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Proceedings Papers

Proceedings Volume Cover
17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
  • Nuclear Engineering Division
ISBN:
978-0-7918-4352-9
Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications

Structural Integrity

Development of a New Spacer Grid Form to Enhance the Integrity of Fuel Rod Support and the Crush Strength of a Spacer Grid Assembly
Kee-nam Song, Soo-bum Lee, Moon-Kyun Shin, Jae-Jun Lee, Gyung-Jin Park
ICONE 2009; 1-9https://doi.org/10.1115/ICONE17-75008
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Topics: Fuel rods , Manufacturing , Optimization
A Comparative Parametric Study of Single Step and Double Step Swage Autofrettage in Swaged Metal Tubes
Azaal M. Malik, Shahab Khushnood, Muddasar Khan, Ghulam Gilani, Musarrat Khan
ICONE 2009; 11-16https://doi.org/10.1115/ICONE17-75081
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Topics: Autofrettage , Metals , Computer software , Finite element analysis , Computer programming , Design , Cylinders , Diesel engines , Failure , Fatigue life
Investigation of Discrepancies in Waterhammer Structural Integrity Analysis Simulation and Actual Vibration Testing
Khalid Chaudhry, Andrei Blahoianu
ICONE 2009; 17-28https://doi.org/10.1115/ICONE17-75100
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Topics: Simulation , Testing , Vibration , Pipes , Displacement , Friction , Stress , ASME Standards , Simulation results , Damping
Reactor Vessel Closure Head Drop Analysis: Sensitivity Study on the Effects of Representing Nonlinear Behavior in the Closure Head Assembly
William C. Castillo, Joseph M. Remic, III, George J. Demetri, Frank J. Marx, David H. Roarty
ICONE 2009; 29-36https://doi.org/10.1115/ICONE17-75170
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Topics: Manufacturing , Reactor vessels , Failure , Nuclear power stations , Cranes , Cavities , Cooling systems , Deflection , Deformation , Missiles
Use of Shear Lugs for Anchorage to Concrete
Peter J. Carrato, Martin Reifschneider
ICONE 2009; 37-44https://doi.org/10.1115/ICONE17-75175
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Topics: Anchorage , Concretes , Shear (Mechanics) , Design , Design methodology , Nuclear power stations , Stress , Construction , Nuclear construction , Structural design
Detailed Engineering Customization: A Cost and Time Effective Approach in the Manufacturing of Steel Structures
Ajaz Bashir Janjua, M. Shahid Khalil, Sajjad Akbar
ICONE 2009; 45-52https://doi.org/10.1115/ICONE17-75194
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Topics: Manufacturing , Optimization , Steel
Simulation of Vessel-With-Melt Deformation by SOCRAT/HEFEST Code
Alexander Filippov, Nikolay Drobyshevsky, Arkady Kisselev, Valery Strizhov
ICONE 2009; 53-60https://doi.org/10.1115/ICONE17-75203
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Topics: Deformation , Simulation , Vessels , Simulation results , Creep , Failure , Finite element analysis , High temperature creep , Pressurized water reactors , Reactor vessels
Assessment of Hill-Side Effect on RV CEDM Nozzles
Seung-Bum Ryu, Moon-kil Park, Byeong-Wook Noh, Jung-hun Lee
ICONE 2009; 61-66https://doi.org/10.1115/ICONE17-75224
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Topics: Nozzles , Stress , Domes (Structural elements) , Fittings , Neutrons , Nuclear fission , Nuclear power stations , Reactor vessels , Shrinkage (Materials) , Stress concentration
Modeling and Simulation of Multi-Stage Autofrettage in Pressure Vessels
Afzaal M. Malik, Shahab Khushnood, Ghulam Gilani, Muddasar Khan, Musarrat Khan
ICONE 2009; 67-74https://doi.org/10.1115/ICONE17-75225
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Topics: Autofrettage , Modeling , Pressure vessels , Simulation , Cylinders , Aircraft , Automobiles , Computer software , Cutting , Fatigue life
Evaluation on the Behavior of Stacked Blocks Subject to a Harmonic Excitation
Woo-Seok Choi, Dong-Ok Kim, Keun-Bae Park, Jae-Man Noh, Won-Jae Lee
ICONE 2009; 75-80https://doi.org/10.1115/ICONE17-75300
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Topics: Excitation , Computer software , Design , Finite element analysis , Graphite , Seismic analysis , Very high temperature reactors
On Design Verification of Piping Supports Under Combined Stresses
Lennart G. Jansson, Lingfu Zeng
ICONE 2009; 81-87https://doi.org/10.1115/ICONE17-75310
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Topics: Design , Pipes , Stress , Steel
Natural Crack Growth in BWR Shroud Support Dissimilar Metal Weld Joints
S. F. Hankinson, T. Hayashi, C. K. Ng, S. A. Swamy
ICONE 2009; 89-95https://doi.org/10.1115/ICONE17-75330
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Topics: Boiling water reactors , Fracture (Materials) , Metals , Shapes , Stress , Simulation , Alloys , Finite element analysis , Fracture mechanics , Geometry
The Use of Stochastic Models to Measure Damage Potential in Acceleration Time Series
Malek Brahimi, Sidi Berri, Abdelrazak Menasseri, Abdelrachid Boulaouad
ICONE 2009; 97-100https://doi.org/10.1115/ICONE17-75349
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Topics: Damage , Time series , Earthquakes , Spectra (Spectroscopy) , Displacement , Ductility
Design by Analysis of Waste Packages at Yucca Mountain for Impact Loads
Randy J. James, Kenneth Jaquay, Michael J. Anderson
ICONE 2009; 101-111https://doi.org/10.1115/ICONE17-75355
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Topics: Design , Stress , Radioactive wastes , Collisions (Physics) , Containers , Containment , Earthquakes , Engineering simulation , Rocks , Shells
FE Simulation of Welding Residual Stresses in Reactor Vessel Head Penetrations
Anne Teughels, Christian Malekian
ICONE 2009; 113-122https://doi.org/10.1115/ICONE17-75433
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Topics: Reactor vessels , Residual stresses , Simulation , Welding , Alloys , Vessels , Transients (Dynamics) , Cracking (Materials) , Finite element analysis , Finite element model
Acoustic Loading of Steam Dryers: Load Attributes and Structural Response
Michael Shehane, Eric M. Moore, Arthur E. Ruggles
ICONE 2009; 123-130https://doi.org/10.1115/ICONE17-75436
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Topics: Dryers , Sound pressure , Steam , Stress , Acoustics , Boiling water reactors , Dynamic testing (Materials) , Fatigue cracks , Physics , Signals
Stress Intensity Factors for Unusual Semi-Elliptical Surface Cracks With Ratio a/l Greater Than 0.5
Christian Malekian, Eric Wyart, Michael Savelsberg, David Lacroix, Anne Teughels, Nicolas Minjauw, Audrey Wendling
ICONE 2009; 131-141https://doi.org/10.1115/ICONE17-75441
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Topics: Stress , Surface cracks , Fracture (Materials) , Finite element analysis , Shapes , Corrosion , Fatigue , Finite element methods , Fracture mechanics , Plates (structures)
Evaluation of the Isolation System Influence in the Seismic Loading Analysis Applied to a Near Term Deployment Reactor
R. Lo Frano, G. Forasassi
ICONE 2009; 143-151https://doi.org/10.1115/ICONE17-75459
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Topics: Dampers , Design , Earthquake risk , Earthquakes , Energy dissipation , Finite element analysis , Nuclear power stations , Nuclear reactors , Safety , Seismic analysis
Nonlinear Analyses for Thermal Cracking in the Design of Concrete Structures
Randy J. James, Ai-Shen Liu
ICONE 2009; 153-160https://doi.org/10.1115/ICONE17-75474
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Topics: Concretes , Cracking (Materials) , Design , Fracture (Process) , Stress , Concrete cracking , Containment , Design methodology , Modeling , Reinforced concrete
Contribution to the Design of Concrete Columns Reinforced With Externally Fiber Polymers
Ferran Prats Bella, Ramo´n Gonza´lez-Drigo, Adrina Bachiller San˜a
ICONE 2009; 161-169https://doi.org/10.1115/ICONE17-75526
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Topics: Concrete columns , Design , Fibers , Polymers , Nuclear power stations , Structures , Concretes , Earthquakes , Momentum , Structural design
Stress Classification Plane and Its Application in Finite Element Analysis
Jianfeng Yang
ICONE 2009; 171-179https://doi.org/10.1115/ICONE17-75547
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Topics: Finite element analysis , Stress , Design , Pressure vessels , Boilers , Cutting , Finite element model , Mechanical engineers , Membranes , Stress concentration
An Approach for Assessing Fuel Assembly’s Structural Integrity Under In-Core Operating Conditions Using Finite Element Method
Wei Zhao, Yuriy Aleshin
ICONE 2009; 181-186https://doi.org/10.1115/ICONE17-75565
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Topics: Finite element methods , Fuels , Stress , Design , Finite element analysis , Irradiation (Radiation exposure) , Springs , Structural elements (Construction) , Absorption , Creep
Analytical Investigation of Deaerator Steam Inlet Nozzle Corrosion Allowance in a CANDU Station
Ali Keshavarz, Andrew K. Ali, Randy K. Lall
ICONE 2009; 187-195https://doi.org/10.1115/ICONE17-75617
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Topics: Clearances (Engineering) , Corrosion , Nozzles , Steam , Metals , Stress , Stress analysis (Engineering) , Carbon steel , Design , Errors
Friction Welding of Mild Steel Components
Sajjad Akbar, M. Shahid Khalil, A. Bashir Janjua, M. Amin
ICONE 2009; 197-204https://doi.org/10.1115/ICONE17-75649
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Topics: Friction welding , Mechanical testing , Steel
Sensitivity Analysis by the Use of a Surrogate Model During Large Break LOCA on ZION Nuclear Power Plant With CATHARE-2 V2.5 Code
Fabrice Fouet, Pierre Probst
ICONE 2009; 205-212https://doi.org/10.1115/ICONE17-75661
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Topics: Nuclear power stations , Response surface methodology , Sensitivity analysis , Simulated annealing
Wave Propagation Analysis of Piping Structures
Akemi Nishida
ICONE 2009; 213-219https://doi.org/10.1115/ICONE17-75760
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Topics: Pipes , Wave propagation , Accidents , Modeling , Nuclear power stations , Piping systems , Timoshenko beam theory , Vibration
The Development of Impact Analysis Methodology for CEDM Missile of APR1400
Tae Kyo Kang, Jin Seok Park, Hyun Min Kim, In Yong Kim
ICONE 2009; 221-228https://doi.org/10.1115/ICONE17-75797
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Topics: Missiles , Flow (Dynamics) , Design , Nozzles , Earthquakes , Equilibrium (Physics) , Kinetic energy , Manufacturing , Reactor vessels , Structural response analysis
A Study of Some Key Parameters Used in the Environmental Fatigue Evaluation of a Hot Leg Surge Nozzle
Tim F. Wiley, Tim J. Pournaras, Chris T. Kupper, Mark A. Gray, Seth A. Swamy
ICONE 2009; 229-234https://doi.org/10.1115/ICONE17-75804
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Topics: Fatigue , Nozzles , Surges , Pressurized water reactors , Electric arc furnaces , Cycles , Design , Fatigue analysis , Nuclear power stations , Nuclear reactor coolants
Review of Recent Aging-Related Degradation Occurrences of Structures and Passive Components in U.S. Nuclear Power Plants
Jinsuo Nie, Joseph I. Braverman, Charles H. Hofmayer, Young-Sun Choun, Min Kyu Kim, In-Kil Choi
ICONE 2009; 235-244https://doi.org/10.1115/ICONE17-75814
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Topics: Nuclear power stations , Anchorage , Computer software , Concretes , Containment , Filters , Nuclear power , Piping systems , Reactor vessels , Structural steel
Evaluation of Load-Time Functions Due to Impact of Soft Missiles
Daniela Ruch, Nico Herrmann, Harald S. Mu¨ller
ICONE 2009; 245-252https://doi.org/10.1115/ICONE17-75825
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Topics: Missiles , Stress , Aircraft , Accelerometers , Computer simulation , Finite element analysis , Peak load , Pressure , Safety , Shapes
Engineering Practices for Tokamak Window Assemblies
C. Waldon, R. Morrell, D. Buckthorpe, M. Davies, P. Sherlock
ICONE 2009; 253-263https://doi.org/10.1115/ICONE17-75858
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Topics: Tokamaks , Design , Safety , Ceramics , Failure , Industrial ceramics , Nonmetallic materials , Plasmas (Ionized gases) , Brittleness , Containment
Sensitivity Investigation of Specimen Shape on Elastic Behaviour of Perforated Plate
Chang-Hoon Ha, Tae-Jung Park, Moo-Yong Kim, Kwang-Sang Seon, Jae-Mean Koo, Chang-Sung Seok
ICONE 2009; 265-272https://doi.org/10.1115/ICONE17-75916
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Topics: Elasticity , Shapes , Compression , Finite element analysis , Computer software , Plates (structures) , Boilers , Elastic moduli , Poisson ratio , Preferences
A Study for the Practicality of the 3D Full Model in the SSI Analysis on the Nuclear Power Plant
Youngsun Jang, Taeyoung Kim, Jongbo Lee, Jonghak Kim
ICONE 2009; 273-279https://doi.org/10.1115/ICONE17-76002
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Topics: Nuclear power stations , Soil , Modeling , Design , Licensing , Uncertainty
Critical Velocity of Potential Flow in Interaction With a System of Plates
Y. Kerboua, A. A. Lakis, M. Thomas, L. Marcouiller, M. H. Toorani
ICONE 2009; 281-289https://doi.org/10.1115/ICONE17-76059
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Topics: Flow (Dynamics) , Plates (structures) , Fluids , Displacement , Boundary-value problems , Equations of motion , Pressure , Stiffness , Damping , Dynamic response

Safety and Security

Research of Nuclear Power Plants Diagnosis Method Based on Data Fusion
Yong-kuo Liu, Hong Xia, Chun-li Xie
ICONE 2009; 291-295https://doi.org/10.1115/ICONE17-75019
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Topics: Data fusion , Fault diagnosis , Nuclear power stations
Seismic Isolation of Nuclear Structures by a Non-Oscillating System SERB Type
Viorel Serban, Adrian Panait, Marian Androne, George Alexandru Ciocan
ICONE 2009; 297-306https://doi.org/10.1115/ICONE17-75022
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Topics: Compression , Damping , Deflection , Displacement , Friction , Nuclear power stations , Shock (Mechanics) , Sliding friction , Soil , Stiffness
Approach on Component Selection for Ageing-Trend Analysis Within PSA Models
Shahen Poghosyan, Armen Amirjanyan, Albert Malkhasyan
ICONE 2009; 307-311https://doi.org/10.1115/ICONE17-75029
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Topics: Damage , Nuclear power stations , Risk , Risk-based decision making , Trend analysis
Modelling of Material Properties Influence in Fuel-Coolant Interaction Codes
Mitja Ursˇicˇ, Matjazˇ Leskovar, Ivo Kljenak, Borut Mavko
ICONE 2009; 313-321https://doi.org/10.1115/ICONE17-75039
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Topics: Coolants , Fuels , Materials properties , Modeling , Drops , Explosions , Steam , Approximation , Cooling , Heat transfer
On the Use of Binary Importance Decision for Risk-Informed Categorization of SSCs
Wei Zeng, Hongxing Yu
ICONE 2009; 323-329https://doi.org/10.1115/ICONE17-75071
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Topics: Risk
Water-Ingress Accident of the 250MW Pebble-Bed Modular High Temperature Gas-Cooled Reactor
Zheng Yanhua, Shi Lei
ICONE 2009; 331-339https://doi.org/10.1115/ICONE17-75078
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Topics: Accidents , Corrosion , Graphite , Natural convection , Very high temperature reactors , Water
Analysis of the Quench-14 Bundle Test With M5® Cladding
Jonathan C. Birchley, Bernd Jaeckel, Timothy J. Haste, Martin Steinbrueck, Juri Stuckert
ICONE 2009; 341-348https://doi.org/10.1115/ICONE17-75099
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Topics: Cladding systems (Building) , Fuel rods , Oxidation , Pressurized water reactors , Accidents , Alloys , Fuels , Geometry , Quenching (Metalworking) , Transients (Dynamics)
The Limit Exceedance Factor Importance Measure: An Application to the Prism Reactor Design
B. C. Johnson, G. E. Apostolakis
ICONE 2009; 349-353https://doi.org/10.1115/ICONE17-75128
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Topics: Design , Risk , Failure , Probability , Crude oil , Damage , Economics , Probabilistic risk assessment , Risk reduction , Safety
Validation of Calculated Skyshine Dose From Turbine Building by Using MCNP5 With Experimental Data at Shimane Nuclear Power Station
Ryuichi Tayama, Kenichi Wakasugi, Ikunori Kawanaka, Yoshinobu Kadota, Yasuhiro Murakami
ICONE 2009; 355-359https://doi.org/10.1115/ICONE17-75145
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Topics: Nuclear power stations , Turbines , Structures , Boiling water reactors , Concretes , Radiation (Physics) , Roofs
Numerical Simulation of the Behavior of Fission Products in the Primary Circuit of the VVER During the LOCA Severe Accident
S. V. Tsaun, V. V. Bezlepkin, A. E. Kiselev, I. A. Potapov, V. F. Strizhov, L. I. Zaichik
ICONE 2009; 361-367https://doi.org/10.1115/ICONE17-75159
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Topics: Accidents , Circuits , Computer simulation , Nuclear fission , Nuclear power stations , Evaporation , Aerosols , Condensation , Containment , Coolants
Vulnerability of Nuclear Power Plants to Voltage Sag Induced by Disturbances in the Transmission Grid: The Concept of Zone of Vulnerability for Voltage
Nick Abi-Samra, Alberto Del Rosso, Frank Rahn
ICONE 2009; 369-378https://doi.org/10.1115/ICONE17-75177
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Topics: Nuclear power stations , Safety , Buses , Diesel generators , Emergencies , Power grids , Risk , Security , Separation (Technology)
Verification of Modified SCDAP/RELAP5 Against CANDU Fuel Deformation Experimental Results
Mirea Mladin, Daniel Dupleac, Ilie Prisecaru
ICONE 2009; 379-385https://doi.org/10.1115/ICONE17-75196
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Topics: Deformation , Fuels , Accidents , Cooling , Flow (Dynamics) , Geometry , Hydrogen , Pressure , Solidification , Steam
Analysis of Rod Ejection Accident in a Research Reactor by the Coupled Technique
Tewfik Hamidouche, El Khider Si-Ahmed, Anis Bousbia-Salah, Jack Legrand
ICONE 2009; 387-393https://doi.org/10.1115/ICONE17-75211
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Topics: Accidents , Safety , Computers , Diffusion (Physics) , Neutrons , Nuclear reactors , Steady state
Natural Circulation and Creep Damage Analyses of Severe Accident for a Typical PWR Plant
Osamu Kawabata, Masao Ogino
ICONE 2009; 395-402https://doi.org/10.1115/ICONE17-75219
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Topics: Accidents , Creep , Damage , Pressurized water reactors
Analytical Evaluation of Core Bowing Reactivity in the 4S Reactor
Satoshi Nishimura, Hirokazu Ohta, Nobuyuki Ueda
ICONE 2009; 403-411https://doi.org/10.1115/ICONE17-75223
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Topics: Absorption , Displacement , Fast neutron reactors , Feedback , Flow (Dynamics) , Neutrons , Optical mirrors , Sodium
Protection and Monitoring of Ionizing Radiation - Nuclear Medicine
Sajjad Akbar, M. Shahid Khalil, Shahzad Ahmad
ICONE 2009; 413-420https://doi.org/10.1115/ICONE17-75227
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Topics: Biomedicine , Ionizing radiation
Preliminary Analysis of Effect of the Intentional Depressurization on Fission Product Behavior During TMLB’ Severe Accident
Gaofeng Huang, Lili Tong, Xuewu Cao
ICONE 2009; 421-425https://doi.org/10.1115/ICONE17-75239
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Topics: Accidents , Nuclear fission
Implementation of a Pressure Drop Model for the CFD Simulation of Clogged Containment Sump Strainers
Alexander Grahn, Eckhard Krepper, Frank-Peter Weiß, So¨ren Alt, Wolfgang Ka¨stner, Alexander Kratzsch, Rainer Hampel
ICONE 2009; 427-438https://doi.org/10.1115/ICONE17-75249
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Topics: Computational fluid dynamics , Containment , Pressure drop , Simulation , Fibers , Particulate matter , Porosity , Accidents , Compacting , Coolants
Successive Accident Frequency Assessment From Initiating Event to Containment Failure
Naoki Hirokawa, Mitsuru Yoneyama, Chikahiro Sato
ICONE 2009; 439-444https://doi.org/10.1115/ICONE17-75252
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Topics: Accidents , Containment , Failure , Damage , Boiling water reactors , Computers , Evaluation methods , Uncertainty analysis
Evaluation of Monju Core Damage Risk With Change of AOT Using Probabilistic Method
Masutake Sotsu, Kenichi Kurisaka
ICONE 2009; 445-453https://doi.org/10.1115/ICONE17-75263
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Topics: Breeder reactors , Cooling , Damage , Engineering prototypes , Regulations , Risk , Safety , Sodium
Experimental Results of Reflood Bundle Test QUENCH-14 With M5® Cladding Tubes
Juri Stuckert, Mirco Große, Leo Sepold, Martin Steinbru¨ck
ICONE 2009; 455-461https://doi.org/10.1115/ICONE17-75266
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Topics: Cladding systems (Building) , Oxidation , Rods , Temperature , Corners (Structural elements) , Alloys , Hydrogen , Cooling , Electricity (Physics) , Heat
Network Computing Infrastructure to Share Tools and Data in GNEP
Guehee Kim, Yoshio Suzuki, Naoya Teshima
ICONE 2009; 463-470https://doi.org/10.1115/ICONE17-75304
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Topics: Collaboration , Design , Encryption , Engineering prototypes , Gates (Closures) , Graphical user interfaces , Leakage , Nuclear power , Security
A New Simulation Code for Analyzing Loss of Coolant Accidents in VVER-440/213 Reactors Concerning Activity Transport
Attila Madaras, Sa´ndor Deme, Zolta´n Ho´zer, Edit La´ng, Istva´n Ne´meth, Tama´s Pa´zma´ndi, Pe´ter Sza´nto´
ICONE 2009; 471-476https://doi.org/10.1115/ICONE17-75306
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Topics: Accidents , Alpha decay , Computers , Containment , Coolants , Design , Gas flow , Modeling , Nuclear fission , Nuclear power
On-Line Workload Assessment by the PET Method
Gueorgui Petkov, Vladislav Georgiev, Emil Stefanov
ICONE 2009; 477-481https://doi.org/10.1115/ICONE17-75352
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Topics: Accidents , Containment , Human reliability analysis , NASA , Nuclear power stations , Performance evaluation , Rupture , Steam
Sources of Uncertainty in a Fire Probabilistic Safety Assessment
Stephen P. Meyer
ICONE 2009; 483-486https://doi.org/10.1115/ICONE17-75360
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Topics: Fire , Probabilistic safety assessment , Uncertainty , Cables , Probability , Safety , Failure , Model development , Modeling , Nuclear power stations
Analysis and Characterization of Sequences in Atucha II PHWR
Pablo Zanocco, Jose´ Gonzalez, Marcelo Gime´nez
ICONE 2009; 487-494https://doi.org/10.1115/ICONE17-75364
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Topics: Heavy water reactors , Heat , Temperature , Safety , Boilers , Coolants , Design , Heat exchangers , Heat sinks , Inertia (Mechanics)
RELAP Model for Atucha II PHWR
M. Schivo, G. Bedrossian, J. Gonza´lez, P. Zanocco, M. Gime´nez, M. Caputo, P. Serrano, O. Mazzantini
ICONE 2009; 495-503https://doi.org/10.1115/ICONE17-75365
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Topics: Heavy water reactors , Construction , Design , Geometry , Licensing , Probabilistic safety assessment , Steady state
Safety Aspects of a PWR With an Inventive TRISO Fuel Particle Composition
Anwar Hussain, Xinrong Cao
ICONE 2009; 505-509https://doi.org/10.1115/ICONE17-75384
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Topics: Fuels , Heating , Particulate matter , Pressurized water reactors , Rods , Safety
Investigation of Chemical Effects on Emergency Core Cooling Filtration Head Loss After Loss of Coolant Accident
Jong Woon Park, Byung Gi Park, Chang Hyun Kim
ICONE 2009; 511-518https://doi.org/10.1115/ICONE17-75398
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Topics: Accidents , Coolants , Cooling , Emergencies , Filtration , Aluminum , Filters , Sprays , Sodium , Building materials
ASTEC, COCOSYS, and LIRIC Interpretation of the Iodine Behaviour in the Large-Scale THAI Test Iod-9
G. Weber, L. Bosland, F. Funke, G. Glowa, T. Kanzleiter
ICONE 2009; 519-531https://doi.org/10.1115/ICONE17-75414
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Topics: Condensation , Desorption , Diffusion (Physics) , Domes (Structural elements) , Mass transfer , Modeling , Simulation results , Steel , Vessels , Water
Core Melt Solidification Characteristics in RPV Lower Head: Experimental Results From LIVE-Tests
Xiaoyang Gaus-Liu, Alexei Miassoedov, Thomas Cron, Jerzy Foit, Thomas Wenz, Silke Schmidt-Stiefel
ICONE 2009; 533-540https://doi.org/10.1115/ICONE17-75450
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Topics: Solidification , Cooling , Water , Vessels , Heat flux , Diluents , Reactor vessels , Steady state , Supercooling , Thermal conductivity
Analysis of a BWR ATWS With Boron Injection
Marcus Eriksson, Ulf Bredolt
ICONE 2009; 541-549https://doi.org/10.1115/ICONE17-75455
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Topics: Boiling water reactors , Boron , Transients (Dynamics) , Computers , Feedwater , Safety , Scram , Simulation
Ex-Vessel Coolability Analysis for a Belgian NPP
Jarne R. Verpoorten, Miche`le Auglaire, Frank Bertels
ICONE 2009; 551-561https://doi.org/10.1115/ICONE17-75456
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Topics: Nuclear power stations , Vessels , Cooling , Accident management , Accidents , Cavities , Damage , Failure , Hardware , Thermomechanics
Approach for the Analysis of a Shutdown Scenario in the Framework of the Validation of Severe Accident Management Guidelines in Belgium
Antonio Cipollaro, Laurent Sallus
ICONE 2009; 563-573https://doi.org/10.1115/ICONE17-75457
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Topics: Accident management , Accidents , Coolants , Emergencies , Heat , Teams , Accounting , Boilers , Containment , Control rooms
A Hybrid Qualitative/Quantitative Uncertainty Importance Assessment Approach: Applications to Thermal-Hydraulics System Codes Calculations
Mohammad Pourgol-Mohammad, Kamran Sepanloo
ICONE 2009; 575-581https://doi.org/10.1115/ICONE17-75464
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Topics: Thermal hydraulics , Uncertainty , Uncertainty quantification
Validation of Severe Accident Management Guidance in Belgium
Laurence Oury, Zeynab Umidova, Miche`le Auglaire, Antonio Cipollaro
ICONE 2009; 583-592https://doi.org/10.1115/ICONE17-75472
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Topics: Accident management , Safety , Accidents , Nuclear power stations , Feedback , Containment , Control rooms , Drills (Tools) , Sprays , Teams
Fire PRA Database Development and Applications
Chris Rochon, Barbara R. Baron, Clarence L. Worrell, Mark A. Ferrel
ICONE 2009; 593-599https://doi.org/10.1115/ICONE17-75517
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Topics: Databases , Fire , Nuclear power stations , Power stations , Probabilistic risk assessment
New Approach for Environmental Protection During Severe Accidents at Nuclear Power Plants
S. A. Kulyukhin, N. B. Mikheev, L. N. Falkovskii, L. A. Reshetov, M. Ya. Zvetkova, V. P. Osipov, I. V. Yagodkin, S. S. Skvortsov, V. M. Berkovich, G. S. Taranov, M. M. Grigor’ev, A. A. Noskov, M. I. Mitrofanov, V. M. Meshkov
ICONE 2009; 601-609https://doi.org/10.1115/ICONE17-75518
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Topics: Accidents , Nuclear power stations , Decontamination , Pressure , Sorption , Steam , Condensers (steam plant) , Containment , Ejectors , Filtration
Quantification of the RELAP5 Model Uncertainty for Application to the Loss-of-RHR Event During the Mid-Loop Operation
Ikuo Kinoshita, Hiroichi Nagumo, Minoru Yamada, Yasuhiro Sasaki, Yoshitaka Yoshida
ICONE 2009; 611-621https://doi.org/10.1115/ICONE17-75550
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Topics: Uncertainty , Heat transfer , Condensation , Cooling , Flow (Dynamics) , Safety , Stratified flow , Water , Boilers , Boiling
Closed Model for Calculation of Differential Pressure After a Loss of Coolant Accident in Boiling Water Reactors
Alexander Kratzsch, Wolfgang Ka¨stner, Rainer Hampel
ICONE 2009; 623-628https://doi.org/10.1115/ICONE17-75562
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Topics: Accidents , Boiling water reactors , Coolants , Pressure , Containment , Heat , Insulation , Exhaust systems , Condensation , Cooling systems
Improvements in the German Fire PSA Methodology Demonstrated at a German BWR Built to Earlier Standards
M. Ro¨wekamp, O. Riese, H. P. Berg
ICONE 2009; 629-637https://doi.org/10.1115/ICONE17-75595
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Topics: Boiling water reactors , Fire , Nuclear power stations , Damage , Uncertainty , Cables , Circuits , Engineering simulation , Failure , Probabilistic safety assessment
Reliability Analysis by Multilevel Flow Models: A Qualitative Analysis Method and Its Application for FTA Validation
Ming Yang, Zhijian Zhang, Jie Liu, Shengyuan Yan
ICONE 2009; 639-648https://doi.org/10.1115/ICONE17-75681
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Topics: Event history analysis , Flow (Dynamics) , Safety , Algorithms , Modeling , Complex systems , Failure mechanisms , Reliability
A Bayesian Framework for Model Uncertainty Considerations in Fire Simulation Codes
Mohammadreza Azarkhail, Victor Ontiveros, Mohammad Modarres
ICONE 2009; 649-656https://doi.org/10.1115/ICONE17-75684
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Topics: Fire , Simulation , Uncertainty , Hazards , Chain , Chemical processes , Computers , Errors , Failure , Instrumentation
Break-Up of Gas Stratification in LWR Containment Induced by Negatively Buoyant Jets and Plumes
Ralf Kapulla, Domenico Paladino, Guillaume Mignot, Robert Zboray, Sanjeev Gupta
ICONE 2009; 657-666https://doi.org/10.1115/ICONE17-75708
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Topics: Containment , Jets , Light water reactors , Plumes (Fluid dynamics) , Steam , Helium , Hydrogen , Pipes , Accidents , Condensation
Safety Analysis of the Control Rod Drop Event Applying 3-D Neutronics/Thermal-Hydraulics Coupling Code SPARKLE
Yuta Maruyama, Satoshi Imura, Junto Ogawa, Shuhei Miyake
ICONE 2009; 667-676https://doi.org/10.1115/ICONE17-75729
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Topics: Safety , Thermal hydraulics , Rods , Neutron flux , Pressurized water reactors , Steam , Transient analysis
Lessons Learned and Insights From Implementation of EPRI Guidelines on Internal Flooding at Fort Calhoun Station
Daniel L. Sadlon, Rupert A. Weston, Raymond E. Schneider, John J. Fluehr, III, Harold A. Hackerott
ICONE 2009; 677-683https://doi.org/10.1115/ICONE17-75805
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Topics: Floods , Fortification , Nuclear power stations , Risk , Combustion engineering , Failure , Maintenance , Optimization , Pipes , Probabilistic risk assessment
The Gasification of Graphite Matrix in Pebble Bed Reactors
Xinli Yu, Suyuan Yu
ICONE 2009; 685-690https://doi.org/10.1115/ICONE17-75827
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Topics: Fuel gasification , Graphite , Fuels , Corrosion , Steam , Engineering simulation , Simulation , Very high temperature reactors , Coolants , Helium
Potential Ways to Modify the NRC Safety Goal Policy
Steven A. Arndt, Richard Denning
ICONE 2009; 691-697https://doi.org/10.1115/ICONE17-75852
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Topics: Safety , Nuclear reactors , Risk , Damage , Electric power generation
Human Reliability, Experience and Error Probability: A New Benchmark
Romney B. Duffey, Tae Sung Ha
ICONE 2009; 699-704https://doi.org/10.1115/ICONE17-75861
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Topics: Errors , Probability , Reliability , Human reliability analysis , Accidents , Transients (Dynamics) , Performance , Risk , Uncertainty
MELCOR/VISOR PWR Desktop Simulator for Accident Analysis and Training
Anka de With, Pieter H. Wakker, Marcel L. F. Slootman
ICONE 2009; 705-712https://doi.org/10.1115/ICONE17-75881
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Topics: Accidents , Pressurized water reactors , Safety
Lessons Learned in Reviewing CCF Events
Ashley Mossa, Rupert Weston
ICONE 2009; 713-717https://doi.org/10.1115/ICONE17-75887
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Topics: Databases , Equipment performance , Failure , Nuclear power stations , Pressurized water reactors , Probabilistic risk assessment
Gas Phase Oxidation of Elemental Iodine in Containment Conditions
Teemu Ka¨rkela¨, Joachim Holm, Ari Auvinen, Christian Ekberg, Henrik Gla¨nneskog, Unto Tapper, Riitta Zilliacus
ICONE 2009; 719-727https://doi.org/10.1115/ICONE17-75927
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Topics: Aerosols , Agglomeration (Materials) , Carbon , Containment , Copper , Filters , Flow (Dynamics) , Fourier transform infrared spectroscopy , Furnaces , Inductively coupled plasma mass spectrometry
Assessment of Reliability of Emergency Core Cooling System (ECCS) of Bushehr Nuclear Power Plant
Mohammad Sotoudeh, Kamran Sepanloo
ICONE 2009; 729-733https://doi.org/10.1115/ICONE17-75931
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Topics: Emergency core cooling systems , Event history analysis , Nuclear power stations , Reliability
Experimental Investigation of Non-Condensable Gases Effect on Novovoronezh NPP-2 Steam Generator Condensation Power Under the Condition of Passive Safety Systems Operation
I. I. Kopytov, S. G. Kalyakin, V. M. Berkovich, A. V. Morozov, O. V. Remizov
ICONE 2009; 735-743https://doi.org/10.1115/ICONE17-75942
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Topics: Boilers , Condensation , Gases , Nuclear power stations , Safety , Steam , Heat , Test facilities , Circuits , Flow (Dynamics)
Effects of Ruthenium Release in Oxidizing Conditions on a BWR Source Term
Atso Suopaja¨rvi, Teemu Ka¨rkela¨, Ari Auvinen, Ilona Lindholm
ICONE 2009; 745-749https://doi.org/10.1115/ICONE17-75946
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Topics: Boiling water reactors , Ruthenium , Accidents , Containment , Nuclear fission , Nuclear power stations , Oxygen , Pressure vessels , Steam , Surface roughness
Point Lepreau Refurbishment Project Level 2 PSA Applications
L. Comanescu, S. Sawh, M. Wei, B. Lee, A. Petrescu, A. Nainer, R. K. Jaitly, A. F. Jean, D. F. Basque, D. S. Mullin
ICONE 2009; 751-756https://doi.org/10.1115/ICONE17-75972
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Topics: Accidents , Damage , Design , Failure , Fire , Floods , Maintenance , Power stations , Probabilistic safety assessment , Risk
Westinghouse AP1000 Solution to Long-Term Cooling Debris Concerns
Terry L. Schulz, Timothy S. Andreychek, Yong J. Song, Kevin F. McNamee
ICONE 2009; 757-764https://doi.org/10.1115/ICONE17-76026
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Topics: Cooling , Containment , Accidents , Design , Pressurized water reactors , Coolants , Safety , Particulate matter , Testing , Construction
Best Estimate Simulation and Uncertainty Analysis of LB LOCA for KudanKulam VVER-1000 NPP
Luben Sabotinov, Abhishek Srivastava, Pierre Probst
ICONE 2009; 765-775https://doi.org/10.1115/ICONE17-76033
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Topics: Nuclear power stations , Simulation , Uncertainty analysis , Uncertainty , Safety , Computers , Accidents , Licensing , Modeling
Point Kinetics LOCA Scenarios Assessment at the Using of Hafnium Absorber in Advanced CANDU Fuel Designs
Iosif Prodea, Cristina Alice Ma˘rgeanu, Ilie Prisecaru, Nicolae Da˘nila˘
ICONE 2009; 777-784https://doi.org/10.1115/ICONE17-76042
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Topics: Fuels , Diffusion (Physics) , Safety , Shells , Simulation , Transients (Dynamics)
ACR-1000™ Level 1 PSA Summary
U. Menon, S. Aprodu, R. Bettig, R. Henderson, T. Ha, P. Iliescu, B. Karimi, M. El-Mansi, J. Robinson, K. Torabi, E. Eman, J. Wu, P. Santamaura
ICONE 2009; 785-791https://doi.org/10.1115/ICONE17-76048
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Topics: Accidents , Boilers , Containment , Containment systems , Coolants , Cooling systems , Damage , Design , Earthquakes , Economics

Advanced Applications of Nuclear Technology

Analysis for Digital Pulse Waveform Based on Cd (Zn) Te Detector
Yu-ming Di, Zhan-liang Li, Guo-ming Fang, Feng Han, Xiao-lin Qiu, Peng Xu, Yuelei Wu
ICONE 2009; 793-797https://doi.org/10.1115/ICONE17-75052
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Topics: Sensors , Signal processing
Characteristics and Operation of Neutron Transmutation Doping in HANARO Reactor
Sang-Jun Park, Myong-Seop Kim, Ki-Doo Kang, In-Cheol Lim
ICONE 2009; 799-806https://doi.org/10.1115/ICONE17-75141
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Topics: Neutrons , Silicon , Irradiation (Radiation exposure) , Semiconductors (Materials) , Nuclear power
Development of the CAD/MCNP Automatic Conversion Code GEOMIT
Hesham R. Nasif, Fukuzo Masuda, Hiromasa Iida, Hidetsugu Morota, Satoshi Sato, Chikara Konno
ICONE 2009; 807-814https://doi.org/10.1115/ICONE17-75229
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Topics: Computer-aided design , Shapes , Solids , Density , Errors , Heat
Allegro: The European Gas Fast Reactor Demonstrator Project
Christian Poette, Vale´rie Brun-Magaud, Franck Morin, Jean-Franc¸ois Pignatel, Richard Stainsby, Konstantin Mikityuk
ICONE 2009; 815-822https://doi.org/10.1115/ICONE17-75326
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Topics: Fast neutron reactors , Design , Ceramics , Fuels , Neutrons , Nuclear reactors , High temperature , Safety , Accidents , Circuits
Development of a New Monte-Carlo Treatment Planning System for Boron Neutron Capture Therapy
Hiroaki Kumada, Takemi Nakamura, Akira Matsumura, Koji Ono
ICONE 2009; 823-829https://doi.org/10.1115/ICONE17-75407
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Topics: Boron , Dosimetry , Neutrons , Patient treatment , Particulate matter , Radiation therapy , Protons , Accuracy and precision , Computation , Ions
Test Results From the Idaho National Laboratory 15kW High Temperature Electrolysis Test Facility
Carl M. Stoots, Keith G. Condie, James E. O’Brien, J. Stephen Herring, Joseph J. Hartvigsen
ICONE 2009; 831-841https://doi.org/10.1115/ICONE17-75417
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Topics: High temperature steam , Test facilities , High temperature , Hydrogen , Design , Heat , Feedstock , Heating , Hydrogen production , Solid oxide fuel cells
The 30 MeV Proton Beam Emittance Measurement via a Designed and Constructed Wire Scanner and Using WinAGILE Beam Transport Code
Mitra Ghergherehchi, Ahmad Mohammadzadeh, Hossein Afarideh
ICONE 2009; 843-846https://doi.org/10.1115/ICONE17-75434
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Topics: Proton beams , Wire , Cyclotrons , Patient treatment , Position control , Protons , Sensors , Stepper motors
System Analyses of High and Low-Temperature Interface Designs for a Nuclear-Driven High-Temperature Electrolysis Hydrogen Production Plant
E. A. Harvego, J. E. O’Brien, M. G. McKellar
ICONE 2009; 847-855https://doi.org/10.1115/ICONE17-75473
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Topics: High temperature steam , Hydrogen production , Low temperature , Systems analysis , Design , Heat pumps , Temperature , Heat , High temperature , Thermodynamic power cycles
Current Status and Performance of the J-PARC Accelerators
Hiroyuki Sako
ICONE 2009; 857-866https://doi.org/10.1115/ICONE17-75557
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Topics: Ceramics , Construction , Density , Design , Downtime , Ducts , Eddies (Fluid dynamics) , Eddy currents (Electricity) , Electromagnets , Life sciences
Design of CT Reconstruction Software Based on the Air Container CT Inspection System
Jinhui Liu, Xincheng Xiang, Zhifang Wu
ICONE 2009; 867-874https://doi.org/10.1115/ICONE17-75579
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Topics: Computer software , Containers , Design , Inspection , Noise (Sound) , Resolution (Optics) , Algorithms , Construction , Density , Gamma rays
The Coupling of Nuclear Heat and Hydrogen Production Thermochemical Cycles
Zhaolin Wang, Greg Naterer, Kamiel S. Gabriel, Rob Gravelsins, Venkata Daggupati
ICONE 2009; 875-883https://doi.org/10.1115/ICONE17-75702
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Topics: Cycles , Heat , Hydrogen production , Water
Advanced Studies on Plutonium for Pu Isotope Transmutation and Pu Separation
Ashraf Elsayed Mohamed Mohamed
ICONE 2009; 885-889https://doi.org/10.1115/ICONE17-75787
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Topics: Isotopes , Metals , Separation (Technology) , Gallium , Cycles , Equilibrium (Physics) , Oxidation , Spectra (Spectroscopy)
Evolving Innovative Reactor Design: Putting the I Into R&D
Romney B. Duffey, Hussam Khartabil
ICONE 2009; 891-895https://doi.org/10.1115/ICONE17-75811
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Topics: Design , Supercritical water reactors , Cycles , China , Collaboration , Fuels , Heat , Hydrogen production , Innovation , Metals
Non-Proliferative, Thorium-Based, Core and Fuel Cycle for Pressurized Water Reactors
Gilad Raitses, Michael Todosow, Alex Galperin
ICONE 2009; 897-904https://doi.org/10.1115/ICONE17-75898
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Topics: Nuclear fuel cycle , Pressurized water reactors , Spent nuclear fuels , Fuels , Cycles , Manufacturing , Design , Fuel management , Energy generation , Engineering teachers
Advanced Application of BNCT in Advanced Cancers
Manuel L. Sztejnberg, Tatjana Jevremovic
ICONE 2009; 905-914https://doi.org/10.1115/ICONE17-75906
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Topics: Cancer , Boron , Tumors , Lung , Biological tissues , Neutrons , Patient treatment , Computerized tomography , Design , Irradiation (Radiation exposure)
iMASS: Evolved NRF Simulations for More Accurate Detection of Nuclear Threats
John Perry, Shanjie Xiao, Tatjana Jevremovic
ICONE 2009; 915-921https://doi.org/10.1115/ICONE17-75907
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Topics: Engineering simulation , Simulation , Containers , Computers , Explosives , Fluorescence , Gates (Closures) , Resonance , Safety , Security
Optimization of Dead-Layer Thickness for a HPGe Detector Using UCODE-MCNP Codes
Noha Shaaban, Wael El Gammal, Hesham Nasif
ICONE 2009; 923-929https://doi.org/10.1115/ICONE17-75939
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Topics: Optimization , Sensors , Crystals , Building materials , Calibration , Modeling , Simulation , Statistics
Why Massive Nuclear Deployment is Essential
Alistair I. Miller, Romney B. Duffey
ICONE 2009; 931-935https://doi.org/10.1115/ICONE17-75949
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Topics: Carbon capture and storage , Carbon dioxide , Climate change , Cycles , Density , Disasters , Emissions , Energy generation , Geothermal engineering , Governments
Experimental and Research Study of Novel Nuclear Concepts (Survey of Current Results of ISTC Programs)
L. V. Tocheny
ICONE 2009; 937-943https://doi.org/10.1115/ICONE17-76031
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Topics: Collaboration , Safety , Weapons

Balance of Plant for Nuclear Applications

STP Balance of Plant Model Update Experience and Results
Ernie Kee, Fatma Yilmaz, Don Wakefield, Steve Epstein
ICONE 2009; 945-953https://doi.org/10.1115/ICONE17-75006
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Topics: Computer software , Damage , Financial risk , Modeling , Probabilistic risk assessment , Profitability , Reliability , Risk , Risk analysis , Risk management
A Lifecycle Management Program for NPP Turbine Balance of Plant
Toshinari Kawai, Katsuhiko Yamakami, Satoshi Hiraoka, Jun Manabe
ICONE 2009; 955-963https://doi.org/10.1115/ICONE17-75087
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Topics: Adhesion , Design , Life cycle management , Nuclear power stations , Turbines , Water treatment
Equipment Reliability Based Ageing and Lifetime Management for Asco´ and Vandello´s Nuclear Power Plants
Xavier Jardi´, Miguel Garci´a, Xavier Castelo, Luis Marti´nez, Isabel Mach
ICONE 2009; 965-973https://doi.org/10.1115/ICONE17-75406
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Topics: Nuclear power stations , Reliability , Public utilities , Safety , Design , Engines , Life extension , Maintenance , Motors , Service life (Equipment)
Global Balance of Plant Using Process Data Reconciliation According to VDI2048
Magnus Langenstein, Bernd Laipple
ICONE 2009; 975-981https://doi.org/10.1115/ICONE17-75490
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Topics: Monitoring systems , Optimization , Quality control
A Comparative Study of Methodologies for Determining Plant Availabilities and Initiator Frequencies
Ernie Kee, Fatma Yilmaz, Paul Nelson
ICONE 2009; 983-992https://doi.org/10.1115/ICONE17-75527
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Topics: Approximation , Cooling , Errors , Failure , Maintenance , Water
Electrical Network Modeling and Electrical Transfer Simulation of C.N. Asco´ I and C.N. Asco´ II, to Obtain Voltage and Frequency Limit Values Allowing the Electrical Transfer From the Main Generator to the External 110 kV Power Grid
Alberto Ban˜o´ Azco´n, Jose´ Mollera Barriga
ICONE 2009; 993-1002https://doi.org/10.1115/ICONE17-75546
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Topics: Generators , Modeling , Power grids , Simulation , Circuit breakers , Delays , Design , Electronic systems , Nuclear power stations , Nuclear reactor coolants
A Modern Approach to Condition-Based Maintenance of Reinforced Rubber Cooling System Expansion Joints Utilizing a Microwave Non-Destructive Inspection Method
Jack Little, Robert Stakenborghs
ICONE 2009; 1003-1009https://doi.org/10.1115/ICONE17-75602
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Topics: Cooling systems , Expansion joints , Maintenance , Microwaves , Nondestructive evaluation , Rubber , Inspection , Rubber products , ASTM International , Building materials
Simplified Approach to Establishing Bounding Main Steam Piping Support Load Increase Due to Reactor Power Uprate
Robert Stakenborghs, Lindsey Dziuba
ICONE 2009; 1011-1019https://doi.org/10.1115/ICONE17-75743
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Topics: Pipes , Power uprate , Steam , Stress , Flow (Dynamics) , Fluids , Turbines , Valves , Electric power generation , Engineers
Study on Pipe Wastage Mechanism by Liquid Droplet Impingement Erosion
Yuma Higashi, Tadashi Narabayashi, Yoichiro Shimazu, Masashi Tsuji, Syuichi Ohmori, Michitsugu Mori, Kenichi Tezuka
ICONE 2009; 1021-1027https://doi.org/10.1115/ICONE17-76029
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Topics: Drops , Erosion , Pipes , Corners (Structural elements) , Corrosion , Errors , Flow (Dynamics) , Mass measurement , Microscopes , Nuclear power stations
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