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

Topics: Nuclear power , Nuclear power stations , Nuclear industry , Construction , Design , Economics , Electric power generation , Electricity (Physics) , Stress , Engines

Probabilistic Safety Assessment Technology for Commercial Nuclear Power Plant Security Evaluation

James K. Liming, David H. Johnson, Andrew A. Dykes

ICONE 2004; 19-24https://doi.org/10.1115/ICONE12-49027

Abstract

View Articletitled, Probabilistic Safety Assessment Technology for Commercial Nuclear Power Plant Security Evaluation

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Topics: Nuclear power stations , Probabilistic safety assessment , Security , Risk assessment , Safety , Decision making , Nuclear industry , Power stations , Risk , Risk management

The Adventitious-Pin-Failure Study Under a Slow Power Ramp

Yoshitaka Fukano, Jean Charpenel

ICONE 2004; 25-32https://doi.org/10.1115/ICONE12-49048

Abstract

View Articletitled, The Adventitious-Pin-Failure Study Under a Slow Power Ramp

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Topics: Failure , Fuels , Melting , Cladding systems (Building) , Density , Coolants , Accidents , Breeder reactors , Cavities , Collaboration

Development of Passive Cooling System Models for the Assessment of the Long Term Cooling Capability in the Liquid Metal Reactor

W. P. Chang, K. S. Ha, H. Y. Jeong, S. Heo, Y. B. Lee

ICONE 2004; 33-40https://doi.org/10.1115/ICONE12-49063

Abstract

View Articletitled, Development of Passive Cooling System Models for the Assessment of the Long Term Cooling Capability in the Liquid Metal Reactor

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Topics: Cooling , Cooling systems , Liquid metals

Analyses of Ex-Vessel Steam Explosion and Its Structural Dynamic Response for a Typical PWR Plant

Osamu Kawabata

ICONE 2004; 41-49https://doi.org/10.1115/ICONE12-49105

Abstract

View Articletitled, Analyses of Ex-Vessel Steam Explosion and Its Structural Dynamic Response for a Typical PWR Plant

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Topics: Explosions , Pressurized water reactors , Steam , Structural dynamics , Vessels

Flow Analyses Using RELAP/MOD3.3 Code for the Simulant Melt Experiments (LAVA-ERVC) Under the External Reactor Vessel Cooling

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

ICONE 2004; 51-56https://doi.org/10.1115/ICONE12-49190

Abstract

View Articletitled, Flow Analyses Using RELAP/MOD3.3 Code for the Simulant Melt Experiments (LAVA-ERVC) Under the External Reactor Vessel Cooling

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Topics: Cooling , Flow (Dynamics) , Reactor vessels , Steam

Experiments on Performance of the Multi-Layered In-Vessel Core Catcher

Kyoung-Ho Kang, Rae-Joon Park, Sang-Baik Kim, K. Y. Suh, F. B. Cheung, J. L. Rempe

ICONE 2004; 57-63https://doi.org/10.1115/ICONE12-49193

Abstract

View Articletitled, Experiments on Performance of the Multi-Layered In-Vessel Core Catcher

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Topics: Coating processes , Coatings , Inspection , Vessels

Practical Procedures for Estimation of Plant Specific Common Cause Failure Quantification Parameters for Plants With Accumulated Operating Experiences

Young G. Jo

ICONE 2004; 65-75https://doi.org/10.1115/ICONE12-49215

Abstract

View Articletitled, Practical Procedures for Estimation of Plant Specific Common Cause Failure Quantification Parameters for Plants With Accumulated Operating Experiences

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Topics: Failure , Failure analysis

A Regulatory Inspection Tool in SDP Context

Chun-Chang Chao, Jyh-Der Lin, Tsu-Jen Lin, Shih-Hsun Huang

ICONE 2004; 77-81https://doi.org/10.1115/ICONE12-49229

Abstract

View Articletitled, A Regulatory Inspection Tool in SDP Context

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Topics: Inspection , Risk , Damage , Safety , Engines , Nuclear energy research , Probabilistic risk assessment , Probability , Risk-based regulations

Insights From Plant Specific Common Cause Failure Analysis

Young G. Jo

ICONE 2004; 83-88https://doi.org/10.1115/ICONE12-49232

Abstract

View Articletitled, Insights From Plant Specific Common Cause Failure Analysis

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Topics: Computer software , Databases , Failure , Failure analysis , Internet

Simulations of Thermal Performance for One- and Two-Dimensional Insulation and Aluminum Foil Fire Barriers

Mauricio A. Sa´nchez, William H. Sutton, Carlos A. Sa´nchez

ICONE 2004; 89-95https://doi.org/10.1115/ICONE12-49265

Abstract

View Articletitled, Simulations of Thermal Performance for One- and Two-Dimensional Insulation and Aluminum Foil Fire Barriers

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Topics: Aluminum foil , Engineering simulation , Fire , Insulation , Simulation , Computer simulation , Concretes , Corners (Structural elements) , Approximation , ASTM International

Industry-Specific Risk Models for Numerical Scoring of Hazards and Prioritization of Safety Measures

Yehia F. Khalil, Kathryn Johnson

ICONE 2004; 97-124https://doi.org/10.1115/ICONE12-49283

Abstract

View Articletitled, Industry-Specific Risk Models for Numerical Scoring of Hazards and Prioritization of Safety Measures

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Topics: Hazards , Risk , Safety , Failure mode and effects analysis , Health and safety , Nuclear power stations , Public utilities , Resource allocation , Risk analysis , Risk assessment

Melt Quenching by Water Injection From Below: Co-Injection of Water and Noncondensable Gas

Dae H. Cho, Richard J. Page, Sherif H. Abdulla, Mark H. Anderson, Helge B. Klockow, Michael L. Corradini

ICONE 2004; 125-131https://doi.org/10.1115/ICONE12-49284

Abstract

View Articletitled, Melt Quenching by Water Injection From Below: Co-Injection of Water and Noncondensable Gas

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Topics: Quenching (Metalworking) , Underground injection , Vessels , Water

The Probability and Management of Human Error

Romney D. Duffey, John W. Saull

ICONE 2004; 133-137https://doi.org/10.1115/ICONE12-49287

Abstract

View Articletitled, The Probability and Management of Human Error

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Topics: Errors , Probability , Failure , Accidents , Nuclear power , Risk , Safety , System failures

Development of the Methodology of the Safety Analysis Performed by the Coupled KIKO3D/ATHLET Code System in VVER-440 Type NPP

Gy. Hegyi, G. Hordo´sy, A. Keresztu´ri, Cs. Mara´czy, I. Panka, M. Telbisz, I. Trosztel

ICONE 2004; 139-146https://doi.org/10.1115/ICONE12-49300

Abstract

View Articletitled, Development of the Methodology of the Safety Analysis Performed by the Coupled KIKO3D/ATHLET Code System in VVER-440 Type NPP

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Topics: Nuclear power stations , Safety , Modeling , Transients (Dynamics) , Accidents , Boron , Computers , Control systems , Coolants , Emergencies

Development of the Methodology for Application of Revised Source Term to Operating Nuclear Power Plants in Korea

Moon Soo Park, Chang-Sun Kang, Joo-Hyun Moon

ICONE 2004; 147-151https://doi.org/10.1115/ICONE12-49309

Abstract

View Articletitled, Development of the Methodology for Application of Revised Source Term to Operating Nuclear Power Plants in Korea

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Topics: Nuclear power stations , Regulations , Fittings , Nuclear fission , Safety

A Feasibility Study on Reducing EPZ for APR-1400 in Societal Implications

Young Wook Lee, Joo Hyun Moon, Suk Hoon Kim, Chang Sun Kang

ICONE 2004; 153-157https://doi.org/10.1115/ICONE12-49312

Abstract

View Articletitled, A Feasibility Study on Reducing EPZ for APR-1400 in Societal Implications

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Topics: Emergencies , Public policy , Safety

Monitoring Risk to Generation

Stephen Meyer, Jeffrey Julius

ICONE 2004; 159-161https://doi.org/10.1115/ICONE12-49326

Abstract

View Articletitled, Monitoring Risk to Generation

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Topics: Energy generation , Plant personnel , Project tasks , Risk , Risk monitoring , Safety

Risk-Informed Hazard Barrier Assessment

Stephen Meyer, Eddie A. Krantz

ICONE 2004; 163-166https://doi.org/10.1115/ICONE12-49327

Abstract

View Articletitled, Risk-Informed Hazard Barrier Assessment

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Topics: Hazards , Risk , Data collection , Fire , Licensing , Model development , Power stations , Probabilistic safety assessment

A Preliminary Safety Analysis of the Whole Assembly Seed-Blanket Heterogeneous PWR Core

Jeongik Lee, Pradip Saha, Mujid S. Kazimi, Won-Jae Lee

ICONE 2004; 167-175https://doi.org/10.1115/ICONE12-49339

Abstract

View Articletitled, A Preliminary Safety Analysis of the Whole Assembly Seed-Blanket Heterogeneous PWR Core

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Topics: Manufacturing , Pressurized water reactors , Safety

Assessment of Potential Negative Impacts of the Main Gate Valve Closure Under Loss of Coolant Accident at VVER-440 Model 213 Nuclear Power Plant

Chester Everline, Gregory Gromov, Igor Lola, Stanislav Sholomitsky, Victor Mukoid, Steve Meyer, Alexander Sevbo

ICONE 2004; 177-184https://doi.org/10.1115/ICONE12-49342

Abstract

View Articletitled, Assessment of Potential Negative Impacts of the Main Gate Valve Closure Under Loss of Coolant Accident at VVER-440 Model 213 Nuclear Power Plant

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Topics: Accidents , Coolants , Gates (Closures) , Nuclear power stations , Valves

Realistic Safety Margin Analysis of “MONJU” Based on Plant Performance Measurements

Fumiaki Yamada, Kenji Kitamura

ICONE 2004; 185-190https://doi.org/10.1115/ICONE12-49381

Abstract

View Articletitled, Realistic Safety Margin Analysis of “MONJU” Based on Plant Performance Measurements

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Topics: Accidents , Safety

Mitigation of a Core Meltdown Scenario by Means of a Core Catcher Located Inside the Reactor Pressure Vessel

D. Aquaro, N. Zaccari

ICONE 2004; 191-199https://doi.org/10.1115/ICONE12-49392

Abstract

View Articletitled, Mitigation of a Core Meltdown Scenario by Means of a Core Catcher Located Inside the Reactor Pressure Vessel

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Topics: Accidents , Ceramic matrix composites , Ceramics , Computer simulation , Cooling , Design , Electrical conductivity , Pressure vessels , Reactor vessels , Simulation

Intentional Back Flow Effects on Ruptured Steam Generator Cooldown During a SGTR Event for KSNP

Cheol Woo Kim, Seok Jeong Park, Chul Jin Choi, Jong Tae Seo

ICONE 2004; 201-209https://doi.org/10.1115/ICONE12-49395

Abstract

View Articletitled, Intentional Back Flow Effects on Ruptured Steam Generator Cooldown During a SGTR Event for KSNP

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Topics: Boilers , Flow (Dynamics)

Validation of the Fast-Running In-Vessel Model ASTRID for Predicting the Radioactive Releases to the Containment

Miettinen Jaakko, Philipp Schmuck

ICONE 2004; 211-221https://doi.org/10.1115/ICONE12-49454

Abstract

View Articletitled, Validation of the Fast-Running In-Vessel Model ASTRID for Predicting the Radioactive Releases to the Containment

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Topics: Containment , Vessels , Radioactivity , Pressurized water reactors , Reactor vessels , Thermal hydraulics , Accidents , Boiling water reactors , Chain , Coolants

A Balancing Method for Calculating a Component RAW Including CCF

Kilyoo Kim, Dae Il Kang, Joon-Eon Yang

ICONE 2004; 223-227https://doi.org/10.1115/ICONE12-49469

Abstract

View Articletitled, A Balancing Method for Calculating a Component RAW Including CCF

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Topics: Failure

IRIS PRA Preliminary Results and Future Direction

David J. Finnicum, Charles L. Kling, Mario D. Carelli

ICONE 2004; 229-234https://doi.org/10.1115/ICONE12-49500

Abstract

View Articletitled, IRIS PRA Preliminary Results and Future Direction

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Topics: Damage , Design , Emergency response , Fire , Licensing , Plant design , Protective actions , Risk , Risk-based design , Safety

Transition Risk Method and Example

Raymond E. Schneider, Steven E. Farkas

ICONE 2004; 235-238https://doi.org/10.1115/ICONE12-49519

Abstract

View Articletitled, Transition Risk Method and Example

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Topics: Risk , Maintenance , Cooling , Damage , Failure mechanisms , Feedwater , Heat , Pressure , Risk assessment , Temperature

SAMA Analysis in Support of License Renewal Application for the Fort Calhoun Station

Raymond E. Schneider, Harold A. Hackerott, Mathew C. Jacob

ICONE 2004; 239-244https://doi.org/10.1115/ICONE12-49544

Abstract

View Articletitled, SAMA Analysis in Support of License Renewal Application for the Fort Calhoun Station

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Topics: Fortification , Licensing , Pressurized water reactors , Risk , Accidents , Design

The Development of Mobile Melt-Dilute Technology for the Treatment of Former Soviet Union Research Reactor Fuel

D. A. Sell, E. A. Howden, K. J. Allen, K. Marsden, B. R. Westphal, H. B. Peacock, N. C. Iyer, D. L. Fisher, T. M. Adams, R. L. Sindelar

ICONE 2004; 245-251https://doi.org/10.1115/ICONE12-49550

Abstract

View Articletitled, The Development of Mobile Melt-Dilute Technology for the Treatment of Former Soviet Union Research Reactor Fuel

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Topics: Nuclear fuels , Weapons , Spent nuclear fuels , Storage , Uranium , Conceptual design , Design , Engineering prototypes , Fuel storage , Furnaces

ARTIST: Introduction and First Results

S. Gu¨ntay, D. Suckow, A. Dehbi, R. Kapulla

ICONE 2004; 253-261https://doi.org/10.1115/ICONE12-49553

Abstract

View Articletitled, ARTIST: Introduction and First Results

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Topics: Accident management , Accidents , Aerosols , Boilers , Condensation , Decontamination , Drops , Flow (Dynamics) , Particulate matter , Pressure

Status of the ANS Low Power and Shutdown PRA Standard

Kenneth L. Kiper

ICONE 2004; 263-265https://doi.org/10.1115/ICONE12-49605

Abstract

View Articletitled, Status of the ANS Low Power and Shutdown PRA Standard

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Topics: Public utilities , Risk

Qualitative Risk Assessment in the ANS LPSD PRA Standard

William E. Burchill, Jeffrey A. Julius, Mary Drouin, Kenneth L. Kiper

ICONE 2004; 267-272https://doi.org/10.1115/ICONE12-49606

Abstract

View Articletitled, Qualitative Risk Assessment in the ANS LPSD PRA Standard

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Topics: Risk assessment , Probabilistic risk assessment , Risk

Probabilistic Risk Assessment of Bolted Dry Spent Fuel Storage Cask

Jeffrey T. Mitman, Ken Canavan

ICONE 2004; 273-281https://doi.org/10.1115/ICONE12-49607

Abstract

View Articletitled, Probabilistic Risk Assessment of Bolted Dry Spent Fuel Storage Cask

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Topics: Probabilistic risk assessment , Spent fuel storage

Plant Modifications for Mixed Oxide Fuel Use in U.S. Reactors

Richard Browder

ICONE 2004; 283-287https://doi.org/10.1115/ICONE12-49033

Abstract

View Articletitled, Plant Modifications for Mixed Oxide Fuel Use in U.S. Reactors

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Topics: Boron , Fuels , Security , Transportation systems , Weapons

Application of Power Reactors for Transmutation of Actinides

B. R. Bergelson, A. S. Gerasimov, G. V. Tikhomirov

ICONE 2004; 289-293https://doi.org/10.1115/ICONE12-49049

Abstract

View Articletitled, Application of Power Reactors for Transmutation of Actinides

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Topics: Equilibrium (Physics) , Heavy water reactors , Radioactive wastes , Spent nuclear fuels , Storage , Water

Pu-Rich MOX Agglomerate-by-Agglomerate Model for Fuel Pellet Burnup Analysis

G. S. Chang

ICONE 2004; 295-300https://doi.org/10.1115/ICONE12-49141

Abstract

View Articletitled, Pu-Rich MOX Agglomerate-by-Agglomerate Model for Fuel Pellet Burnup Analysis

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Topics: Fuels , Modeling , Pressurized water reactors , Irradiation (Radiation exposure) , Licensing , Nuclear fission , Uranium , Weapons

The REBUS Experimental Programme for Burn-Up Credit

Pierre D’hondt, Peter Baeten, Leo Sannen, Daniel Marloye, Benoit Lance, Alfred Renard, Jacques Basselier

ICONE 2004; 301-307https://doi.org/10.1115/ICONE12-49164

Abstract

View Articletitled, The REBUS Experimental Programme for Burn-Up Credit

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Topics: Fuels , Nuclear fission , Nuclear research , Physics , Pressurized water reactors , Public utilities , Spent nuclear fuels , Water

Glass Melter Replacement and Melter Technology Development in the Tokai Vitrification Facility

Atsushi Aoshima, Tetsuo Kozaka, Kazuhiko Tanaka

ICONE 2004; 309-314https://doi.org/10.1115/ICONE12-49175

Abstract

View Articletitled, Glass Melter Replacement and Melter Technology Development in the Tokai Vitrification Facility

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Topics: Glass , Technology development , Vitrification , Design , Manufacturing , Electrodes , Cycles , Damage , Lasers , Platinum group metals

Conceptual Design Study on Fast Reactor Fuel Reprocessing System Using Super-DIREX Process

Takeshi Takata, Yoshikazu Koma, Koji Sato, Takashi Shimada, Yukihide Mori, Shinya Ogumo, Yasuhiro Ishida

ICONE 2004; 315-320https://doi.org/10.1115/ICONE12-49183

Abstract

View Articletitled, Conceptual Design Study on Fast Reactor Fuel Reprocessing System Using Super-DIREX Process

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Topics: Conceptual design , Fast neutron reactors , Fuels

High Efficiency Combined Aggregate – Submerged Combustion Melter–Electric Furnace for Vitrification of High-Level Radioactive Wastes

L. S. Pioro, I. L. Pioro

ICONE 2004; 321-324https://doi.org/10.1115/ICONE12-49298

Abstract

View Articletitled, High Efficiency Combined Aggregate – Submerged Combustion Melter–Electric Furnace for Vitrification of High-Level Radioactive Wastes

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Topics: Combustion , Furnaces , Radioactive wastes , Vitrification

Basic Design and Safety Evaluation of Metal Cask Storage Facility With New Transportation System

Takashi Satoh, Hiroshi Ijichi, Tadashi Yamane, Takeshi Mannen, Kouji Busujima, Masashi Shimizu

ICONE 2004; 325-332https://doi.org/10.1115/ICONE12-49320

Abstract

View Articletitled, Basic Design and Safety Evaluation of Metal Cask Storage Facility With New Transportation System

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Topics: Design , Fluid films , Metals , Safety , Storage , Transportation systems

Assessing Aircraft Hazards to Nuclear Facilities

Gary M. Sandquist, D. Shannon Sentell, Jr.

ICONE 2004; 333-337https://doi.org/10.1115/ICONE12-49384

Abstract

View Articletitled, Assessing Aircraft Hazards to Nuclear Facilities

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Topics: Aircraft , Hazards , Nuclear power stations , Risk assessment

Integral Solutions of Phase Change With Internal Heat Generation

Ali Siahpush, John Crepeau

ICONE 2004; 339-344https://doi.org/10.1115/ICONE12-49412

Abstract

View Articletitled, Integral Solutions of Phase Change With Internal Heat Generation

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Topics: Heat

Improving the Utilization of Nuclear Resources

Jay F. Kunze, Gary M. Sandquist, D. Shannon Sentell, Jr.

ICONE 2004; 345-350https://doi.org/10.1115/ICONE12-49445

Abstract

View Articletitled, Improving the Utilization of Nuclear Resources

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Topics: Combustion , Delays , Economics , Fuels , Governments , Light water reactors , Nuclear fuel cycle , Nuclear fuels , Nuclear industry , Nuclear power

Experimental Equipment Design and Testing of the DEOX Process

K. J. Bateman, B. R. Westphal, M. A. Stawicki

ICONE 2004; 351-356https://doi.org/10.1115/ICONE12-49451

Abstract

View Articletitled, Experimental Equipment Design and Testing of the DEOX Process

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Topics: Cladding systems (Building) , Collaboration , Design , Fuels , Nuclear fission , Nuclear fuels , Oxidation , Particle size , Size reduction (Materials) , Spent nuclear fuels

Integrity of Radioactive Waste Packages at the Yucca Mountain Repository

Gary Sandquist, Andrew Biaglow, Michael Huber, Chad Jagmin

ICONE 2004; 357-362https://doi.org/10.1115/ICONE12-49491

Abstract

View Articletitled, Integrity of Radioactive Waste Packages at the Yucca Mountain Repository

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Topics: Radioactive wastes

Assessment of MELCOR 1.8.5 Versus Different Versions of SCDAP/RELAP5 MOD 3.3 With Lower Head Creep Rupture Analysis of Alternative Accident Sequences of the Three Mile Island Unit 2

Sang Lung Chan

ICONE 2004; 363-370https://doi.org/10.1115/ICONE12-49032

Abstract

View Articletitled, Assessment of MELCOR 1.8.5 Versus Different Versions of SCDAP/RELAP5 MOD 3.3 With Lower Head Creep Rupture Analysis of Alternative Accident Sequences of the Three Mile Island Unit 2

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Topics: Accidents , Creep , Rupture , Flow (Dynamics) , Failure , Temperature , Pumps , Carbon steel , Delays , High pressure (Physics)

Analysis of Magnetohydrodynamic Flow in Annular Duct

Geun Jong Yoo, Hoon Ki Choi, Jae Jeong Eun

ICONE 2004; 371-376https://doi.org/10.1115/ICONE12-49035

Abstract

View Articletitled, Analysis of Magnetohydrodynamic Flow in Annular Duct

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Topics: Ducts , Flow (Dynamics) , Magnetohydrodynamics , Pumps

One-Dimensional Drift-Flux Model and Constitutive Equations for Relative Motion Between Phases in Various Two-Phase Flow Regimes at Microgravity Conditions

Takashi Hibiki, Tomoji Takamasa, Mamoru Ishii

ICONE 2004; 377-386https://doi.org/10.1115/ICONE12-49037

Abstract

View Articletitled, One-Dimensional Drift-Flux Model and Constitutive Equations for Relative Motion Between Phases in Various Two-Phase Flow Regimes at Microgravity Conditions

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Topics: Constitutive equations , Gravity (Force) , Two-phase flow , Flow (Dynamics) , Porosity

25-Years Three-Fluid Modeling Experience: Successes and Limits

Nikolay Ivanov Kolev

ICONE 2004; 387-392https://doi.org/10.1115/ICONE12-49054

Abstract

View Articletitled, 25-Years Three-Fluid Modeling Experience: Successes and Limits

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Topics: Fluids , Modeling , Nuclear engineering

The Role of Two-Phase Coolant in Moderating Fretting in Nuclear Steam Generators

John M. Dyke

ICONE 2004; 393-395https://doi.org/10.1115/ICONE12-49059

Abstract

View Articletitled, The Role of Two-Phase Coolant in Moderating Fretting in Nuclear Steam Generators

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Topics: Boilers , Coolants , Nuclear reactor steam generators , Vibration , Boiling , Bubbles , Design , Flow (Dynamics) , Geometry , Japan Society of Mechanical Engineers

Computer Code Applicability Assessment for the Advanced CANDU Reactor

D. J. Wren, N. Popov, V. J. Langman, V. G. Snell

ICONE 2004; 397-404https://doi.org/10.1115/ICONE12-49101

Abstract

View Articletitled, Computer Code Applicability Assessment for the Advanced CANDU Reactor

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Topics: Computers , Safety , Computer software , Design , Licensing , Nuclear power , Quality control

Validation of Physics and Thermalhydraulics Computer Codes for Advanced CANDU Reactor Applications

D. J. Wren, N. Popov, V. G. Snell

ICONE 2004; 405-413https://doi.org/10.1115/ICONE12-49102

Abstract

View Articletitled, Validation of Physics and Thermalhydraulics Computer Codes for Advanced CANDU Reactor Applications

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Topics: Computers , Physics , Safety , Design , Water , Computer software , Coolants , Databases , Fuels , Quality control

Large-Break Loss-of-Coolant Accident Phenomena Identification and Ranking Table (PIRT) for the Advanced CANDU Reactor

N. Popov, H. E. Sills, V. G. Snell, B. Boyack, V. J. Langman

ICONE 2004; 415-424https://doi.org/10.1115/ICONE12-49103

Abstract

View Articletitled, Large-Break Loss-of-Coolant Accident Phenomena Identification and Ranking Table (PIRT) for the Advanced CANDU Reactor

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Topics: Accidents , Coolants , Water , Design , Safety , Fuels , Uranium , Computers , Economics , Electricity (Physics)

Application of ANNs in Tube CHF Prediction: Effect of Neuron Number in Hidden Layer

Lang Han, Jianqiang Shan, Bin Zhang

ICONE 2004; 425-428https://doi.org/10.1115/ICONE12-49112

Abstract

View Articletitled, Application of ANNs in Tube CHF Prediction: Effect of Neuron Number in Hidden Layer

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Topics: Artificial neural networks , Critical heat flux

RELAP5-3D Code Validation for RBMK-1500 Reactors

Evaldas Bubelis, Algirdas Kaliatka, Eugenijus Uspuras

ICONE 2004; 429-438https://doi.org/10.1115/ICONE12-49122

Abstract

View Articletitled, RELAP5-3D Code Validation for RBMK-1500 Reactors

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Topics: Circuits , Modeling , Nuclear power stations , Safety , Transients (Dynamics)

COBRA Code Assessment for Dry Out Power of Advanced CANDU Fuels

Hernando Daverio, Luis E. Juanico´, Dari´o Delmastro

ICONE 2004; 439-444https://doi.org/10.1115/ICONE12-49123

Abstract

View Articletitled, COBRA Code Assessment for Dry Out Power of Advanced CANDU Fuels

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Topics: Fuels

Sensitivity Studies on Thermal-Hydraulic Behavior Associated With LOFT Total Loss-of-Feedwater Accident

Kyu Bok Lee, Heedo Lee, Hee Jin Ko, Ho Je Seong, Jae Sik Jeung, Chang Hyo Kim

ICONE 2004; 445-453https://doi.org/10.1115/ICONE12-49124

Abstract

View Articletitled, Sensitivity Studies on Thermal-Hydraulic Behavior Associated With LOFT Total Loss-of-Feedwater Accident

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Topics: Accidents , Feedwater , Transients (Dynamics) , Boilers , Computers , Discharge coefficient , Fluids , Heat transfer , Heat transfer coefficients , Relief valves

Jet Pump Noise Analysis for BWRs

Rogelio Castillo-Dura´n, Javier Ortiz-Villafuerte, He´ctor Herna´ndez-Lo´pez, Gustavo Alonso-Vargas, Gabriel Calleros-Micheland

ICONE 2004; 455-458https://doi.org/10.1115/ICONE12-49136

Abstract

View Articletitled, Jet Pump Noise Analysis for BWRs

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Topics: Boiling water reactors , Jet pumps , Noise (Sound) , Signals , Computer software , Computers , Nuclear power stations , Pressure drop , Algorithms , Fast Fourier transforms

Thermal Hydraulic Analysis Due to the Changes in Heat Removal for Advanced Heavy Water Reactor

B. Chatterjee, A. Srivastava, D. Mukhopadhyay, P. Majumdar, H. G. Lele, S. K. Gupta

ICONE 2004; 459-464https://doi.org/10.1115/ICONE12-49147

Abstract

View Articletitled, Thermal Hydraulic Analysis Due to the Changes in Heat Removal for Advanced Heavy Water Reactor

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Topics: Heat , Heavy water reactors , Flow (Dynamics) , Feedwater , Turbines , Pressure , Valves , Control equipment , Temperature , Collapse

A Simplified Model for Dynamic Simulation of the Primary Circuit of Pressurized Water Reators

Jian Su, Thiago Pontual

ICONE 2004; 465-473https://doi.org/10.1115/ICONE12-49159

Abstract

View Articletitled, A Simplified Model for Dynamic Simulation of the Primary Circuit of Pressurized Water Reators

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Topics: Circuits , Simulation , Water , Transients (Dynamics) , Accidents , Boilers , Dynamics (Mechanics) , Engineering models , Flow (Dynamics) , Fuels

Linear Analysis of Density-Wave Oscillations in a Parallel Heated Channel

Hesham Nagah Abdou, Veronica Beatriz Garea, Axel Eduardo Larreteguy

ICONE 2004; 475-484https://doi.org/10.1115/ICONE12-49162

Abstract

View Articletitled, Linear Analysis of Density-Wave Oscillations in a Parallel Heated Channel

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Topics: Density , Oscillations , Waves , Boiling , Steam , Subcooling , Equilibrium (Physics) , Stability , Thermal equilibrium , Friction

An Advanced Ultrasonic Technique for Flow and Void Fraction Measurements of Two-Phase Flow

J. L. H. Faccini, J. Su, G. D. Harvel, J. S. Chang

ICONE 2004; 485-489https://doi.org/10.1115/ICONE12-49171

Abstract

View Articletitled, An Advanced Ultrasonic Technique for Flow and Void Fraction Measurements of Two-Phase Flow

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Topics: Flow (Dynamics) , Porosity , Two-phase flow , Echoes , Flowmeters , Pipes , Flow visualization , Generators , Nuclear engineering , Signals

Effects of Contact Line Condition on Excitation of Internal Waves Confined by a Cylindrical Wall

Takahiro Ito, Jun Shimizu, Hideyuki Nakayama, Yutaka Kukita

ICONE 2004; 491-497https://doi.org/10.1115/ICONE12-49187

Abstract

View Articletitled, Effects of Contact Line Condition on Excitation of Internal Waves Confined by a Cylindrical Wall

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Topics: Excitation , Waves , Fluids , Cycles , Deformation , Mechanical admittance , Oscillations

Visualization System of Swirl Motion

Katsuyuki Nakayama, Kenji Umeda, Toshio Ichikawa, Teruyuki Nagano, Hideyuki Sakata

ICONE 2004; 499-504https://doi.org/10.1115/ICONE12-49189

Abstract

View Articletitled, Visualization System of Swirl Motion

PDF

Topics: Visualization , Swirling flow , Flow (Dynamics) , Instrumentation , Design , Eigenvalues , Numerical analysis , Particulate matter , Tensors , Transparent solids

Influence of Dissolved Gas Concentration on Subcooled Flow Boiling Critical Heat Flux in Short Vertical Tube

Koichi Hata, Hirokazu Komori, Masahiro Shiotsu, Nobuaki Noda

ICONE 2004; 505-514https://doi.org/10.1115/ICONE12-49194

Abstract

View Articletitled, Influence of Dissolved Gas Concentration on Subcooled Flow Boiling Critical Heat Flux in Short Vertical Tube

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Topics: Boiling , Critical heat flux , Flow (Dynamics) , Subcooling , Pressure , Oxygen , Surface roughness , Flux (Metallurgy) , Heat , Nitrogen

Study on Mixing Due to Transversal Flow in a Fuel Subassembly of Fast Reactor: Sodium Experiment Using a 37-Pin Subassembly Model

Hideki Kamide, Hiroyuki Miyakoshi, Nobuhiro Kawamata, Hiroyuki Ohshima

ICONE 2004; 515-523https://doi.org/10.1115/ICONE12-49199

Abstract

View Articletitled, Study on Mixing Due to Transversal Flow in a Fuel Subassembly of Fast Reactor: Sodium Experiment Using a 37-Pin Subassembly Model

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Topics: Cross-flow , Fast neutron reactors , Flow (Dynamics) , Fuels , Sodium

Effect of Inlet Flow Resistance on Instabilities During Startup Transient in Natural Circulation BWRs

Selim Kuran, Xiaodong Sun, Yiban Xu, Ho Jun Yoon, Ling Cheng, Shripad T. Revankar, Mamoru Ishii, Weidong Wang

ICONE 2004; 525-535https://doi.org/10.1115/ICONE12-49221

Abstract

View Articletitled, Effect of Inlet Flow Resistance on Instabilities During Startup Transient in Natural Circulation BWRs

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Topics: Boiling water reactors , Flow (Dynamics) , Transients (Dynamics) , Oscillations , Engineering prototypes , Manufacturing , Pressure , Reactor vessels , Simulation , Simulation experiments

Study on Drag Coefficients for Two Groups of Bubbles

Xiaodong Sun, Yang Liu, Basar Ozar, Mamoru Ishii, Joseph M. Kelly

ICONE 2004; 537-543https://doi.org/10.1115/ICONE12-49231

Abstract

View Articletitled, Study on Drag Coefficients for Two Groups of Bubbles

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Topics: Bubbles , Drag (Fluid dynamics) , Flow (Dynamics) , Fluids , Databases , Heat transfer , Modeling , Momentum , Pipes , Slug flows

Development of Moisture Separator With High Performance of Steam Generator

Kenji Nishida, Toshiyuki Mizutani, Tadahiko Suzuta, Yoshiyuki Kondo, Yasuhiko Hirao

ICONE 2004; 545-550https://doi.org/10.1115/ICONE12-49241

Abstract

View Articletitled, Development of Moisture Separator With High Performance of Steam Generator

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Topics: Boilers

Assessment of the MELCOR Code Against PHEBUS Experiment FPT-1 Performed in the Frame of ISP-46

J. Birchley

ICONE 2004; 551-560https://doi.org/10.1115/ICONE12-49267

Abstract

View Articletitled, Assessment of the MELCOR Code Against PHEBUS Experiment FPT-1 Performed in the Frame of ISP-46

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Topics: Accidents , Aerosols , Chemistry , Computers , Containment , Engineering standards , Heat , Modeling , Nuclear fission , Nuclear power stations

Study on Entrainment From High-Viscosity Falling Liquid Film of Counter-Current Two-Phase Flow in a Vertical Pipe

Yasuo Koizumi, Ryou Enari, Hiroyasu Ohtake

ICONE 2004; 561-569https://doi.org/10.1115/ICONE12-49268

Abstract

View Articletitled, Study on Entrainment From High-Viscosity Falling Liquid Film of Counter-Current Two-Phase Flow in a Vertical Pipe

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Topics: Floods , Flow (Dynamics) , Liquid films , Pipes , Two-phase flow , Viscosity , Silicon , Water , Reynolds number , Drops

Experimental Study on Post-Dryout Heat Transfer of Dispersed Flow in Vertical Narrow Annuli

Aye Myint, Wenxi Tian, Zhihui Li, Suizheng Qiu, Dounan Jia, Guanghui Su

ICONE 2004; 571-576https://doi.org/10.1115/ICONE12-49293

Abstract

View Articletitled, Experimental Study on Post-Dryout Heat Transfer of Dispersed Flow in Vertical Narrow Annuli

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Topics: Annulus , Flow (Dynamics) , Heat transfer

Film Boiling on Downward Quenching Hemisphere of Varying Sizes

Chan S. Kim, Kune Y. Suh, Joy L. Rempe, Fan-Bill Cheung, Sang B. Kim

ICONE 2004; 577-585https://doi.org/10.1115/ICONE12-49305

Abstract

View Articletitled, Film Boiling on Downward Quenching Hemisphere of Varying Sizes

PDF

Topics: Film boiling , Quenching (Metalworking) , Heat transfer coefficients , Boiling , Copper , Heat transfer , Laminar flow

Direct Vessel Vertical Injection for Advanced Emergency Core Cooling System

Sang H. Yoon, Kune Y. Suh, Yong H. Yu

ICONE 2004; 587-593https://doi.org/10.1115/ICONE12-49308

Abstract

View Articletitled, Direct Vessel Vertical Injection for Advanced Emergency Core Cooling System

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Topics: Emergency core cooling systems , Vessels , Coolants , Manufacturing , Nozzles , Water , Accidents , Collaboration , Emergencies , Engineering design

Experimental Study About ONB and Subcooled Boiling Heat Transfer

Changhong Peng, Aye Myint, Yun Guo, Dounan Jia

ICONE 2004; 595-600https://doi.org/10.1115/ICONE12-49311

Abstract

View Articletitled, Experimental Study About ONB and Subcooled Boiling Heat Transfer

PDF

Topics: Annulus , Boiling , Heat transfer , Subcooling

Wave-Induced Streaming in Vertically-Excited, Stratified Fluids

Hideyuki Nakayama, Haruhiko Mori, Jun Shimizu, Takahiro Ito, Hideo Nakamura, Yoshiyuki Tsuji, Yutaka Kukita

ICONE 2004; 601-607https://doi.org/10.1115/ICONE12-49314

Abstract

View Articletitled, Wave-Induced Streaming in Vertically-Excited, Stratified Fluids

PDF

Topics: Fluids , Waves

Experimental Investigation of Mixed Convection Heat Transfer Caused by Forced-Jets in Large Enclosure

Fenglei Niu, Per F. Peterson

ICONE 2004; 609-616https://doi.org/10.1115/ICONE12-49323

Abstract

View Articletitled, Experimental Investigation of Mixed Convection Heat Transfer Caused by Forced-Jets in Large Enclosure

PDF

Topics: Heat transfer , Jets , Mixed convection , Containment , Accidents , Containment buildings , Cooling systems , Flow (Dynamics) , Natural convection

Detailed CFD Analysis of Coolant Mixing in VVER-440 Fuel Assembly Heads Performed With the Code CFX-5.5

Ga´bor Le´gra´di, Attila Aszo´di

ICONE 2004; 617-626https://doi.org/10.1115/ICONE12-49325

Abstract

View Articletitled, Detailed CFD Analysis of Coolant Mixing in VVER-440 Fuel Assembly Heads Performed With the Code CFX-5.5

PDF

Topics: Computational fluid dynamics , Coolants , Fuels , Manufacturing , Nuclear power stations , Signals , Thermocouples , Economics , Flow (Dynamics) , Heat

Modeling of Safety/Relief Valves With Thermal-Hydraulic System Computer Codes

Claudio Delfino, Birol Aktas

ICONE 2004; 627-636https://doi.org/10.1115/ICONE12-49336

Abstract

View Articletitled, Modeling of Safety/Relief Valves With Thermal-Hydraulic System Computer Codes

PDF

Topics: Computers , Modeling , Relief valves , Safety , Simulation , Valves , Boiling water reactors , Cooling , Errors , Flow (Dynamics)

Experimental Study of Stable Droplet in Blowdown Phenomenon of Large Break LOCA

Yoshiyuki Kondo, Koichi Tanimoto, Keiichi Hori, Tatsuo Ishiguro, Junji Ogata, Shigemitsu Umezawa, Tetsuya Teramae, Yuji Furukawa

ICONE 2004; 637-642https://doi.org/10.1115/ICONE12-49349

Abstract

View Articletitled, Experimental Study of Stable Droplet in Blowdown Phenomenon of Large Break LOCA

PDF

Topics: Drops , Flow (Dynamics)

Experimental Study on Dryout Point in Vertical Narrow Annulus Under Low Flow Conditions

Wenxi Tian, Aye Myint, Zhihui Li, Suizheng Qiu, G. H. Su, Dounan Jia

ICONE 2004; 643-648https://doi.org/10.1115/ICONE12-49351

Abstract

View Articletitled, Experimental Study on Dryout Point in Vertical Narrow Annulus Under Low Flow Conditions

PDF

Topics: Annulus , Flow (Dynamics)

Generation of Consistent Data for Neutron Kinetics Models of the GRS System Code ATHLET

S. Langenbuch, K. Velkov

ICONE 2004; 649-653https://doi.org/10.1115/ICONE12-49356

Abstract

View Articletitled, Generation of Consistent Data for Neutron Kinetics Models of the GRS System Code ATHLET

PDF

Topics: Algorithms , Boron , Neutrons , Switches , Transients (Dynamics)

Assessment of RELAP5 mod3.3 and CATHARE2 V1.5a Against a Full Scale Test of PERSEO Device

F. Bianchi, P. Meloni, R. Ferri, A. Achilli

ICONE 2004; 655-661https://doi.org/10.1115/ICONE12-49374

Abstract

View Articletitled, Assessment of RELAP5 mod3.3 and CATHARE2 V1.5a Against a Full Scale Test of PERSEO Device

PDF

Topics: Heat , Heat exchangers , Reliability , Safety , Stability

Sensitivity Analysis of 200 mm LOCA at Armenian NPP Unit 2

Armen Amirjanyan, Tsolak Malakyan, Jae Jo

ICONE 2004; 663-672https://doi.org/10.1115/ICONE12-49390

Abstract

View Articletitled, Sensitivity Analysis of 200 mm LOCA at Armenian NPP Unit 2

PDF

Topics: Nuclear power stations , Sensitivity analysis , Diesel generators , Pumps , Safety , Trains , Acceptance criteria , Cladding systems (Building) , Temperature , Accidents

An Implementation and Assessment of the Viscous Stress Model in the MARS Multi-Dimensional Component

S. W. Bae, J. J. Jeong, M. Hwang, B. D. Chung

ICONE 2004; 673-679https://doi.org/10.1115/ICONE12-49401

Abstract

View Articletitled, An Implementation and Assessment of the Viscous Stress Model in the MARS Multi-Dimensional Component

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Topics: Stress , Fluids , Hydraulic drive systems , Nuclear industry , Nuclear reactors , Safety , Shear stress , Simulation , Turbulence , Viscosity

Recent Improvements of Physical Models in the CATHARE Code and Their Validation

I. Dor, G. Geffraye, G. Lavialle, T. Mieusset

ICONE 2004; 681-691https://doi.org/10.1115/ICONE12-49408

Abstract

View Articletitled, Recent Improvements of Physical Models in the CATHARE Code and Their Validation

PDF

Topics: Boilers , Cladding systems (Building) , Condensation , Diffusion (Physics) , Film condensation , Fluids , Friction , Gases , Heat , Heat transfer coefficients

Analysis of Pressure Wave Phenomena in Steam Line Piping

Juswald Vedovi, Michael J. Hibbard, Donald R. Todd, Kostadin Ivanov

ICONE 2004; 693-703https://doi.org/10.1115/ICONE12-49414

Abstract

View Articletitled, Analysis of Pressure Wave Phenomena in Steam Line Piping

PDF

Topics: Pipes , Pressure , Steam , Turbines , Water hammer , Wave phenomena , Waves

Effect of Wall Surface Wettability Due to Radiation Induced Surface Activation on Quenching Process

Naohisa Tamura, Tatsuya Hazuku, Tomoji Takamasa, Kaichiro Mishima, Toru Mitsutake, Sinichi Morooka

ICONE 2004; 705-710https://doi.org/10.1115/ICONE12-49420

Abstract

View Articletitled, Effect of Wall Surface Wettability Due to Radiation Induced Surface Activation on Quenching Process

PDF

Topics: Quenching (Metalworking) , Radiation (Physics)

Experimental Investigation of Coolant Mixing in the RPV of a PWR During Natural Circulation Conditions

S. Kliem, T. Hoehne, H.-M. Prasser, U. Rohde, F.-P. Weiss

ICONE 2004; 711-720https://doi.org/10.1115/ICONE12-49424

Abstract

View Articletitled, Experimental Investigation of Coolant Mixing in the RPV of a PWR During Natural Circulation Conditions

PDF

Topics: Coolants , Pressurized water reactors , Flow (Dynamics) , Slug flows , Density , Safety , Boron , Circuits , Heat , Accidents

Simulations of the Pressurizer Safety Valve Stuck Open Accident for the Development of the Accident Sequences in the Low Power/Shutdown PSA

Ho-Gon Lim, Jin-Hee Park, Seung-Chul Jang, Tae-Woon Kim

ICONE 2004; 721-726https://doi.org/10.1115/ICONE12-49436

Abstract

View Articletitled, Simulations of the Pressurizer Safety Valve Stuck Open Accident for the Development of the Accident Sequences in the Low Power/Shutdown PSA

PDF

Topics: Accidents , Safety , Simulation , Valves , Damage , Pressure , Platform supply vessels , Boilers , Cooling systems , Failure

Void Fraction Predictions in Rod Bundles at Low-Pressure Low-Flow Conditions Based on Cunningham-Yeh Model

Cesare Frepoli, Katsuhiro Ohkawa

ICONE 2004; 727-736https://doi.org/10.1115/ICONE12-49437

Abstract

View Articletitled, Void Fraction Predictions in Rod Bundles at Low-Pressure Low-Flow Conditions Based on Cunningham-Yeh Model

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Topics: Flow (Dynamics) , Fuel rods , Porosity , Pressure , Boiling , Accidents , Coolants , Databases , Design , Drag (Fluid dynamics)

The Combined Thermohydraulics-Neutronics Code TRAB-SMABRE for 3D Plant Transient and Accident Analyses

Miettinen Jaakko, Vanttola Timo, Daavittila Antti, Ra¨ty Hanna

ICONE 2004; 737-743https://doi.org/10.1115/ICONE12-49452

Abstract

View Articletitled, The Combined Thermohydraulics-Neutronics Code TRAB-SMABRE for 3D Plant Transient and Accident Analyses

PDF

Topics: Accidents , Thermal hydraulics , Transients (Dynamics) , Boiling water reactors , Pressurized water reactors , Circuits , Fuels , Boron , Diffusion (Physics) , Flow (Dynamics)

Derivations of Correlation and Model of Transition Boiling Heat Transfer: Liquid-Solid Contact Model for Transition Boiling Heat Transfer in High Wall Superheat

Hiroyasu Ohtake, Yasuo Koizumi

ICONE 2004; 745-749https://doi.org/10.1115/ICONE12-49460

Abstract

View Articletitled, Derivations of Correlation and Model of Transition Boiling Heat Transfer: Liquid-Solid Contact Model for Transition Boiling Heat Transfer in High Wall Superheat

PDF

Topics: Boiling , Heat transfer

A Stability Investigation of Two-Dimensional Surface Waves on Evaporating, Isothermal or Condensing Liquid Films: Part II — A Universal Linear Stability Formulation

Xuemin Ye, Weiping Yan, Chunxi Li

ICONE 2004; 751-757https://doi.org/10.1115/ICONE12-49480

Abstract

View Articletitled, A Stability Investigation of Two-Dimensional Surface Waves on Evaporating, Isothermal or Condensing Liquid Films: Part II — A Universal Linear Stability Formulation

PDF

Topics: Evaporation , Liquid films , Stability , Surface waves (Fluid)

A Stability Investigation of Two-Dimensional Surface Waves on Evaporating, Isothermal or Condensing Liquid Films: Part III — Temporal Stability of Traveling Waves

Xuemin Ye, Chunxi Li, Weiping Yan

ICONE 2004; 759-765https://doi.org/10.1115/ICONE12-49481

Abstract

View Articletitled, A Stability Investigation of Two-Dimensional Surface Waves on Evaporating, Isothermal or Condensing Liquid Films: Part III — Temporal Stability of Traveling Waves

PDF

Topics: Evaporation , Flow (Dynamics) , Liquid films , Stability , Surface waves (Fluid) , Traveling waves

A Stability Investigation of Two-Dimensional Surface Waves on Evaporating, Isothermal or Condensing Liquid Films: Part I — Thermal Non-Equilibrium Effects on Wave Velocity

Chunxi Li, Xuemin Ye

ICONE 2004; 767-774https://doi.org/10.1115/ICONE12-49482

Abstract

View Articletitled, A Stability Investigation of Two-Dimensional Surface Waves on Evaporating, Isothermal or Condensing Liquid Films: Part I — Thermal Non-Equilibrium Effects on Wave Velocity

PDF

Topics: Equilibrium (Physics) , Evaporation , Liquid films , Lubrication theory , Stability , Surface waves (Fluid) , Waves

Subcooled Boiling Data From Rod Bundles

Zeses E. Karoutas, Yixing Sung, Yutung R. Chang, Gennady A. Kogan, Paul F. Joffre

ICONE 2004; 775-794https://doi.org/10.1115/ICONE12-49492

Abstract

View Articletitled, Subcooled Boiling Data From Rod Bundles

PDF

Topics: Boiling , Fuel rods , Subcooling , Heat transfer , Temperature , Fuels , Flow (Dynamics) , Heat flux , Modeling , Pressure

Feasibility Study on Thermal-Hydraulic Performance in Tight-Lattice Rod Bundles for Reduced-Moderation Water Reactors

Akira Ohnuki, Masatoshi Kureta, Wei Liu, Hidesada Tamai, Hajime Akimoto

ICONE 2004; 795-801https://doi.org/10.1115/ICONE12-49496

Abstract

View Articletitled, Feasibility Study on Thermal-Hydraulic Performance in Tight-Lattice Rod Bundles for Reduced-Moderation Water Reactors

PDF

Topics: Fuel rods , Water

Development of Quantitative Analytical Procedures on Two-Phase Flow in Tight-Lattice Fuel Bundles for Reduced-Moderation Light-Water Reactors

Kazuyuki Takae, Hiroyuki Yoshida, Masatoshi Kureta, Hidesada Tamai, Akira Ohnuki, Hajime Akimoto

ICONE 2004; 803-810https://doi.org/10.1115/ICONE12-49498

Abstract

View Articletitled, Development of Quantitative Analytical Procedures on Two-Phase Flow in Tight-Lattice Fuel Bundles for Reduced-Moderation Light-Water Reactors

PDF

Topics: Fuels , Light water reactors , Two-phase flow

Comparison of Realistic Large Break LOCA Analyses of a 3-Loop Westinghouse Plant Using Response Surface and Statistical Sampling Techniques

K. Muftuoglu, K. Ohkawa, C. Frepoli, M. Nissley

ICONE 2004; 811-818https://doi.org/10.1115/ICONE12-49499

Abstract

View Articletitled, Comparison of Realistic Large Break LOCA Analyses of a 3-Loop Westinghouse Plant Using Response Surface and Statistical Sampling Techniques

PDF

Topics: Response surface methodology , Sampling methods , Uncertainty , Emergency core cooling systems , Transients (Dynamics) , Accidents , Coolants , Probability , Regression models , Statistics

Detailed Investigation of Thermal-Hydraulic Aspects During the Reflood Phase in QUENCH Experiments

Christoph Homann, Wolfgang Hering, Alexei Miassoedov, Leo Sepold

ICONE 2004; 819-828https://doi.org/10.1115/ICONE12-49517

Abstract

View Articletitled, Detailed Investigation of Thermal-Hydraulic Aspects During the Reflood Phase in QUENCH Experiments

PDF

Topics: Accidents , Computation , Damage , Drops , Engineering standards , Flow (Dynamics) , Fluids , Inspection , Instrumentation , Light water reactors

Simulation of Containment Thermal-Hydraulic Transients in Different Experimental Facilities With the CONTAIN Code

Ivo Kljenak, Borut Mavko

ICONE 2004; 829-835https://doi.org/10.1115/ICONE12-49533

Abstract

View Articletitled, Simulation of Containment Thermal-Hydraulic Transients in Different Experimental Facilities With the CONTAIN Code

PDF

Topics: Condensation , Containment , Simulation , Transients (Dynamics)

A Hybrid Solution Method for the Two-Phase Fluid Flow Equations

Vincent A. Mousseau

ICONE 2004; 837-846https://doi.org/10.1115/ICONE12-49536

Abstract

View Articletitled, A Hybrid Solution Method for the Two-Phase Fluid Flow Equations

PDF

Topics: Algorithms , Fluid dynamics , Heat conduction , Partial differential equations , Two-phase flow

An Experimental Study on Coolability of Particulate Core-Metal Debris Bed With Oxidization

H. Aoki, K. Sugiyama, G. H. Su, H. Sakashita, Y. Kojima

ICONE 2004; 847-852https://doi.org/10.1115/ICONE12-49557

Abstract

View Articletitled, An Experimental Study on Coolability of Particulate Core-Metal Debris Bed With Oxidization

PDF

Topics: Metals , Particulate matter , Eutectic alloys , Temperature , Water , Heat , Electromagnetic induction , Heat flux , Heating , Melting point

Dynamic PIV Measurement of High-Speed Mist Flow

Masaaki Ishikawa, Seong-Dae Hong, Koji Okamoto, Haruki Madarame

ICONE 2004; 853-858https://doi.org/10.1115/ICONE12-49562

Abstract

View Articletitled, Dynamic PIV Measurement of High-Speed Mist Flow

PDF

Topics: Flow (Dynamics) , Electrons , Jets , Lasers , Particulate matter

Materials Interaction Tests to Identify Base and Coating Materials for an Enhanced In-Vessel Core Catcher Design

J. L. Rempe, D. L. Knudson, K. G. Condie, W. D. Swank, K. Y. Suh, F.-B. Cheung, S.-B. Kim

ICONE 2004; 859-869https://doi.org/10.1115/ICONE12-49579

Abstract

View Articletitled, Materials Interaction Tests to Identify Base and Coating Materials for an Enhanced In-Vessel Core Catcher Design

PDF

Topics: Accidents , Coatings , Design , Vessels

Wavelet Analysis on Eddy Structure in Micro Bubble Two Phase Flow Using PIV

Ling Zhen, Claudia del Carmen Gutierrez-Torres

ICONE 2004; 871-874https://doi.org/10.1115/ICONE12-49585

Abstract

View Articletitled, Wavelet Analysis on Eddy Structure in Micro Bubble Two Phase Flow Using PIV

PDF

Topics: Eddies (Fluid dynamics) , Microbubbles , Two-phase flow , Wavelets , Turbulence , Drag reduction , Boundary layers , Vortices , Containment , Drag (Fluid dynamics)

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