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

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; 17-28doi:https://doi.org/10.1115/ICONE17-75100

Abstract

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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; 29-36doi:https://doi.org/10.1115/ICONE17-75170

Abstract

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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; 37-44doi:https://doi.org/10.1115/ICONE17-75175

Abstract

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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; 45-52doi:https://doi.org/10.1115/ICONE17-75194

Abstract

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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; 53-60doi:https://doi.org/10.1115/ICONE17-75203

Abstract

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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; 61-66doi:https://doi.org/10.1115/ICONE17-75224

Abstract

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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; 67-74doi:https://doi.org/10.1115/ICONE17-75225

Abstract

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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; 75-80doi:https://doi.org/10.1115/ICONE17-75300

Abstract

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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; 81-87doi:https://doi.org/10.1115/ICONE17-75310

Abstract

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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; 89-95doi:https://doi.org/10.1115/ICONE17-75330

Abstract

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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; 97-100doi:https://doi.org/10.1115/ICONE17-75349

Abstract

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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; 101-111doi:https://doi.org/10.1115/ICONE17-75355

Abstract

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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; 113-122doi:https://doi.org/10.1115/ICONE17-75433

Abstract

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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; 123-130doi:https://doi.org/10.1115/ICONE17-75436

Abstract

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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; 131-141doi:https://doi.org/10.1115/ICONE17-75441

Abstract

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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; 143-151doi:https://doi.org/10.1115/ICONE17-75459

Abstract

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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; 153-160doi:https://doi.org/10.1115/ICONE17-75474

Abstract

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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; 161-169doi:https://doi.org/10.1115/ICONE17-75526

Abstract

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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; 171-179doi:https://doi.org/10.1115/ICONE17-75547

Abstract

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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; 181-186doi:https://doi.org/10.1115/ICONE17-75565

Abstract

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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; 187-195doi:https://doi.org/10.1115/ICONE17-75617

Abstract

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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; 197-204doi:https://doi.org/10.1115/ICONE17-75649

Abstract

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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; 205-212doi:https://doi.org/10.1115/ICONE17-75661

Abstract

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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; 213-219doi:https://doi.org/10.1115/ICONE17-75760

Abstract

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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; 221-228doi:https://doi.org/10.1115/ICONE17-75797

Abstract

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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; 229-234doi:https://doi.org/10.1115/ICONE17-75804

Abstract

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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; 235-244doi:https://doi.org/10.1115/ICONE17-75814

Abstract

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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; 245-252doi:https://doi.org/10.1115/ICONE17-75825

Abstract

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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; 253-263doi:https://doi.org/10.1115/ICONE17-75858

Abstract

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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; 265-272doi:https://doi.org/10.1115/ICONE17-75916

Abstract

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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; 273-279doi:https://doi.org/10.1115/ICONE17-76002

Abstract

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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; 281-289doi:https://doi.org/10.1115/ICONE17-76059

Abstract

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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; 291-295doi:https://doi.org/10.1115/ICONE17-75019

Abstract

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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; 297-306doi:https://doi.org/10.1115/ICONE17-75022

Abstract

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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; 307-311doi:https://doi.org/10.1115/ICONE17-75029

Abstract

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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; 313-321doi:https://doi.org/10.1115/ICONE17-75039

Abstract

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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; 323-329doi:https://doi.org/10.1115/ICONE17-75071

Abstract

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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; 331-339doi:https://doi.org/10.1115/ICONE17-75078

Abstract

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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; 341-348doi:https://doi.org/10.1115/ICONE17-75099

Abstract

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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; 349-353doi:https://doi.org/10.1115/ICONE17-75128

Abstract

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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; 355-359doi:https://doi.org/10.1115/ICONE17-75145

Abstract

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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; 361-367doi:https://doi.org/10.1115/ICONE17-75159

Abstract

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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; 369-378doi:https://doi.org/10.1115/ICONE17-75177

Abstract

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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; 379-385doi:https://doi.org/10.1115/ICONE17-75196

Abstract

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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; 387-393doi:https://doi.org/10.1115/ICONE17-75211

Abstract

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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; 395-402doi:https://doi.org/10.1115/ICONE17-75219

Abstract

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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; 403-411doi:https://doi.org/10.1115/ICONE17-75223

Abstract

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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; 413-420doi:https://doi.org/10.1115/ICONE17-75227

Abstract

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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; 421-425doi:https://doi.org/10.1115/ICONE17-75239

Abstract

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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; 427-438doi:https://doi.org/10.1115/ICONE17-75249

Abstract

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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; 439-444doi:https://doi.org/10.1115/ICONE17-75252

Abstract

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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; 445-453doi:https://doi.org/10.1115/ICONE17-75263

Abstract

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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; 455-461doi:https://doi.org/10.1115/ICONE17-75266

Abstract

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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; 463-470doi:https://doi.org/10.1115/ICONE17-75304

Abstract

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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; 471-476doi:https://doi.org/10.1115/ICONE17-75306

Abstract

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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; 477-481doi:https://doi.org/10.1115/ICONE17-75352

Abstract

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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; 483-486doi:https://doi.org/10.1115/ICONE17-75360

Abstract

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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; 487-494doi:https://doi.org/10.1115/ICONE17-75364

Abstract

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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; 495-503doi:https://doi.org/10.1115/ICONE17-75365

Abstract

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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; 505-509doi:https://doi.org/10.1115/ICONE17-75384

Abstract

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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; 511-518doi:https://doi.org/10.1115/ICONE17-75398

Abstract

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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; 519-531doi:https://doi.org/10.1115/ICONE17-75414

Abstract

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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; 533-540doi:https://doi.org/10.1115/ICONE17-75450

Abstract

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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; 541-549doi:https://doi.org/10.1115/ICONE17-75455

Abstract

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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; 551-561doi:https://doi.org/10.1115/ICONE17-75456

Abstract

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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; 563-573doi:https://doi.org/10.1115/ICONE17-75457

Abstract

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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; 575-581doi:https://doi.org/10.1115/ICONE17-75464

Abstract

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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; 583-592doi:https://doi.org/10.1115/ICONE17-75472

Abstract

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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; 593-599doi:https://doi.org/10.1115/ICONE17-75517

Abstract

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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; 601-609doi:https://doi.org/10.1115/ICONE17-75518

Abstract

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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; 611-621doi:https://doi.org/10.1115/ICONE17-75550

Abstract

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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; 623-628doi:https://doi.org/10.1115/ICONE17-75562

Abstract

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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; 629-637doi:https://doi.org/10.1115/ICONE17-75595

Abstract

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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; 639-648doi:https://doi.org/10.1115/ICONE17-75681

Abstract

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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; 649-656doi:https://doi.org/10.1115/ICONE17-75684

Abstract

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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; 657-666doi:https://doi.org/10.1115/ICONE17-75708

Abstract

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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; 667-676doi:https://doi.org/10.1115/ICONE17-75729

Abstract

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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; 677-683doi:https://doi.org/10.1115/ICONE17-75805

Abstract

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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; 685-690doi:https://doi.org/10.1115/ICONE17-75827

Abstract

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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; 691-697doi:https://doi.org/10.1115/ICONE17-75852

Abstract

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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; 699-704doi:https://doi.org/10.1115/ICONE17-75861

Abstract

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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; 705-712doi:https://doi.org/10.1115/ICONE17-75881

Abstract

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Topics: Accidents , Pressurized water reactors , Safety

Lessons Learned in Reviewing CCF Events

Ashley Mossa, Rupert Weston

ICONE 2009; 713-717doi:https://doi.org/10.1115/ICONE17-75887

Abstract

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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; 719-727doi:https://doi.org/10.1115/ICONE17-75927

Abstract

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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; 729-733doi:https://doi.org/10.1115/ICONE17-75931

Abstract

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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; 735-743doi:https://doi.org/10.1115/ICONE17-75942

Abstract

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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; 745-749doi:https://doi.org/10.1115/ICONE17-75946

Abstract

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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; 751-756doi:https://doi.org/10.1115/ICONE17-75972

Abstract

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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; 757-764doi:https://doi.org/10.1115/ICONE17-76026

Abstract

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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; 765-775doi:https://doi.org/10.1115/ICONE17-76033

Abstract

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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; 777-784doi:https://doi.org/10.1115/ICONE17-76042

Abstract

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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; 785-791doi:https://doi.org/10.1115/ICONE17-76048

Abstract

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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; 793-797doi:https://doi.org/10.1115/ICONE17-75052

Abstract

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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; 799-806doi:https://doi.org/10.1115/ICONE17-75141

Abstract

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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; 807-814doi:https://doi.org/10.1115/ICONE17-75229

Abstract

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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; 815-822doi:https://doi.org/10.1115/ICONE17-75326

Abstract

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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; 823-829doi:https://doi.org/10.1115/ICONE17-75407

Abstract

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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; 831-841doi:https://doi.org/10.1115/ICONE17-75417

Abstract

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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; 843-846doi:https://doi.org/10.1115/ICONE17-75434

Abstract

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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; 847-855doi:https://doi.org/10.1115/ICONE17-75473

Abstract

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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; 857-866doi:https://doi.org/10.1115/ICONE17-75557

Abstract

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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; 867-874doi:https://doi.org/10.1115/ICONE17-75579

Abstract

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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; 875-883doi:https://doi.org/10.1115/ICONE17-75702

Abstract

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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; 885-889doi:https://doi.org/10.1115/ICONE17-75787

Abstract

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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; 891-895doi:https://doi.org/10.1115/ICONE17-75811

Abstract

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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; 897-904doi:https://doi.org/10.1115/ICONE17-75898

Abstract

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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; 905-914doi:https://doi.org/10.1115/ICONE17-75906

Abstract

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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; 915-921doi:https://doi.org/10.1115/ICONE17-75907

Abstract

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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; 923-929doi:https://doi.org/10.1115/ICONE17-75939

Abstract

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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; 931-935doi:https://doi.org/10.1115/ICONE17-75949

Abstract

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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; 937-943doi:https://doi.org/10.1115/ICONE17-76031

Abstract

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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; 945-953doi:https://doi.org/10.1115/ICONE17-75006

Abstract

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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; 955-963doi:https://doi.org/10.1115/ICONE17-75087

Abstract

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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; 965-973doi:https://doi.org/10.1115/ICONE17-75406

Abstract

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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; 975-981doi:https://doi.org/10.1115/ICONE17-75490

Abstract

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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; 983-992doi:https://doi.org/10.1115/ICONE17-75527

Abstract

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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; 993-1002doi:https://doi.org/10.1115/ICONE17-75546

Abstract

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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; 1003-1009doi:https://doi.org/10.1115/ICONE17-75602

Abstract

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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; 1011-1019doi:https://doi.org/10.1115/ICONE17-75743

Abstract

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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; 1021-1027doi:https://doi.org/10.1115/ICONE17-76029

Abstract

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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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