 2006; 457-464https://doi.org/10.1115/ICONE14-89362

Abstract

View Articletitled, Methodology for Determining the Radiological Status of a Process: Application to Decommissioning of a Fuel Reprocessing Facility

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Topics: Fuels , Nuclear decommissioning , Chemical processes , Contamination , Gamma ray spectrometry , Imaging , Instrumentation , Radioactivity , Safety , Sensors

Applicability Examination and Evaluation of Reactor Dismantlement Technology in the FUGEN: Examination of Double Tubes Cutting by Abrasive Water Jet

Yasuyuki Nakamura, Kouichi Kikuchi, Yoshitugu Morishita, Tatsuo Usui, Daisuke Ogane

ICONE 2006; 465-473https://doi.org/10.1115/ICONE14-89380

Abstract

View Articletitled, Applicability Examination and Evaluation of Reactor Dismantlement Technology in the FUGEN: Examination of Double Tubes Cutting by Abrasive Water Jet

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Topics: Cutting , Water , Nuclear decommissioning , Pressure , Zirconium alloys

Characteristics of Melting for the Radioactive Aluminum Wastes From the Decommissioned Nuclear Facilities

Pyung Seob Song, Byung Youn Min, Wang Kyu Choi, Chong Hun Jung, Won Zin Oh

ICONE 2006; 475-480https://doi.org/10.1115/ICONE14-89401

Abstract

View Articletitled, Characteristics of Melting for the Radioactive Aluminum Wastes From the Decommissioned Nuclear Facilities

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Topics: Aluminum , Melting , Nuclear power stations , Nuclides , Slags , Flux (Metallurgy) , Cobalt , Furnaces , Strontium , Dust

Development of the Analysis Method for the Radioactivity Concentration Estimation of Soils for a Regulatory Clearance

Dae-Seok Hong, Jong-Sik Shon, Tae-Kuk Kim, Han-Seok Cho

ICONE 2006; 481-484https://doi.org/10.1115/ICONE14-89443

Abstract

View Articletitled, Development of the Analysis Method for the Radioactivity Concentration Estimation of Soils for a Regulatory Clearance

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Topics: Clearances (Engineering) , Radioactivity , Soil , Concretes , Decontamination , Errors , Nuclear decommissioning , Nuclear power , Nuclides , Particulate matter

Contaminated Metal Components in Dismantling by Hot Cutting Processes

Franco G. Cesari, Massimo Rogante, Angelo Giostri, Gianmario Conforti

ICONE 2006; 485-494https://doi.org/10.1115/ICONE14-89451

Abstract

View Articletitled, Contaminated Metal Components in Dismantling by Hot Cutting Processes

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Topics: Aerosols , Cutting , Metalwork , Plasmas (Ionized gases)

Comprehensive Cost Estimation Method for Decommissioning

Kenji Kudo, Shinji Kawatsuma, Hiroshi Rindo, Kozo Watabe, Hiroyuki Tomii, Kunio Shiraishi, Naoto Yagi, Tadashi Fukushima, Tomohisa Zaitsu

ICONE 2006; 495-503https://doi.org/10.1115/ICONE14-89586

Abstract

View Articletitled, Comprehensive Cost Estimation Method for Decommissioning

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Topics: Nuclear decommissioning , Nuclear power , Cycles , Industrial research , Nuclear fuel cycle , Engineering prototypes , Fuels , Nuclear power stations , Safety , Uranium

The Fate of Hazardous Materials in the Biosphere

Gary M. Sandquist

ICONE 2006; 505-509https://doi.org/10.1115/ICONE14-89632

Abstract

View Articletitled, The Fate of Hazardous Materials in the Biosphere

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Topics: Hazardous substances , Nuclear power , Oceans , Radioactive substances , Radioactive wastes , Containment , Energy resources , Hazardous wastes , Nuclear fuel cycle , Radioactive waste repositories