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17th International Conference on Nuclear Engineering

July 12–16, 2009

Brussels, Belgium

Conference Sponsors:

ISBN:

978-0-7918-4355-0

In This Volume

Fuel Cycle and High and Low Level Waste Management and Decommissioning (28)
Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes (55)
Instrumentation and Control (I&C) (17)

Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control

Fuel Cycle and High and Low Level Waste Management and Decommissioning

Development of a Remote Welding Machine for a DUPIC Fuel Bundle Fabrication

Soo-sung Kim, Geun-il Park, Jung-won Lee, Jin-hyun Koh

ICONE 2009; 1-8https://doi.org/10.1115/ICONE17-75095

Abstract

View Articletitled, Development of a Remote Welding Machine for a DUPIC Fuel Bundle Fabrication

PDF

Topics: Fuels , Machinery , Manufacturing , Welding

Design and Fabrication of the FBR Fuel Disassembly System

Toru Kitagaki, Masayuki Tasaka, Hidetoshi Higuchi, Kenji Koizumi, Hiroyasu Hirano, Tadahiro Washiya, Tsuguyuki Kobayashi

ICONE 2009; 9-13https://doi.org/10.1115/ICONE17-75117

Abstract

View Articletitled, Design and Fabrication of the FBR Fuel Disassembly System

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Topics: Design , Die cutting , Fuels , Manufacturing

Development of Salt Particle Collection Device to Prevent SCC of Canisters

Hirofumi Takeda, Toshiari Saegusa

ICONE 2009; 15-23https://doi.org/10.1115/ICONE17-75122

Abstract

View Articletitled, Development of Salt Particle Collection Device to Prevent SCC of Canisters

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Topics: Particulate matter , Water , Seas , Storage , Concretes , Cooling systems , Ducts , Flow (Dynamics) , Heat , Pressure

Development of Safety Assessment Code for Decommissioning of Nuclear Facilities (DecDose)

Taro Shimada, Soichiro Ohshima, Takenori Sukegawa

ICONE 2009; 25-32https://doi.org/10.1115/ICONE17-75123

Abstract

View Articletitled, Development of Safety Assessment Code for Decommissioning of Nuclear Facilities (DecDose)

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Topics: Nuclear decommissioning , Nuclear power stations , Safety , Radioisotopes , Cutting , Radiation (Physics) , Nuclear power , Aerosols , Containers , Decontamination

Development of Short Stroke Shearing Technology for FBR Fuel Pins

Hidetoshi Higuchi, Kenji Koizumi, Hiroyasu Hirano, Masayuki Tasaka, Tadahiro Washiya, Tsuguyuki Kobayashi

ICONE 2009; 33-37https://doi.org/10.1115/ICONE17-75125

Abstract

View Articletitled, Development of Short Stroke Shearing Technology for FBR Fuel Pins

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Topics: Die cutting , Fuels , Pins (Engineering) , Shearing (Deformation)

Cementation of Radioactive Waste Resin by Calcium Sulfoaluminate Cement

Junfeng Li, Jianlong Wang

ICONE 2009; 47-51https://doi.org/10.1115/ICONE17-75197

Abstract

View Articletitled, Cementation of Radioactive Waste Resin by Calcium Sulfoaluminate Cement

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Topics: Cements (Adhesives) , Radioactive wastes , Resins , Ion exchange , Temperature , Compressive strength , Irradiation (Radiation exposure) , Solidification , China , Needles

Study on Properties of Reprocessed Uranium: Investigation of Surface Gamma Dose and Water Content of Reprocessed UO₃ Powder in the Storage

Atsushi Yamanaka, Manabu Murakami, Yuuichi Goto, Shigeo Senoo

ICONE 2009; 53-56https://doi.org/10.1115/ICONE17-75244

Abstract

View Articletitled, Study on Properties of Reprocessed Uranium: Investigation of Surface Gamma Dose and Water Content of Reprocessed UO3 Powder in the Storage

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Topics: Storage , Uranium , Water

Competitiveness of Small-Medium, New Generation Reactors: A Comparative Study on Decommissioning

Giorgio Locatelli, Mauro Mancini

ICONE 2009; 57-66https://doi.org/10.1115/ICONE17-75254

Abstract

View Articletitled, Competitiveness of Small-Medium, New Generation Reactors: A Comparative Study on Decommissioning

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Topics: Nuclear decommissioning , Economics , Design , Maintenance , Project cost estimation

Chromatography Column System With Controlled Flow and Temperature for Engineering Scale Application

Sou Watanabe, Ichiro Goto, Yuichi Sano, Yoshikazu Koma

ICONE 2009; 67-73https://doi.org/10.1115/ICONE17-75298

Abstract

View Articletitled, Chromatography Column System With Controlled Flow and Temperature for Engineering Scale Application

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Topics: Flow (Dynamics) , Temperature , Heat , Cycles , Fast neutron reactors , Fuels , Gates (Closures) , Nuclear power , Sensors , Technology development

Enhanced VVER-1000 Fuel Technology and Performance

H. Shah, R. Latorre, G. Raspopin, J. Sparrow

ICONE 2009; 75-82https://doi.org/10.1115/ICONE17-75335

Abstract

View Articletitled, Enhanced VVER-1000 Fuel Technology and Performance

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Topics: Fuels , Nuclear power stations , Pacific Ocean , Safety

Continuous-Operation Test at Engineering Scale Uranium Crystallizer System

Tadahiro Washiya, Toshimitsu Tayama, Kazuhito Nakamura, Kimihiko Yano, Atsuhiro Shibata, Kazunori Nomura, Takahiro Chikazawa, Masanobu Nagata, Toshiaki Kikuchi

ICONE 2009; 83-88https://doi.org/10.1115/ICONE17-75339

Abstract

View Articletitled, Continuous-Operation Test at Engineering Scale Uranium Crystallizer System

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Topics: Crystallization , Uranium , Crystals , Failure , Fuels , Ions , Nuclear power , Screws , Stability , Steady state

Transport of High-Temperature Molten Salt Slurry for Pyro-Reprocessing

Takatoshi Hijikata, Tadafumi Koyama

ICONE 2009; 89-98https://doi.org/10.1115/ICONE17-75379

Abstract

View Articletitled, Transport of High-Temperature Molten Salt Slurry for Pyro-Reprocessing

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Topics: High temperature , Slurries , Filters , Metals , Anodes , Centrifugal pumps , Gravity (Force) , Impellers , Nuclear fission , Nuclear fuel cycle

Preliminary Set Up of the Methodology to Analyze Nuclear Fuel Cycle Scenarios

Barbara Vezzoni, Giuseppe Forasassi

ICONE 2009; 99-106https://doi.org/10.1115/ICONE17-75410

Abstract

View Articletitled, Preliminary Set Up of the Methodology to Analyze Nuclear Fuel Cycle Scenarios

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Topics: Equilibrium (Physics) , Nuclear fuel cycle , Nuclear power , Radioactive wastes

Extraction of Technetium as [Tc(II)(NO)(AHA)₂H₂O]⁺ Species in the UREX Process

Patricia Paviet-Hartmann, Ana Nunez Gomez-Aleixandre, Joshua Pak, Amparo Glez Espartero, Frederic Poineau, Amber Wright, Edward Mausolf, Kenneth R. Czerwinski

ICONE 2009; 107-113https://doi.org/10.1115/ICONE17-75509

Abstract

View Articletitled, Extraction of Technetium as [Tc(II)(NO)(AHA)2H2O]+ Species in the UREX Process

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Topics: Water , Diluents , Ethers (Class of compounds)

Decontamination of Metal Surfaces Artificially Contaminated With Cs⁺ Ions by a Laser Ablation

Hui Jun Won, Byambatseren Baigalmaa, Jei Kwon Moon, Chong Hun Jung, Kune Woo Lee

ICONE 2009; 115-118https://doi.org/10.1115/ICONE17-75535

Abstract

View Articletitled, Decontamination of Metal Surfaces Artificially Contaminated With Cs+ Ions by a Laser Ablation

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Topics: Decontamination , Ions , Laser ablation , Metal surfaces , Lasers , Irradiation (Radiation exposure) , Fluence (Radiation measurement) , Low temperature , Nd-YAG lasers , Oxygen

Development of Simulation Tool for Dismantling Planning

Haishan Zhu, Zhongkun Liu

ICONE 2009; 119-122https://doi.org/10.1115/ICONE17-75605

Abstract

View Articletitled, Development of Simulation Tool for Dismantling Planning

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Topics: Simulation , Virtual reality

Agents and Processes Design for TRU Elements Back Extraction in TRPO Process

Meng Wei, Xuegang Liu, Jing Chen

ICONE 2009; 123-130https://doi.org/10.1115/ICONE17-75652

Abstract

View Articletitled, Agents and Processes Design for TRU Elements Back Extraction in TRPO Process

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Topics: Design , Recycling , Risk , Waste disposal

Spent Resin Hot Compaction at Tihange NPP

Baudouin Centner, David Charpentier

ICONE 2009; 131-138https://doi.org/10.1115/ICONE17-75696

Abstract

View Articletitled, Spent Resin Hot Compaction at Tihange NPP

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Topics: Compacting , Nuclear power stations , Resins , Acceptance criteria , Fracture (Materials) , Optimization , Water , Boiling water reactors , Brittleness , Condensed matter

IDEA: An Integrated Set of Tools for Sustainable Nuclear Decommissioning Projects

Pierre Cnapelinckx, Fanny Castillo

ICONE 2009; 139-147https://doi.org/10.1115/ICONE17-75699

Abstract

View Articletitled, IDEA: An Integrated Set of Tools for Sustainable Nuclear Decommissioning Projects

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Topics: Nuclear decommissioning , Sustainability , Computers , Nuclear power stations , Radioactive wastes , Computer software , Nuclides , Radioisotopes , Algorithms , Computer-aided design

Assessment of TRANSURANUS Fuel Performance Code Against Studsvik Inter-Ramp BWR Database

Martina Adorni, Alessandro Del Nevo, Paul Van Uffelen, Francesco Oriolo, Francesco D’Auria

ICONE 2009; 149-158https://doi.org/10.1115/ICONE17-75704

Abstract

View Articletitled, Assessment of TRANSURANUS Fuel Performance Code Against Studsvik Inter-Ramp BWR Database

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Topics: Boiling water reactors , Databases , Fuels , Cladding systems (Building) , Nuclear fission , Accidents , Defense industry , Density , Design , Engineering simulation

Release of Materials During the Decommissioning of the Belgonucleaire Dessel MOX Fuel Fabrication Plant

Jean-Marie Cuchet, Alain Vandergheynst, Henri Libon

ICONE 2009; 159-166https://doi.org/10.1115/ICONE17-75782

Abstract

View Articletitled, Release of Materials During the Decommissioning of the Belgonucleaire Dessel MOX Fuel Fabrication Plant

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Topics: Fuels , Manufacturing , Nuclear decommissioning , Metals , Regulations , Cables , Containment , Contamination , Decontamination , Electronics

Advanced First Core Design for the Westinghouse AP1000

Robert J. Fetterman

ICONE 2009; 167-174https://doi.org/10.1115/ICONE17-75806

Abstract

View Articletitled, Advanced First Core Design for the Westinghouse AP1000

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Topics: Design , Cycles , Fuels , Leakage , Economics , Public utilities , Construction , Nuclear fuel cycle , Pressurized water reactors , Uranium

Progress and Experiences From the Decommissioning of the Eurochemic Reprocessing Plant

Robert Walthe´ry, Patrick Lewandowski, Bart Ooms, Nancy Reusen, Wim Van Laer

ICONE 2009; 175-181https://doi.org/10.1115/ICONE17-75809

Abstract

View Articletitled, Progress and Experiences From the Decommissioning of the Eurochemic Reprocessing Plant

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Topics: Nuclear decommissioning , Decontamination , Concretes , Protective clothing , Ceilings , Contamination , Cooling , Demolition , Fuels , Industrial wastes

TREQ: Fuel Rod Performance Code for Demanding PWR Plants

I. Pastor, N. Doncel

ICONE 2009; 183-191https://doi.org/10.1115/ICONE17-75832

Abstract

View Articletitled, TREQ: Fuel Rod Performance Code for Demanding PWR Plants

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Topics: Fuel rods , Pressurized water reactors , Fuels , Cladding systems (Building) , Design , Irradiation (Radiation exposure) , Rods , Safety , Accidents , Economics

Volume Reduction of Radioactive Concrete Wastes by Thermal and Mechanical Treatments

Wang Kyu Choi, Byung Youn Min, Kune Woo Lee

ICONE 2009; 193-196https://doi.org/10.1115/ICONE17-75917

Abstract

View Articletitled, Volume Reduction of Radioactive Concrete Wastes by Thermal and Mechanical Treatments

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Topics: Concretes , Nuclear decommissioning , Uranium , Weight (Mass) , Cements (Adhesives) , Heating , Radioactive wastes , Radioactivity , Separation (Technology) , Graphite

Using a Real Coded Genetic Algorithm to Obtain the Optimal Parameters of a Cascade of Gas Centrifuge

Hamid Minuchehr, Ahmad Zolfaghari, Peymaan Makarachi, Ali Noroozy

ICONE 2009; 197-204https://doi.org/10.1115/ICONE17-75926

Abstract

View Articletitled, Using a Real Coded Genetic Algorithm to Obtain the Optimal Parameters of a Cascade of Gas Centrifuge

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Topics: Cascades (Fluid dynamics) , Genetic algorithms , Construction , Design , Geometry , Optimization , Performance , Rotors , Separation (Technology)

PWR Fuel Management Optimization Using a New Integer Coded Genetic Algorithm

Ahmad Zolfaghari, Hamid Minuchehr, Ali Noroozy, Peymaan Makarachi

ICONE 2009; 205-209https://doi.org/10.1115/ICONE17-75932

Abstract

View Articletitled, PWR Fuel Management Optimization Using a New Integer Coded Genetic Algorithm

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Topics: Fuel management , Genetic algorithms , Optimization , Pressurized water reactors , Design , Fuels

The Release of Radionuclides in the Laser Decontamination Process

Marion Herrmann, Wolfgang Lippmann, Antonio Hurtado

ICONE 2009; 211-216https://doi.org/10.1115/ICONE17-75958

Abstract

View Articletitled, The Release of Radionuclides in the Laser Decontamination Process

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Topics: Decontamination , Lasers , Radioisotopes , Concretes , Glass , Ablation (Vaporization technology) , Filters , Phase transition temperature , Chemical properties , Contamination

Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes

A Conceptual Design of I-125 Generator at the HANARO

Heonil Kim, Jonghark Park, Byungchul Lee, Heetaek Chae, Youngki Kim

ICONE 2009; 217-222https://doi.org/10.1115/ICONE17-75020

Abstract

View Articletitled, A Conceptual Design of I-125 Generator at the HANARO

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Topics: Conceptual design , Generators , Neutrons , Computational fluid dynamics , Design , Physics , Thermal hydraulics

Calculation and Measurement of Kinetics Parameters of Tehran Research Reactor

Seyed Abolfazl Hosseini, Naser Vosoughi, Mortaza Gharib, Mohammad Bagher Ghofrani

ICONE 2009; 223-228https://doi.org/10.1115/ICONE17-75036

Abstract

View Articletitled, Calculation and Measurement of Kinetics Parameters of Tehran Research Reactor

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Topics: Coolants , Errors , Fuels , Neutrons , Physics , Temperature , Transient analysis

CFD Investigating the Changes of FAC Wear Sites Due to the Power Uprate of Nuclear Power Plant

Tsun Fu Hung, Yuh Ming Ferng, Bing Hong Lin, Chunkuan Shih, Bau-Shei Pei

ICONE 2009; 229-237https://doi.org/10.1115/ICONE17-75049

Abstract

View Articletitled, CFD Investigating the Changes of FAC Wear Sites Due to the Power Uprate of Nuclear Power Plant

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Topics: Computational fluid dynamics , Nuclear power stations , Power uprate , Wear , Boiling water reactors , Simulation results , Two-phase flow , Computation , Corrosion , Flow (Dynamics)

Sensitivity Study of Lower Plenum Boron Injection in a BWR

Jin Yan, Andrew Mallner

ICONE 2009; 239-247https://doi.org/10.1115/ICONE17-75056

Abstract

View Articletitled, Sensitivity Study of Lower Plenum Boron Injection in a BWR

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Topics: Boiling water reactors , Boron , Computational fluid dynamics , Control systems , Flow (Dynamics) , Nuclear reactor coolants , Rods

CFD Simulation of Forced Flow Within the THAI Model Containment

Armin Zirkel, Guido Doebbener, Eckart Laurien

ICONE 2009; 249-256https://doi.org/10.1115/ICONE17-75070

Abstract

View Articletitled, CFD Simulation of Forced Flow Within the THAI Model Containment

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Topics: Computational fluid dynamics , Containment , Flow (Dynamics) , Simulation , Turbulence , Geometry , Accidents , Anisotropy , Circuits , Computer simulation

Optimization of a Two-Fluid Hydrodynamic Model of Churn-Turbulent Flows

Donna Post Guillen, Jonathan K. Shelley, Steven P. Antal, Elena A. Tselishcheva, Michael Z. Podowski, Dirk Lucas, Matthias Beyer

ICONE 2009; 257-266https://doi.org/10.1115/ICONE17-75113

Abstract

View Articletitled, Optimization of a Two-Fluid Hydrodynamic Model of Churn-Turbulent Flows

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Topics: Computational fluid dynamics , Design , Flow (Dynamics) , Fluids , Optimization , Turbulence

ABWR Start-Up Test Analysis With Transient Code BISON

Kazuki Yano, Yamato Hayashi

ICONE 2009; 267-273https://doi.org/10.1115/ICONE17-75127

Abstract

View Articletitled, ABWR Start-Up Test Analysis With Transient Code BISON

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Topics: Transients (Dynamics) , Control systems , Design , Feedwater , Flow (Dynamics) , Pumps , Steady state , Boiling water reactors , Geometry , Pressure

Development and Validation of a Computational Fluid Dynamics Model for the Simulation of Two-Phase Flow Phenomena in a Boiling Water Reactor Fuel Assembly

Adrian Tentner, W. David Pointer, Simon Lo, Andrew Splawski

ICONE 2009; 275-284https://doi.org/10.1115/ICONE17-75135

Abstract

View Articletitled, Development and Validation of a Computational Fluid Dynamics Model for the Simulation of Two-Phase Flow Phenomena in a Boiling Water Reactor Fuel Assembly

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Topics: Boiling water reactors , Computational fluid dynamics , Fuels , Manufacturing , Simulation , Two-phase flow , Modeling , Cladding systems (Building) , Coolants , Heat transfer

Analysis of ABWR Critical Control Operation by TRACG Code

Yoshihiko Ishii, Kazuaki Kitou, Tomohiko Ikegawa, Shin Hasegawa, Hitoshi Ochi

ICONE 2009; 285-291https://doi.org/10.1115/ICONE17-75143

Abstract

View Articletitled, Analysis of ABWR Critical Control Operation by TRACG Code

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Topics: Algorithms , Design , Diffusion (Physics) , Neutrons , Power regulators , Transient analysis , Two-phase flow

Numerical and Modeling Issues in Application of CFD to Flow in a Simplified Plenum Relevant to a Prismatic VHTR

Ismail Celik, Ertan Karaismail

ICONE 2009; 293-306https://doi.org/10.1115/ICONE17-75187

Abstract

View Articletitled, Numerical and Modeling Issues in Application of CFD to Flow in a Simplified Plenum Relevant to a Prismatic VHTR

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Topics: Computational fluid dynamics , Flow (Dynamics) , Modeling , Very high temperature reactors , Uncertainty , Turbulence , Vortex shedding , Fluids engineering , Reynolds number , Reynolds-averaged Navier–Stokes equations

CFD Application of the Diffusion-Inertia Model to Bubble Flows and Boiling Water Problems

Alexander S. Filippov, Vladimir M. Alipchenkov, Nickolay I. Drobyshevsky, Roman V. Mukin, Valeri Th. Strizhov, Leonid I. Zaichik

ICONE 2009; 307-315https://doi.org/10.1115/ICONE17-75208

Abstract

View Articletitled, CFD Application of the Diffusion-Inertia Model to Bubble Flows and Boiling Water Problems

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Topics: Boiling , Bubbly flow , Computational fluid dynamics , Diffusion (Physics) , Inertia (Mechanics) , Water , Turbulence , Density , Drops , Flow (Dynamics)

Development and Validation of a Multifield Model of Churn-Turbulent Gas/Liquid Flows

Elena A. Tselishcheva, Steven P. Antal, Michael Z. Podowski, Donna Post Guillen, Matthias Beyer, Dirk Lucas

ICONE 2009; 317-326https://doi.org/10.1115/ICONE17-75210

Abstract

View Articletitled, Development and Validation of a Multifield Model of Churn-Turbulent Gas/Liquid Flows

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Topics: Flow (Dynamics) , Turbulence , Bubbles , Modeling , Computers , Engineering simulation , Fluid dynamics , Simulation , Test facilities , Two-phase flow

Numerical Prediction of Void Distribution in Two-Phase Turbulent Flow in a Sub-Channel

Tsutomu Ikeno, Tatsuya Sasakawa, Isao Kataoka

ICONE 2009; 327-334https://doi.org/10.1115/ICONE17-75302

Abstract

View Articletitled, Numerical Prediction of Void Distribution in Two-Phase Turbulent Flow in a Sub-Channel

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Topics: Turbulence , Pressurized water reactors , Flow (Dynamics) , Atmospheric pressure , Computer simulation , Finite volume methods , Fuel rods , Heat flux , Nucleate boiling , Porosity

Experimental and Numerical Investigations of Temperature Stratification Phenomena in Passive Safety Systems for Decay Heat Removal

Eckhard Krepper, Matthias Beyer

ICONE 2009; 335-343https://doi.org/10.1115/ICONE17-75303

Abstract

View Articletitled, Experimental and Numerical Investigations of Temperature Stratification Phenomena in Passive Safety Systems for Decay Heat Removal

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Topics: Heat , Safety , Temperature , Computational fluid dynamics , Condensers (steam plant) , Emergencies , Engineering simulation , Simulation , Boiling water reactors , Heat sinks

Hydrodynamic Modeling of Mineral Wool Fiber Suspensions in a Two-Dimensional Flow

Gregory M. Cartland Glover, Alexander Grahn, Eckhard Krepper, Frank-Peter Weiss, So¨ren Alt, Rainer Hampel, Wolfgang Ka¨stner, Alexander Kratzsch, Frank Zacharias

ICONE 2009; 345-354https://doi.org/10.1115/ICONE17-75308

Abstract

View Articletitled, Hydrodynamic Modeling of Mineral Wool Fiber Suspensions in a Two-Dimensional Flow

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Topics: Fibers , Flow (Dynamics) , Mineral wool , Modeling , Accidents , Computer simulation , Containment , Coolants , Drag (Fluid dynamics) , Engineering simulation

CFD Study on Mixing in VVER-440 Fuel Rod Bundle With Guiding Vanes in Spacer Grids

Tellervo Brandt, Timo Toppila

ICONE 2009; 355-363https://doi.org/10.1115/ICONE17-75316

Abstract

View Articletitled, CFD Study on Mixing in VVER-440 Fuel Rod Bundle With Guiding Vanes in Spacer Grids

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Topics: Computational fluid dynamics , Fuel rods , Flow (Dynamics) , Flux (Metallurgy) , Fuels , Geometry , Heat , Manufacturing , Modeling , Pressurized water reactors

Numerical Flow Simulation of Spacer Grids With Mixing Vanes in a 5 × 5 PWR Rod Bundle

Moyse´s Alberto Navarro, Andre´ Augusto Campagnole dos Santos

ICONE 2009; 365-373https://doi.org/10.1115/ICONE17-75354

Abstract

View Articletitled, Numerical Flow Simulation of Spacer Grids With Mixing Vanes in a 5 × 5 PWR Rod Bundle

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Topics: Flow simulation , Fuel rods , Pressurized water reactors , Heat transfer , Coolants , Flow (Dynamics) , Pressure , Pressure drop , Computational fluid dynamics , Engineering simulation

Application of a Step-Wise Verification and Validation Procedure to the 3D Neutron Kinetics Code DYN3D Within the European NURESIM Project

U. Rohde, S. Mittag, U. Grundmann, P. Petkov, J. Ha´dek

ICONE 2009; 375-387https://doi.org/10.1115/ICONE17-75446

Abstract

View Articletitled, Application of a Step-Wise Verification and Validation Procedure to the 3D Neutron Kinetics Code DYN3D Within the European NURESIM Project

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Topics: Neutrons , Errors , Diffusion (Physics) , Approximation , Modeling , Cross section (Physics) , Manufacturing , Physics , Software development , Steady state

Next Generation Safety Analysis Methods for SFRs—(2) Experimental Analyses by SIMMER-III for the Integral Verification of the COMPASS Code on Fuel-Pin Disruption and Low-Energy Disrupted Core Motion

Hidemasa Yamano, Yoshiharu Tobita

ICONE 2009; 389-398https://doi.org/10.1115/ICONE17-75462

Abstract

View Articletitled, Next Generation Safety Analysis Methods for SFRs—(2) Experimental Analyses by SIMMER-III for the Integral Verification of the COMPASS Code on Fuel-Pin Disruption and Low-Energy Disrupted Core Motion

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Topics: Experimental analysis , Fuels , Safety , Sodium fast reactors , Failure , Accidents , Computers , Databases , Deformation , Failure mechanisms

Identification and Prioritization of Generic Nuclear Safety Problems Requiring CFD Analysis

Brian L. Smith

ICONE 2009; 399-408https://doi.org/10.1115/ICONE17-75482

Abstract

View Articletitled, Identification and Prioritization of Generic Nuclear Safety Problems Requiring CFD Analysis

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Topics: Computational fluid dynamics , Safety , Cycles , Fatigue

Next Generation Safety Analysis Methods for SFRs—(3) Thermal Hydraulics Models of COMPASS Code and Experimental Analyses

Yuichi Yamamoto, Etsujo Hirano, Masaya Oue, Sensuke Shimizu, Noriyuki Shirakawa, Seiichi Koshizuka, Koji Morita, Hidemasa Yamano, Yoshiharu Tobita

ICONE 2009; 409-418https://doi.org/10.1115/ICONE17-75521

Abstract

View Articletitled, Next Generation Safety Analysis Methods for SFRs—(3) Thermal Hydraulics Models of COMPASS Code and Experimental Analyses

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Topics: Experimental analysis , Safety , Sodium fast reactors , Thermal hydraulics , Accidents , Computers , Conceptual design , Particulate matter , Physics

Sensitivity Analysis of Kinetics Parameters of Tehran Research Reactor (TRR)

Seyed Abolfazl Hosseini, Naser Vosoughi

ICONE 2009; 419-423https://doi.org/10.1115/ICONE17-75523

Abstract

View Articletitled, Sensitivity Analysis of Kinetics Parameters of Tehran Research Reactor (TRR)

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Topics: Computers , Coolants , Fuels , Neutrons , Nuclear fission , Sensitivity analysis , Temperature , Uranium

Next Generation Safety Analysis Methods for SFRs—(5) Structural Mechanics Models of COMPASS Code and Verification Analyses

Noriyuki Shirakawa, Yasushi Uehara, Masanori Naitoh, Hidetoshi Okada, Yuichi Yamamoto, Seiichi Koshizuka

ICONE 2009; 425-434https://doi.org/10.1115/ICONE17-75532

Abstract

View Articletitled, Next Generation Safety Analysis Methods for SFRs—(5) Structural Mechanics Models of COMPASS Code and Verification Analyses

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Topics: Safety , Sodium fast reactors , Structural analysis , Structural mechanics , Design , Fluid dynamics , Fracture (Materials) , Fracture (Process) , Particulate matter , Phase transitions

Next Generation Safety Analysis Methods for SFRs—(6) SCARABEE BE+3 Analysis With SIMMER-III and COMPASS Codes Featuring Duct-Wall Failure

Yasushi Uehara, Noriyuki Shirakawa, Masanori Naitoh, Hidetoshi Okada, Hidemasa Yamano, Yoshiharu Tobita, Yuichi Yamamoto, Seiichi Koshizuka

ICONE 2009; 435-444https://doi.org/10.1115/ICONE17-75533

Abstract

View Articletitled, Next Generation Safety Analysis Methods for SFRs—(6) SCARABEE BE+3 Analysis With SIMMER-III and COMPASS Codes Featuring Duct-Wall Failure

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Topics: Ducts , Failure , Safety , Sodium fast reactors , Fuels , Model development , Accidents , Freezing , Mesoscopic systems , Metals

Development and Verification of Unstructured Adaptive Mesh Technique With Edge Compatibility

Kei Ito, Tomoaki Kunugi, Hiroyuki Ohshima

ICONE 2009; 445-453https://doi.org/10.1115/ICONE17-75536

Abstract

View Articletitled, Development and Verification of Unstructured Adaptive Mesh Technique With Edge Compatibility

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Topics: Algorithms , Cavities , Computational fluid dynamics , Design , Errors , Flow (Dynamics) , Fluids , Modeling , Reactor vessels , Shapes

Use of BEPU Technique for Analyses of BDBAs With Cooling in WWER-1000

Grigory L. Ponomarenko, Sergey B. Ryzhov, Mikhail A. Bykov, Aleksandr M. Moskalev

ICONE 2009; 455-463https://doi.org/10.1115/ICONE17-75537

Abstract

View Articletitled, Use of BEPU Technique for Analyses of BDBAs With Cooling in WWER-1000

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Topics: Cooling , Accidents , Acceptance criteria , Coolants , Design , Emergencies , Failure , Neutrons , Nuclear fuels , Rods

Next Generation Safety Analysis Methods for SFRs—(4) Development of a Computational Framework on Fluid-Solid Mixture Flow Simulations for the COMPASS Code

Shuai Zhang, Koji Morita, Noriyuki Shirakawa, Yuichi Yamamoto

ICONE 2009; 465-471https://doi.org/10.1115/ICONE17-75549

Abstract

View Articletitled, Next Generation Safety Analysis Methods for SFRs—(4) Development of a Computational Framework on Fluid-Solid Mixture Flow Simulations for the COMPASS Code

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Topics: Flow simulation , Fluids , Safety , Sodium fast reactors , Discrete element methods , Engineering simulation , Rods , Simulation , Solids , Accidents

Boron Transient Analysis by the GRS Coupled Code Systems QUABOX-CUBBOX/ATHLET and TORT-TD/ATHLET

K. Velkov, A. Seubert, I. Pasichnyk, A. Pautz

ICONE 2009; 473-477https://doi.org/10.1115/ICONE17-75555

Abstract

View Articletitled, Boron Transient Analysis by the GRS Coupled Code Systems QUABOX-CUBBOX/ATHLET and TORT-TD/ATHLET

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Topics: Boron , Transient analysis , Diffusion (Physics) , Transients (Dynamics) , Approximation , Fuels , Manufacturing , Neutrons , Pressurized water reactors , Safety

Next Generation Safety Analysis Methods for SFRs—(1) Brief Introduction of the Project and Basic Study for Algorithm of Particle Method

Seiichi Koshizuka

ICONE 2009; 479-485https://doi.org/10.1115/ICONE17-75556

Abstract

View Articletitled, Next Generation Safety Analysis Methods for SFRs—(1) Brief Introduction of the Project and Basic Study for Algorithm of Particle Method

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Topics: Algorithms , Particulate matter , Safety , Sodium fast reactors , Boundary-value problems , Flow (Dynamics) , Fuels , Metals , Accidents , Cladding systems (Building)

Influence of System and Neutron-Kinetic Parameter Variations on an Anticipated Transient Without SCRAM in a PWR

So¨ren Kliem, Siegfried Mittag, Ulrich Rohde, Frank-Peter Weiss

ICONE 2009; 487-493https://doi.org/10.1115/ICONE17-75569

Abstract

View Articletitled, Influence of System and Neutron-Kinetic Parameter Variations on an Anticipated Transient Without SCRAM in a PWR

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Topics: Neutrons , Pressurized water reactors , Scram , Transients (Dynamics) , Pressure , Coolants , Circuits , Safety , Failure , Feedwater

Next Generation Safety Analysis Methods for SFRs—(8) Analyses of Eutectics Between Fuel and Steel in Metal Fuel With FPMD Code VASP

Masashi Himi, Yuichi Yamamoto, Yasuo Nagamine, Noriyuki Shirakawa, Yasushi Uehara, Tatsumi Arima

ICONE 2009; 495-504https://doi.org/10.1115/ICONE17-75578

Abstract

View Articletitled, Next Generation Safety Analysis Methods for SFRs—(8) Analyses of Eutectics Between Fuel and Steel in Metal Fuel With FPMD Code VASP

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Topics: Fuels , Metals , Safety , Sodium fast reactors , Steel , Diffusion (Physics) , Molecular dynamics , Accidents , Cladding systems (Building) , High temperature

A Discrete Equation Method for Two-Dimensional Calculations of Two-Phase Compressible Mixtures

A. A. Leonov, V. V. Chudanov

ICONE 2009; 505-512https://doi.org/10.1115/ICONE17-75586

Abstract

View Articletitled, A Discrete Equation Method for Two-Dimensional Calculations of Two-Phase Compressible Mixtures

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Topics: Bubbles , Density , Discrete element methods , Flow (Dynamics) , Flux (Metallurgy) , Relaxation (Physics) , Resolution (Optics) , Shock tubes , Shock waves

A Case History of CFD Support to Accelerator Driven System Plant Design

Vincent Moreau, Luigi Mansani, Maurizio Petrazzini

ICONE 2009; 513-523https://doi.org/10.1115/ICONE17-75588

Abstract

View Articletitled, A Case History of CFD Support to Accelerator Driven System Plant Design

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Topics: Computational fluid dynamics , Plant design , Design , Simulation , Flow (Dynamics) , Heat exchangers , Pumps , Shapes , Accident management , Collaboration

Next Generation Safety Analysis Methods for SFRs—(7) Potential Model for Classical Molecular Dynamics on Pu-Fe System

Takahiro Ito, Tatsumi Arima, Masashi Himi

ICONE 2009; 525-533https://doi.org/10.1115/ICONE17-75591

Abstract

View Articletitled, Next Generation Safety Analysis Methods for SFRs—(7) Potential Model for Classical Molecular Dynamics on Pu-Fe System

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Topics: Molecular dynamics , Safety , Sodium fast reactors , Atoms , Accidents , Alloys , Intermetallic compounds , Materials properties , Metals , Simulation

CFD Investigation of Experimental Data Proposed to be a Validation Data Set

Richard W. Johnson

ICONE 2009; 535-542https://doi.org/10.1115/ICONE17-75604

Abstract

View Articletitled, CFD Investigation of Experimental Data Proposed to be a Validation Data Set

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Topics: Computational fluid dynamics , Very high temperature reactors , Coolants , Flow (Dynamics) , Gas cooled reactors , Heat transfer , Helium , Nuclear power stations , Reactor vessels , Refractive index

CFD Modeling of Fuel Rod Heat Transfer to Aid in the Risk Assessment of Fuel Rod Failure Due to Localized Crud

Steven Beltz, Bin Liu, Zeses Karoutas

ICONE 2009; 543-550https://doi.org/10.1115/ICONE17-75710

Abstract

View Articletitled, CFD Modeling of Fuel Rod Heat Transfer to Aid in the Risk Assessment of Fuel Rod Failure Due to Localized Crud

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Topics: Computational fluid dynamics , Failure , Fuel rods , Heat transfer , Modeling , Risk assessment , Fuels , Heat transfer coefficients , Design , Arches

Methods for Modeling Local Fuel Rod Crud and Assessing Failure Risk

Michael A. Krammen, Guoqiang Wang, Steven F. Grill, Zeses E. Karoutas, Michael Y. Young

ICONE 2009; 551-559https://doi.org/10.1115/ICONE17-75715

Abstract

View Articletitled, Methods for Modeling Local Fuel Rod Crud and Assessing Failure Risk

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Topics: Failure , Fuel rods , Modeling , Risk , Fuels , Computational fluid dynamics , Nuclear reactor coolants , Corrosion , Design , Boiling

Three Dimensional Modelling of the Hydrodynamics of Oblique Droplet-Hot Wall Interactions During the Reflood Phase After a LOCA

D. Chatzikyriakou, S. P. Walker, B. Belhouachi, C. Narayanan, D. Lakehal, G. F. Hewitt

ICONE 2009; 561-568https://doi.org/10.1115/ICONE17-75716

Abstract

View Articletitled, Three Dimensional Modelling of the Hydrodynamics of Oblique Droplet-Hot Wall Interactions During the Reflood Phase After a LOCA

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Topics: Drops , Hydrodynamics , Three-dimensional modeling , Temperature , Cooling , Heat transfer , Simulation , Algorithms , Computational fluid dynamics , Convection

Temperature Fluctuations in a CANDU Moderator Test Facility

F. Farhadi, N. Ashgriz, M. Kwee, R. Girard, Y. Parlatan, M. Ali

ICONE 2009; 569-577https://doi.org/10.1115/ICONE17-75717

Abstract

View Articletitled, Temperature Fluctuations in a CANDU Moderator Test Facility

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Topics: Fluctuations (Physics) , Temperature , Test facilities , Flow (Dynamics) , Jets , Buoyancy , Computer simulation , Fluids , Vortices

Time Domain Analysis of the Temperatures in an Electrical Auxiliary Building Room

Andron Creary, Matthew F. King, Matthew Langston, Cable Kurwitz, Paul Nelson, Fatma Yilmaz

ICONE 2009; 579-586https://doi.org/10.1115/ICONE17-75720

Abstract

View Articletitled, Time Domain Analysis of the Temperatures in an Electrical Auxiliary Building Room

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Topics: Temperature , Time-domain analysis , Computational fluid dynamics , Lumped parameter models , Eigenvalues , Electronics , Heat

Implementation of RAVE™ (To a Reload)

Cenk Gu¨ler, Serhat Lider

ICONE 2009; 587-592https://doi.org/10.1115/ICONE17-75728

Abstract

View Articletitled, Implementation of RAVE™ (To a Reload)

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Topics: Accidents , Licensing , Pressurized water reactors , Safety , Transients (Dynamics)

Treatment of Noise in Experimental Transport Measurements Plots With Discrete Wavelet Transforms

Rube´n Panta Pazos

ICONE 2009; 593-598https://doi.org/10.1115/ICONE17-75731

Abstract

View Articletitled, Treatment of Noise in Experimental Transport Measurements Plots With Discrete Wavelet Transforms

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Topics: Discrete wavelet transforms , Noise (Sound) , Signals , Compression , Wavelet transforms , Algebra , Algorithms , Computers , Filters , Low-pass filters

Proposed Experiment for Validation of CFD Methods for Advanced SFR Design: Upper Plenum Thermal Striping and Stratification

W. David Pointer, Stephen Lomperski, Paul Fischer, Aleksandr Obabko

ICONE 2009; 599-611https://doi.org/10.1115/ICONE17-75740

Abstract

View Articletitled, Proposed Experiment for Validation of CFD Methods for Advanced SFR Design: Upper Plenum Thermal Striping and Stratification

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Topics: Computational fluid dynamics , Design , Sodium fast reactors , Simulation , Turbulence , Physics , Resolution (Optics) , Reynolds-averaged Navier–Stokes equations , Safety , Coolants

The Study of Hybrid Method in the Onset of Droplet Escaping From the Film

Yun Guo, Yuki Ishiwatari, Satoshi Ikejiri, Yoshiaki Oka

ICONE 2009; 613-620https://doi.org/10.1115/ICONE17-75757

Abstract

View Articletitled, The Study of Hybrid Method in the Onset of Droplet Escaping From the Film

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Topics: Drops , Particulate matter , Surface tension , Adhesion , Density , Flow (Dynamics) , Fluid films , Simulation

Behavior of a Sequence of Geometric Transformations for a Truncated Ellipsoid Geometry in Transport Theory

Rube´n Panta Pazos

ICONE 2009; 621-625https://doi.org/10.1115/ICONE17-75758

Abstract

View Articletitled, Behavior of a Sequence of Geometric Transformations for a Truncated Ellipsoid Geometry in Transport Theory

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Topics: Geometry , Transport theory , Boundary-value problems , Algebra , Biomedicine , Computers , Neutrons , Rotation , Vacuum

Numerical Analysis for Heat and Mass Transfer of Granular Flow in a Duct by the Discrete Particle Simulation

Tomohiko Yamaguchi, Kuniyasu Kanemaru, Satoru Momoki, Toru Shigechi, Ryo Fujiwara

ICONE 2009; 627-632https://doi.org/10.1115/ICONE17-75762

Abstract

View Articletitled, Numerical Analysis for Heat and Mass Transfer of Granular Flow in a Duct by the Discrete Particle Simulation

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Topics: Ducts , Flow (Dynamics) , Heat , Mass transfer , Numerical analysis , Particulate matter , Simulation , Temperature , Fluids , Momentum

CFD Simulation of Passive Auto-Catalytic Recombiner Operational Behaviour

S. Kelm, W. Jahn, E.-A. Reinecke, J. Baggemann, H.-J. Allelein

ICONE 2009; 633-639https://doi.org/10.1115/ICONE17-75831

Abstract

View Articletitled, CFD Simulation of Passive Auto-Catalytic Recombiner Operational Behaviour

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Topics: Accidents , Catalysts , Chemical kinetics , Combustion , Computational fluid dynamics , Computer simulation , Containment , Databases , Failure , Flow (Dynamics)

Control Rod Ejection Accident: Benchmark Solution With FEM Code DiFis

Aleksandr I. Zhukov, Akif M. Abdullayev

ICONE 2009; 641-647https://doi.org/10.1115/ICONE17-75889

Abstract

View Articletitled, Control Rod Ejection Accident: Benchmark Solution With FEM Code DiFis

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Topics: Accidents , Finite element methods , Fuels , Diffusion (Physics) , Feedback , Neutrons , Approximation , Cladding systems (Building) , Coolants , Cross section (Physics)

Application of Large-Eddy Simulation to Pressurized Thermal Shock Problem

M. S. Loginov, E. M. J. Komen, A. K. Kuczaj

ICONE 2009; 649-658https://doi.org/10.1115/ICONE17-75894

Abstract

View Articletitled, Application of Large-Eddy Simulation to Pressurized Thermal Shock Problem

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Topics: Large eddy simulation , Thermal shock , Flow (Dynamics) , Computational fluid dynamics , Coolants , Buoyancy , Engineering simulation , Reynolds-averaged Navier–Stokes equations , Scalars , Simulation

COSI Test Case Simulation With CFX Code

Tony Glantz

ICONE 2009; 659-666https://doi.org/10.1115/ICONE17-75923

Abstract

View Articletitled, COSI Test Case Simulation With CFX Code

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Topics: Simulation , Fluids , Computational fluid dynamics , Pressurized water reactors , Water , Condensation , Temperature , Thermal shock , Accidents , Coolants

PWR Nuclear Power Plants Fuel Management Optimization

Ahmad Zolfaghari, Hamid Minuchehr, Ali Noroozy, Peymaan Makarachi, F. Koshahval

ICONE 2009; 667-672https://doi.org/10.1115/ICONE17-75924

Abstract

View Articletitled, PWR Nuclear Power Plants Fuel Management Optimization

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Topics: Fuel management , Nuclear power stations , Optimization , Pressurized water reactors , Genetic algorithms , Design , Fuels

Study on Spacer Grid Span Pressure Loss Under High Reynolds Number Flow Condition

Kazuo Ikeda, Yasunao Yamaguchi, Juntaro Shimizu, Kaoru Okamoto

ICONE 2009; 673-684https://doi.org/10.1115/ICONE17-75925

Abstract

View Articletitled, Study on Spacer Grid Span Pressure Loss Under High Reynolds Number Flow Condition

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Topics: Flow (Dynamics) , Pressure , Reynolds number , Computational fluid dynamics , Fuel rods , Design , Computer simulation , Nuclear fuels , Pressurized water reactors , Simulation

Development of Code, PNFENT, Based on Using Finite Elements for Neutron Transport

Ahmad Zolfaghari, Hamid Minuchehr, Mohammadreza Abbasi

ICONE 2009; 685-689https://doi.org/10.1115/ICONE17-75964

Abstract

View Articletitled, Development of Code, PNFENT, Based on Using Finite Elements for Neutron Transport

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Topics: Finite element analysis , Neutrons , Anisotropy , Computation , Electromagnetic scattering , Errors , Finite element methods , Leakage , Parity (Physics) , Radiation scattering

Numerical Modelling of Stratified Gas-Liquid Flow in Inclined Circular Pipes

Jose´ L. H. Faccini, Paulo A. B. De Sampaio, Jian Su

ICONE 2009; 691-696https://doi.org/10.1115/ICONE17-75986

Abstract

View Articletitled, Numerical Modelling of Stratified Gas-Liquid Flow in Inclined Circular Pipes

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Topics: Flow (Dynamics) , Modeling , Pipes , Pressure gradient , Finite element methods , Navier-Stokes equations , Nonlinear differential equations , Turbulence

FLUENT Analysis of a ROSA Two-Phase Stratification Test

Tatiana Farkas, Iva´n To´th

ICONE 2009; 697-706https://doi.org/10.1115/ICONE17-76012

Abstract

View Articletitled, FLUENT Analysis of a ROSA Two-Phase Stratification Test

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Topics: Computational fluid dynamics , Condensation , Emergency core cooling systems , Flow (Dynamics) , Fluids , Nuclear reactor safety , Steam , Subcooling , Temperature , Temperature distribution

Instrumentation and Control (I&C)

Development of Control Rod Position Indicator Using Seismic-Resistance Reed Switches

Je-Yong Yu, Ji-Ho Kim, Hyung Huh, Myong-Hwan Choi, Dong-Seong Sohn

ICONE 2009; 707-711https://doi.org/10.1115/ICONE17-75092

Abstract

View Articletitled, Development of Control Rod Position Indicator Using Seismic-Resistance Reed Switches

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Topics: Switches , Permanent magnets , Safety , Control systems , Design , Failure , Reliability , Boron , Damage , Earthquakes

Reliability of Reactor Control Digital Systems

Mikhail A. Yastrebenetsky, Alexander A. Siora, Volodymyr I. Tokarev

ICONE 2009; 713-717https://doi.org/10.1115/ICONE17-75157

Abstract

View Articletitled, Reliability of Reactor Control Digital Systems

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Topics: Reliability , Control systems , Nuclear power stations , Instrumentation , Failure

US-APWR Human Systems Interface System Verification and Validation Results: Impact on Digital I&C Design

Robert E. Hall, James Easter, Emilie Roth, Leonard Kaban, Kenji Mashio, Kunio Yugami, Koichi Takahashi, Timothy Clouser

ICONE 2009; 719-727https://doi.org/10.1115/ICONE17-75176

Abstract

View Articletitled, US-APWR Human Systems Interface System Verification and Validation Results: Impact on Digital I&C Design

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Topics: Design , Safety , Pressurized water reactors , Computer software , Computers , Construction , Control systems , Data collection , Instrumentation , Licensing

Applying Engineering Simulator to Verification and Validation of Digital I&C in Nuclear Power Plant

Meng Lin, Zongwei Yang, Dong Hou, Pengfei Liu

ICONE 2009; 729-733https://doi.org/10.1115/ICONE17-75234

Abstract

View Articletitled, Applying Engineering Simulator to Verification and Validation of Digital I&C in Nuclear Power Plant

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Topics: Nuclear power stations , Control systems , Engineers , China , Computer software , Design , Hardware , Reactor protection systems , Signals , Water

A Practical Example of Simulation Assisted Engineering and System Integrated Test for ABWR RIP-MFG System

Hitoshi Ochi, Atsutoshi Mizuide

ICONE 2009; 735-743https://doi.org/10.1115/ICONE17-75257

Abstract

View Articletitled, A Practical Example of Simulation Assisted Engineering and System Integrated Test for ABWR RIP-MFG System

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Topics: Simulation , Design , Boiling water reactors , Flow (Dynamics) , Construction , Control equipment , Electricity (Physics) , Engines , Errors , Flow control

Licensing Principles of FPGA-Based NPP I&C Systems

Alexander Siora, Volodymyr Sklyar, Yuriy Rozen, Svetlana Vinogradskaya, Mikhail Yastrebenetsky

ICONE 2009; 745-754https://doi.org/10.1115/ICONE17-75270

Abstract

View Articletitled, Licensing Principles of FPGA-Based NPP I&C Systems

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Topics: Licensing , Nuclear power stations , Computer software , Hardware

Modernization Project of Ikata Unit 1/2 Main Control Room Using Full Digital Control Board

Tomohide Sakuma, Kazuo Kitamura, Hiroki Okamoto, Tadashi Nakao, Hiroshi Watanabe

ICONE 2009; 755-761https://doi.org/10.1115/ICONE17-75278

Abstract

View Articletitled, Modernization Project of Ikata Unit 1/2 Main Control Room Using Full Digital Control Board

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Topics: Control panels , Control rooms , Construction , Inspection , Instrumentation , Safety , Control systems , Design , Electricity (Physics) , Pressurized water reactors

Advanced Control Design, Optimal Sensor Placement, and Technology Demonstration for Small and Medium Nuclear Power Reactors

B. R. Upadhyaya, S. R. P. Perillo, X. Xu, F. Li

ICONE 2009; 763-773https://doi.org/10.1115/ICONE17-75343

Abstract

View Articletitled, Advanced Control Design, Optimal Sensor Placement, and Technology Demonstration for Small and Medium Nuclear Power Reactors

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Topics: Design , Nuclear reactors , Sensor placement , Control equipment , Fault diagnosis , Instrumentation , Maintenance , Steam , Water , Actuators

Effects on Core Damage Frequency to Sensitivity of Instrumentation and Control Reliability

John T. Kitzmiller, Richard G. Anderson, Laura L. Genutis, Dennis M. Popp

ICONE 2009; 775-779https://doi.org/10.1115/ICONE17-75413

Abstract

View Articletitled, Effects on Core Damage Frequency to Sensitivity of Instrumentation and Control Reliability

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Topics: Damage , Instrumentation , Reliability , Failure , Modeling , Nuclear power stations , Probability , Safety , Computer software , Computers

Innovative Design for Control Rooms

Christian Hessler, Tobias Scharf

ICONE 2009; 781-789https://doi.org/10.1115/ICONE17-75512

Abstract

View Articletitled, Innovative Design for Control Rooms

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Topics: Control rooms , Design , Safety , Machinery , Cables , Control panels , Control systems , Licensing , Nuclear power stations , Process industries

Application of Virtual Reality in Evaluation and Optimization for Human Machine Interface

Shengyuan Yan, Chunyan Xia, Zhijian Zhang, Minjun Peng, Ming Yang

ICONE 2009; 791-796https://doi.org/10.1115/ICONE17-75644

Abstract

View Articletitled, Application of Virtual Reality in Evaluation and Optimization for Human Machine Interface

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Topics: Machinery , Optimization , Virtual reality , Simulation , Computer software , Control rooms

A Computer-Aided Layout Method for Human Machine Interface of Main Control Room

Yuqing Xu, Qingxin Meng, Kun Yu, Zhidan Xu, Shengyuan Yan

ICONE 2009; 797-801https://doi.org/10.1115/ICONE17-75645

Abstract

View Articletitled, A Computer-Aided Layout Method for Human Machine Interface of Main Control Room

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Topics: Computer-aided engineering , Control rooms , Machinery , Power stations , Accidents , Emergencies , Ergonomics , Genetic algorithms , Monitoring systems , Safety

Modernization of the Safety I&C at the Dukovany VVER 440/213 Nuclear Power Plant

Jean-Michel Palaric, Philippe Rebreyend, Philippe Mouly, Claude Esmenjaud, Frantisˇek Dalik

ICONE 2009; 803-813https://doi.org/10.1115/ICONE17-75706

Abstract

View Articletitled, Modernization of the Safety I&C at the Dukovany VVER 440/213 Nuclear Power Plant

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Topics: Nuclear power stations , Safety , Design , Instrumentation , Licensing

Development of Advanced System for Early Detection of Primary Coolant Circuit Piping Leaks

Petros Hovhannisyan

ICONE 2009; 815-820https://doi.org/10.1115/ICONE17-75810

Abstract

View Articletitled, Development of Advanced System for Early Detection of Primary Coolant Circuit Piping Leaks

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Topics: Circuits , Coolants , Leakage , Pipes , Fracture (Materials) , Pipelines , Deformation , Maintenance , Nuclear power stations , Safety

Experimental Evaluation of Wire Type Leak Detector Layout for Prototype Fast Breeder Reactor (PFBR)

K. K. Rajan, G. Vijayakumar, S. Chandramouli, K. Madhusoodhanan, P. Kalyanasundaram, G. Vaidyanathan

ICONE 2009; 821-829https://doi.org/10.1115/ICONE17-75822

Abstract

View Articletitled, Experimental Evaluation of Wire Type Leak Detector Layout for Prototype Fast Breeder Reactor (PFBR)

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Topics: Breeder reactors , Engineering prototypes , Leakage , Sensors , Wire , Sodium , Test facilities , Circuits , Electrical conductivity , Filters