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

Skip Nav Destination

2014 22nd International Conference on Nuclear Engineering

July 7–11, 2014

Prague, Czech Republic

Conference Sponsors:

ISBN:

978-0-7918-4589-9

In This Volume

Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant (27)
Nuclear Fuel and Materials (29)
Plant Systems, Structures and Components (30)
Codes, Standards, Licensing and Regulatory Issues (20)

Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues

Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant

A Statistical Model for Accessing Wall Thinning Rate due to Flow Accelerated Corrosion Based on Inspection Data in Nuclear Power Plants

Yuyun Zeng, Jingquan Liu, Weilin Huang

ICONE 2014; V001T01A001https://doi.org/10.1115/ICONE22-30043

Abstract

View Articletitled, A Statistical Model for Accessing Wall Thinning Rate due to Flow Accelerated Corrosion Based on Inspection Data in Nuclear Power Plants

PDF

Topics: Corrosion , Flow (Dynamics) , Inspection , Nuclear power stations , Pipes , Pressurized water reactors , Alloys , Carbon steel , Circuits , Decision making

Feasibility of Enhanced Estimation of PWR Primary Parameters: Twin Experiments for Assessing Data Assimilation Benefits (0D-Model With a Monte-Carlo Approach on Pseudo-Real Data)

Thibaud Mercier, Jean-Melaine Favennec, Alexandre Girard

ICONE 2014; V001T01A002https://doi.org/10.1115/ICONE22-30118

Abstract

View Articletitled, Feasibility of Enhanced Estimation of PWR Primary Parameters: Twin Experiments for Assessing Data Assimilation Benefits (0D-Model With a Monte-Carlo Approach on Pseudo-Real Data)

PDF

Topics: Pressurized water reactors , Climate , Nuclear reactor coolants , Flow (Dynamics) , Meteorology , Safety , Temperature distribution , Uncertainty

A New Paradigm: Cycling Operations at Nuclear Power Plants in the United States

Douglas Hilleman, Nikhil Kumar, Steven Lefton

ICONE 2014; V001T01A003https://doi.org/10.1115/ICONE22-30241

Abstract

View Articletitled, A New Paradigm: Cycling Operations at Nuclear Power Plants in the United States

PDF

Topics: Nuclear power stations , Damage , Stress , Boiling water reactors , Cycles , Fatigue damage

Dedicated Commercial Power Distribution Panels for Nuclear Safety Related Application

Yao-Tung Hsu

ICONE 2014; V001T01A004https://doi.org/10.1115/ICONE22-30247

Abstract

View Articletitled, Dedicated Commercial Power Distribution Panels for Nuclear Safety Related Application

PDF

Topics: Safety , Nuclear power stations , Testing , Acceptance criteria , Accidents , Diesel generators , Emergency power , Engineering standards , Failure , Fukushima nuclear disaster, Japan, 2011

A Remote Operated Quadruped Robot System for Investigation of Reactor Building

Naotaka Suganuma, Takuya Uehara, Kenji Matsuzaki, Makoto Ochiai, Fujio Terai, Akira Tsuyuki, Itaru Chida

ICONE 2014; V001T01A005https://doi.org/10.1115/ICONE22-30304

Abstract

View Articletitled, A Remote Operated Quadruped Robot System for Investigation of Reactor Building

PDF

Topics: Robots , Vehicles , Fukushima nuclear disaster, Japan, 2011 , Nuclear power stations , Stairs , Cables , Disasters , Manipulators , Radiation (Physics) , Water leakage

The SCORPIO-VVER Core Monitoring and Surveillance System for VVER Type of Reactors

Jozef Molnar, Radim Vocka

ICONE 2014; V001T01A006https://doi.org/10.1115/ICONE22-30431

Abstract

View Articletitled, The SCORPIO-VVER Core Monitoring and Surveillance System for VVER Type of Reactors

PDF

Topics: Monitoring systems , Nuclear power stations , Design , Fuels , Physicists , Bearings , Education , Neutrons , Physics , Safety

Atmosphere Isolation During the Maintenance of HTR-10 Helium Circulator

Ling Liu, Liqiang Wei, Xiaoming Chen, Yucheng Wang

ICONE 2014; V001T01A007https://doi.org/10.1115/ICONE22-30462

Abstract

View Articletitled, Atmosphere Isolation During the Maintenance of HTR-10 Helium Circulator

PDF

Topics: Helium , Maintenance , Contamination , Diffusion (Physics) , Dust , Graphite

Numerical Analysis of the Weld Joint Resulting Influence on the Pressurizer Surge Line Stress Distribution

Yang Yang, Hong Xia, Xian Zeng, Dali Yu

ICONE 2014; V001T01A008https://doi.org/10.1115/ICONE22-30470

Abstract

View Articletitled, Numerical Analysis of the Weld Joint Resulting Influence on the Pressurizer Surge Line Stress Distribution

PDF

Topics: Numerical analysis , Stress concentration , Surges , Parallel strand lumber , Stress , Finite element methods , Steady state , Finite volume methods , Temperature , Temperature distribution

Prediction Model for Oxidation Layer Thickness in Flow Accelerated Corrosion

Ruixuan Han, Yi Peng, Huailin Li

ICONE 2014; V001T01A009https://doi.org/10.1115/ICONE22-30489

Abstract

View Articletitled, Prediction Model for Oxidation Layer Thickness in Flow Accelerated Corrosion

PDF

Topics: Corrosion , Flow (Dynamics) , Oxidation , Temperature , Carbon steel

Application of Leakage-Flux Analysis for Three-Phase Induction Motors

Kohichi Nakayama, Yukio Watanabe, Kenji Osaki, Kotaro Hegi

ICONE 2014; V001T01A010https://doi.org/10.1115/ICONE22-30593

Abstract

View Articletitled, Application of Leakage-Flux Analysis for Three-Phase Induction Motors

PDF

Topics: Electromagnetic induction , Leakage , Motors , Bearings , Electric current , Vibration , Wear

A Portable Laser Processing System for Maintenance and Repair of Nuclear Facilities

Takaya Terada, Kiyoshi Oka, Akihiko Nishimura

ICONE 2014; V001T01A011https://doi.org/10.1115/ICONE22-30638

Abstract

View Articletitled, A Portable Laser Processing System for Maintenance and Repair of Nuclear Facilities

PDF

Topics: Lasers , Maintenance , Nuclear power stations , Cladding systems (Building) , Arc welding , Automatic control , Composite materials , Damage , Fiber lasers , Heating

On Vibration Properties of Piping Systems and Practical Measures for Preventing Vibration Damages

Lennart G. Jansson, Lingfu Zeng

ICONE 2014; V001T01A012https://doi.org/10.1115/ICONE22-30702

Abstract

View Articletitled, On Vibration Properties of Piping Systems and Practical Measures for Preventing Vibration Damages

PDF

Topics: Damage , Piping systems , Vibration , Design , Pipes , Risk

Thermal Performance Monitoring and Optimization in Dukovany NPP

Jiri Pliska, Zdenek Machat, Libor Veznik, Jiri Smisek

ICONE 2014; V001T01A013https://doi.org/10.1115/ICONE22-30735

Abstract

View Articletitled, Thermal Performance Monitoring and Optimization in Dukovany NPP

PDF

Topics: Nuclear power stations , Optimization , Maintenance , Sensors , Power stations , Circuits , Cooling , Cycles , Electricity (Physics) , Flaw detection

Performance of Equipment Qualification Safety Factor of Periodic Safety Review for Qinshan III CANDU NPP

Shen Xiaoyao

ICONE 2014; V001T01A014https://doi.org/10.1115/ICONE22-30799

Abstract

View Articletitled, Performance of Equipment Qualification Safety Factor of Periodic Safety Review for Qinshan III CANDU NPP

PDF

Topics: Equipment performance , Nuclear power stations , Safety , Equipment qualification , China , Performance , Teams

HFE Safety Evaluation in Angra-1 NPP for the Preparation and Inclusion of a Chapter 18 in the Plant Final Safety Analysis Report

Pedro Trueba Alonso, Juan Carlos Valdivia, Luís Fernández Illobre, Mark Hulsmans

ICONE 2014; V001T01A015https://doi.org/10.1115/ICONE22-30816

Abstract

View Articletitled, HFE Safety Evaluation in Angra-1 NPP for the Preparation and Inclusion of a Chapter 18 in the Plant Final Safety Analysis Report

PDF

Topics: Nuclear power stations , Safety , Design , Control rooms , Ergonomics , Governments , Instrumentation , Licensing , Pressurized water reactors

The Role of CHECWORKS™ in an Effective FAC Program

David Smith, Jeffrey Horowitz

ICONE 2014; V001T01A016https://doi.org/10.1115/ICONE22-30854

Abstract

View Articletitled, The Role of CHECWORKS™ in an Effective FAC Program

PDF

Topics: Accidents , Carbon steel , Computer software , Condensed matter , Corrosion , Engineers , Failure , Flow (Dynamics) , Fossil fuels , Inspection

Experimental Investigation of Dynamic Characteristics of Swing and Tilted Disc Check Valves

Jerzy Marcinkiewicz, Adam Adamkowski, Mariusz Lewandowski, Waldemar Janicki

ICONE 2014; V001T01A017https://doi.org/10.1115/ICONE22-30879

Abstract

View Articletitled, Experimental Investigation of Dynamic Characteristics of Swing and Tilted Disc Check Valves

PDF

Topics: Disks , Valves , Flow (Dynamics) , Pipelines , Pipes , Pressure , Pumps , Centrifugal pumps , Engines , Friction

Investigation on the Backflow Induced Pre-Rotation of RCP

Junlian Yin, Jingjing Li, Hui Chen, Yaoyu Hu, Dezhong Wang

ICONE 2014; V001T01A018https://doi.org/10.1115/ICONE22-30896

Abstract

View Articletitled, Investigation on the Backflow Induced Pre-Rotation of RCP

PDF

Topics: Rotation , Flow (Dynamics) , Pipes , Computational fluid dynamics , Design , Pressure , Pumps , Simulation

Cost Saving When Using Enhanced Conductivity Nuclear Fuel Containing BeO in WWER-1000 Reactors

Tomáš Zahrádka, Radek Škoda

ICONE 2014; V001T01A019https://doi.org/10.1115/ICONE22-30901

Abstract

View Articletitled, Cost Saving When Using Enhanced Conductivity Nuclear Fuel Containing BeO in WWER-1000 Reactors

PDF

Topics: Nuclear fuels , Thermal conductivity , Fuels , Temperature , Corporate average fuel economy , Cracking (Materials) , Fracture (Process) , Fuel efficiency , Gases , Geometry

Design and Development of Failed Fuel Location Module for Prototype Fast Breeder Reactor

Vijayashree Raju, Rajan Babu Vinayagamoorthy, Parthasarathy Uppala, Sureshkumar Ramachandran, Raghupathy Sundararajan, Chellapandi Perumal

ICONE 2014; V001T01A020https://doi.org/10.1115/ICONE22-30913

Abstract

View Articletitled, Design and Development of Failed Fuel Location Module for Prototype Fast Breeder Reactor

PDF

Topics: Breeder reactors , Design , Engineering prototypes , Fuels , Nuclear fission , Coolants , Manufacturing , Circuits , Conceptual design , Containment

Application of an Integrated Head Assembly Concept at Pressurized Water Reactor Commercial Nuclear Plants

Ravi Baliga, Tom Neal Watts, Harish Kamath

ICONE 2014; V001T01A021https://doi.org/10.1115/ICONE22-30916

Abstract

View Articletitled, Application of an Integrated Head Assembly Concept at Pressurized Water Reactor Commercial Nuclear Plants

PDF

Topics: Manufacturing , Nuclear power stations , Pressurized water reactors , Storage , Radiation (Physics) , Containment , Cooling , Design , Ducts , Missiles

Development of a Quality Manual for Radioisotope Production Plants

Yasser E. Tawfik

ICONE 2014; V001T01A022https://doi.org/10.1115/ICONE22-30918

Abstract

View Articletitled, Development of a Quality Manual for Radioisotope Production Plants

PDF

Topics: Radioisotopes , Nuclear power , Product quality , Production facilities , Quality management

Limit Load Analysis of Pipe Bend With Extrados Wall Thinning

TaeRyong Kim, ChangKyun Oh

ICONE 2014; V001T01A023https://doi.org/10.1115/ICONE22-31000

Abstract

View Articletitled, Limit Load Analysis of Pipe Bend With Extrados Wall Thinning

PDF

Topics: Pipe bends , Stress , Pressure , Corrosion , Diluents , Erosion , Manufacturing , Piping systems , Safety , Shapes

AP1000^® Plant Adaptation To European Markets

Kathyrn J. Demetri, Terry L. Schulz, Bryan N. Friedman

ICONE 2014; V001T01A024https://doi.org/10.1115/ICONE22-31057

Abstract

View Articletitled, AP1000® Plant Adaptation To European Markets

PDF

Topics: Accidents , China , Construction , Defense industry , Design , Electricity (Physics) , Licensing , Light water reactors , Maintenance , Plant design

A Study on Weld Residual Stress Relaxation by Local Post Weld Heat Treatment for Circumferential Weld

Seung-gun Lee, Youngho Son

ICONE 2014; V001T01A025https://doi.org/10.1115/ICONE22-31083

Abstract

View Articletitled, A Study on Weld Residual Stress Relaxation by Local Post Weld Heat Treatment for Circumferential Weld

PDF

Topics: Heat treating (Metalworking) , Relaxation (Physics) , Stress , Finite element analysis , Heat , Alloy steel , Engineering standards , Fracture (Materials) , Furnaces , Nuclear power stations

Loss of Representativeness of the Fixed Incore Instrumentation of the EPR™ Reactor

Brice Jardiné, Olivier Bougeant, Maxime Pfeiffer

ICONE 2014; V001T01A026https://doi.org/10.1115/ICONE22-31097

Abstract

View Articletitled, Loss of Representativeness of the Fixed Incore Instrumentation of the EPR™ Reactor

PDF

Topics: Instrumentation , Uncertainty , Surveillance , Probability , Signals , Algorithms , Engineering drawings , Failure , Fuels , Monte Carlo methods

Global Balance of Plant in NPPs Using Process Data Reconciliation According to VDI 2048

Magnus Langenstein, Bernd Laipple

ICONE 2014; V001T01A027https://doi.org/10.1115/ICONE22-31277

Abstract

View Articletitled, Global Balance of Plant in NPPs Using Process Data Reconciliation According to VDI 2048

PDF

Topics: Nuclear power stations , Feedwater , Flow (Dynamics) , Monitoring systems , Boilers , Energy budget (Physics) , Gases , Heat transfer coefficients , Leakage , Maintenance

Nuclear Fuel and Materials

Development and Verification of the Thermal Behavior Analysis Code for MA Containing MOX Fuels

Yoshihisa Ikusawa, Takayuki Ozawa, Shun Hirooka, Koji Maeda, Masato Kato, Seiichiro Maeda

ICONE 2014; V001T02A001https://doi.org/10.1115/ICONE22-30005

Abstract

View Articletitled, Development and Verification of the Thermal Behavior Analysis Code for MA Containing MOX Fuels

PDF

Topics: Fuels , Irradiation (Radiation exposure) , Temperature , Computers , Design methodology , Fast neutron reactors , Melting , Pressure , Thermal conductivity , Thermal properties

Evaluation of Fatigue Strength of Similar and Dissimilar Welded Joints of Modified 9Cr-1Mo Steel

Shigeru Takaya

ICONE 2014; V001T02A002https://doi.org/10.1115/ICONE22-30022

Abstract

View Articletitled, Evaluation of Fatigue Strength of Similar and Dissimilar Welded Joints of Modified 9Cr-1Mo Steel

PDF

Topics: Fatigue strength , Steel , Welded joints , Fatigue life , Base metals , Breeder reactors , Evaluation methods , Failure , Fatigue , Mechanical properties

A Three-Dimensional Analysis of the Local Stresses and Strains at the Pellet Ridges in a Horizontal Nuclear Fuel Element

Kyle A. L. Gamble, Anthony F. Williams, Paul K. Chan

ICONE 2014; V001T02A003https://doi.org/10.1115/ICONE22-30023

Abstract

View Articletitled, A Three-Dimensional Analysis of the Local Stresses and Strains at the Pellet Ridges in a Horizontal Nuclear Fuel Element

PDF

Topics: Nuclear fuels , Stress , Creep , Fuels , Simulation , Cladding systems (Building) , Cracking (Materials) , Deformation , Engineering standards , Finite element model

Optimized Surface Treatments and Manufacturing Techniques for Components of Sodium Cooled Fast Reactors

Emmanuel Horowitz

ICONE 2014; V001T02A004https://doi.org/10.1115/ICONE22-30119

Abstract

View Articletitled, Optimized Surface Treatments and Manufacturing Techniques for Components of Sodium Cooled Fast Reactors

PDF

Topics: Fast neutron reactors , Manufacturing , Sodium , Surface finishing , Shot peening , Laser hardening , Blades , Brittleness , Coatings , Corrosion

Computational Analyses of the Thermal Stress Induced by Coolant Mixing in a T-Joint

K. G. F. Janssens, M. Niffenegger, M. Sharabi

ICONE 2014; V001T02A005https://doi.org/10.1115/ICONE22-30218

Abstract

View Articletitled, Computational Analyses of the Thermal Stress Induced by Coolant Mixing in a T-Joint

PDF

Topics: Coolants , Thermal stresses , Boundary-value problems , Engineering simulation , Finite element analysis , Flow (Dynamics) , Low cycle fatigue , Simulation , Computational fluid dynamics , Cracking (Materials)

Character of Liquid Metal Embrittlement of the Steel T91 in Contact With Lead-Bismuth Eutectic

Anna Hojna, Fosca Di Gabriele, Jakub Klecka

ICONE 2014; V001T02A006https://doi.org/10.1115/ICONE22-30322

Abstract

View Articletitled, Character of Liquid Metal Embrittlement of the Steel T91 in Contact With Lead-Bismuth Eutectic

PDF

Topics: Embrittlement , Liquid metals , Steel , Fracture (Materials) , Fracture toughness , ASTM standards , Martensitic steel

Effect of Lath Width and Dislocation Density on Resistance to Irradiation of Warmly Deformed SCRAM Steel

Yang Mou, Lihong Xue, Qilai Zhou, Caixuan Lu, Jinping Suo, Youwei Yan, Liping Guo

ICONE 2014; V001T02A007https://doi.org/10.1115/ICONE22-30374

Abstract

View Articletitled, Effect of Lath Width and Dislocation Density on Resistance to Irradiation of Warmly Deformed SCRAM Steel

PDF

Topics: Dislocation density , Irradiation (Radiation exposure) , Scram , Steel , Helium , Bubbles , Hardening , Nanoindentation , Deformation , Machinery

Rapid Fabrication of Li₂TiO₃ Pebbles via Microwave-Induced Combustion Process and 3D Printing

Qilai Zhou, Yue Gao, Yang Mou, Lihong Xue, Heping Li, Youwei Yan

ICONE 2014; V001T02A008https://doi.org/10.1115/ICONE22-30394

Abstract

View Articletitled, Rapid Fabrication of Li2TiO3 Pebbles via Microwave-Induced Combustion Process and 3D Printing

PDF

Topics: Additive manufacturing , Combustion , Manufacturing , Microwaves , Computers , Ceramics , Fuels , Fusion reactors , Grain size , Lithium

HT9 Strain Modeling for Fuel Pin Deformation

Micah Hackett, Ryan Latta, Sam Miller, Cheng Xu

ICONE 2014; V001T02A009https://doi.org/10.1115/ICONE22-30414

Abstract

View Articletitled, HT9 Strain Modeling for Fuel Pin Deformation

PDF

Topics: Deformation , Fuels , Modeling , Cladding systems (Building) , Design , Creep , Fuel systems , Irradiation (Radiation exposure) , Nuclear fuel cycle , Pins (Engineering)

Retrieving Fuel Elements by Pneumatic Suction in Pebble-Bed High Temperature Gas-Cooled Reactor

Bin Wu, Jin-hua Wang, Yue Li, Bing Wang, Ji-guo Liu

ICONE 2014; V001T02A010https://doi.org/10.1115/ICONE22-30499

Abstract

View Articletitled, Retrieving Fuel Elements by Pneumatic Suction in Pebble-Bed High Temperature Gas-Cooled Reactor

PDF

Topics: Fuels , Suction , Very high temperature reactors , Pressure , Damage , Pressure drop , Spent fuel storage , Air flow , Design , Dynamics (Mechanics)

Investigation of Electron Beam Welding Characteristics Using AA6061-T6 for Nuclear Plate-Type Fuel Assembly

Soo-sung Kim, Yong-jin Jeong, Jong-man Park, Yoon-sang Lee

ICONE 2014; V001T02A011https://doi.org/10.1115/ICONE22-30588

Abstract

View Articletitled, Investigation of Electron Beam Welding Characteristics Using AA6061-T6 for Nuclear Plate-Type Fuel Assembly

PDF

Topics: Electron beam welding , Fuels , Manufacturing , Exploding wires , Welded joints , Welding , Aluminum alloys , Fracture (Materials) , Fracture (Process)

Three Dimensional Coupled Simulation of Plutonium, Oxygen and Heat Diffusion in Mixed Oxide (U, Pu)O₂ Fast Reactor Fuel

Rong Liu, Wenzhong Zhou, Gang Yang

ICONE 2014; V001T02A012https://doi.org/10.1115/ICONE22-30641

Abstract

View Articletitled, Three Dimensional Coupled Simulation of Plutonium, Oxygen and Heat Diffusion in Mixed Oxide (U, Pu)O2 Fast Reactor Fuel

PDF

Topics: Fast neutron reactors , Fuels , Oxygen , Simulation , Thermal diffusion , Diffusion (Physics) , Density , High temperature , Irradiation (Radiation exposure) , Materials properties

Enhanced Thermal Conductivity UO₂-BeO Fuels Fabrication Methods and Their Thermal Performance in Light Water Reactors

Wenzhong Zhou, Rong Liu

ICONE 2014; V001T02A013https://doi.org/10.1115/ICONE22-30647

Abstract

View Articletitled, Enhanced Thermal Conductivity UO2-BeO Fuels Fabrication Methods and Their Thermal Performance in Light Water Reactors

PDF

Topics: Fuels , Light water reactors , Manufacturing , Thermal conductivity , Finite element methods , Nuclear fuels , Composite materials , Computer software , Engineering simulation , Nuclear reactors

Assessment Oxidation Kinetics and Products in SCWR Media of Austenitic ODS Steels With Different Austenite Stabilisers

Maria Mihalache, Mihail Mihalache, Iulia Dumitrescu, Zhangjian Zhou

ICONE 2014; V001T02A014https://doi.org/10.1115/ICONE22-30665

Abstract

View Articletitled, Assessment Oxidation Kinetics and Products in SCWR Media of Austenitic ODS Steels With Different Austenite Stabilisers

PDF

Topics: Oxidation , Steel , Supercritical water reactors , Coolants , Water , Corrosion resistance , Pressure , Stainless steel , Temperature , Titanium

Results of a New Production of Nuclear-Grade 1.4970 ‘15-15Ti’ Stainless Steel Fuel Cladding Tubes for GEN IV Reactors

Rémi Delville, Erich Stergar, Marc Verwerft

ICONE 2014; V001T02A015https://doi.org/10.1115/ICONE22-30781

Abstract

View Articletitled, Results of a New Production of Nuclear-Grade 1.4970 ‘15-15Ti’ Stainless Steel Fuel Cladding Tubes for GEN IV Reactors

PDF

Topics: Cladding systems (Building) , Fuels , Stainless steel , Steel , Materials properties , Sodium fast reactors , Creep , Databases , Metallography , Nuclear fuels

Modelling of the Impact of Local Effects on Fuel-Cladding Interaction During Power Ramp

Jan Klouzal, Martin Dostál

ICONE 2014; V001T02A016https://doi.org/10.1115/ICONE22-30807

Abstract

View Articletitled, Modelling of the Impact of Local Effects on Fuel-Cladding Interaction During Power Ramp

PDF

Topics: Cladding systems (Building) , Fuels , Modeling , Cracking (Materials) , Design , Failure , Fracture (Process) , Heat , Heat transfer , Manufacturing

Characterisation of FeCrAlY Coatings for Applications in Lead Environment

Fosca Di Gabriele, Sarka Houdkova, Ondrej Soukup, Dalibor Karnik

ICONE 2014; V001T02A017https://doi.org/10.1115/ICONE22-30839

Abstract

View Articletitled, Characterisation of FeCrAlY Coatings for Applications in Lead Environment

PDF

Topics: Coatings , Coolants , Corrosion , Damage , Lasers , Liquid metals , Alloys , Corrosion resistance , Erosion , Fast neutron reactors

Zirconium Dioxide as a Protective Layer of Zirconium Fuel Cladding

Barbora Benešová, Radek Škoda

ICONE 2014; V001T02A018https://doi.org/10.1115/ICONE22-30848

Abstract

View Articletitled, Zirconium Dioxide as a Protective Layer of Zirconium Fuel Cladding

PDF

Topics: Cladding systems (Building) , Fuels , Zirconium , Oxidation , Stress , Temperature , Accidents , Ceramics , Cooling , Corrosion

Effects of Carbide Precipitate Formation on the Change in Ultrasonic Velocity in Austenitic Stainless Steels

Taira Okita, Junji Etoh, Mitsuyuki Sagisaka, Takashi Matsunaga, Yoshihiro Isobe

ICONE 2014; V001T02A019https://doi.org/10.1115/ICONE22-30859

Abstract

View Articletitled, Effects of Carbide Precipitate Formation on the Change in Ultrasonic Velocity in Austenitic Stainless Steels

PDF

Topics: Stainless steel , Annealing , Carbon , Grain boundaries , Precipitation , Temperature , Ultrasonic testing

Burnable Absorber Selection With U_WB₁ Depletion Code

Martin Lovecký, Jan Prehradný, Radek Škoda

ICONE 2014; V001T02A020https://doi.org/10.1115/ICONE22-30870

Abstract

View Articletitled, Burnable Absorber Selection With UWB1 Depletion Code

PDF

Topics: Approximation , Computers , Cross section (Physics) , Cycles , Fuels , Nuclear fuels , Nuclides

Polycrystalline Diamond Films as Protection of Zircaloy Fuel Cladding

Jan Škarohlíd, Radek Škoda

ICONE 2014; V001T02A021https://doi.org/10.1115/ICONE22-30873

Abstract

View Articletitled, Polycrystalline Diamond Films as Protection of Zircaloy Fuel Cladding

PDF

Topics: Cladding systems (Building) , Diamond films , Fuels , Zirconium alloys , Diamonds , Oxidation , Accidents , Alloys , Carbon , Chemical vapor deposition

Burnable Absorber Comparison Between VVER, PWR and SFR With U_WB₁ and SERPENT Codes

Jan Prehradný, Martin Lovecký, Radek Škoda

ICONE 2014; V001T02A022https://doi.org/10.1115/ICONE22-30894

Abstract

View Articletitled, Burnable Absorber Comparison Between VVER, PWR and SFR With UWB1 and SERPENT Codes

PDF

Topics: Pressurized water reactors , Sodium fast reactors , Fuels , Nuclear fuels , Spectra (Spectroscopy) , Cycles , Neutrons

Synthesis of Nanostructured Fuels: Mimicking the High Burn-Up Structure

Vaclav Tyrpekl, Raquel Jovani-Abril, Michael Holzhäuser

ICONE 2014; V001T02A023https://doi.org/10.1115/ICONE22-30952

Abstract

View Articletitled, Synthesis of Nanostructured Fuels: Mimicking the High Burn-Up Structure

PDF

Topics: Fuels , Nanoparticles , Sintering , Compacting , Density , Diffraction , Electron microscopy , Grain size , Nuclear fission , Nuclear reactors

Water Chemistry Technology of Methanol Addition in PWR Primary Systems: Radiolysis of Methanol Solution at 320 °C

Masafumi Domae, Kosho Hojo, Wataru Sugino

ICONE 2014; V001T02A024https://doi.org/10.1115/ICONE22-30954

Abstract

View Articletitled, Water Chemistry Technology of Methanol Addition in PWR Primary Systems: Radiolysis of Methanol Solution at 320 °C

PDF

Topics: Methanol , Pressurized water reactors , Water chemistry , Irradiation (Radiation exposure) , Carbon dioxide , Fuels , Hydrogen , Corrosion , Polymerization , Water

Characterization of In-Core Water Chemistry for Corrosion Control of LWRs

Genn Saji

ICONE 2014; V001T02A025https://doi.org/10.1115/ICONE22-30990

Abstract

View Articletitled, Characterization of In-Core Water Chemistry for Corrosion Control of LWRs

PDF

Topics: Corrosion protection , Light water reactors , Water chemistry , Radiation (Physics) , Boiling water reactors , Corrosion , Fittings , Hydrogen , Pressurized water reactors , Chemistry

Review on Water Radiolysis in the Fukushima Daiichi Accident: Potential Cause of Hydrogen Generation and Explosion

Genn Saji

ICONE 2014; V001T02A026https://doi.org/10.1115/ICONE22-30991

Abstract

View Articletitled, Review on Water Radiolysis in the Fukushima Daiichi Accident: Potential Cause of Hydrogen Generation and Explosion

PDF

Topics: Accidents , Explosions , Fukushima nuclear disaster, Japan, 2011 , Hydrogen , Water , Heat , Radiation (Physics) , Boiling , Bubbles , Chain

Advanced Alternatives of VVER-440 Fuel Assembly

Juraj Tomaškovič, Petr Dařílek, Radoslav Zajac, Vladimír Nečas

ICONE 2014; V001T02A027https://doi.org/10.1115/ICONE22-31108

Abstract

View Articletitled, Advanced Alternatives of VVER-440 Fuel Assembly

PDF

Topics: Fuels , Manufacturing , Absorption , Nuclear fuel cycle , Optimization , Equilibrium (Physics) , Pressurized water reactors

Variants of the Perspective Closed Fuel Cycle, Based on REMIX-Technology

Evgeniy Bobrov, Pavel Teplov, Pavel Alekseev, Alexander Chibinyaev, Anatoliy Dudnikox

ICONE 2014; V001T02A028https://doi.org/10.1115/ICONE22-31244

Abstract

View Articletitled, Variants of the Perspective Closed Fuel Cycle, Based on REMIX-Technology

PDF

Topics: Nuclear fuel cycle , Uranium , Fuels , Light water reactors , Raw materials , Breeder reactors , Cycles , Defense industry , Irradiation (Radiation exposure) , Nuclear fission

Simulation of PWR Crud

W. A. Byers, G. Wang, M. Y. Young, J. Deshon

ICONE 2014; V001T02A029https://doi.org/10.1115/ICONE22-31265

Abstract

View Articletitled, Simulation of PWR Crud

PDF

Topics: Pressurized water reactors , Simulation , Cladding systems (Building) , Corrosion , Fuels , Boron , Chemistry , Coolants , Electricity (Physics) , Fuel rods

Plant Systems, Structures and Components

Thermal Growth Simulations of the Rotor and Auxiliary Bearing Contact Events

Yulan Zhao, Guojun Yang, Zhengang Shi, Lei Zhao

ICONE 2014; V001T03A001https://doi.org/10.1115/ICONE22-30053

Abstract

View Articletitled, Thermal Growth Simulations of the Rotor and Auxiliary Bearing Contact Events

PDF

Topics: Bearings , Engineering simulation , Rotors , Simulation , Temperature , Heat , Failure , Heat transfer , Ball bearings , Ceramics

Dynamic Behavior Analysis of Touchdown Process in Active Magnetic Bearing System Based on Kalman Filtering

Zhe Sun, Xiao Kang, Jingjing Zhao, Guojun Yang, Zhengang Shi

ICONE 2014; V001T03A002https://doi.org/10.1115/ICONE22-30058

Abstract

View Articletitled, Dynamic Behavior Analysis of Touchdown Process in Active Magnetic Bearing System Based on Kalman Filtering

PDF

Topics: Filtration , Magnetic bearings , Bearings , Dynamic analysis , Dynamic models , Rotors , Very high temperature reactors , Brakes , Design , Safety

Dynamic Behavior of the AMB’s Vertical Arranged Rotor During Its Drop Process

Xiao Kang, Guojun Yang, Suyuan Yu

ICONE 2014; V001T03A003https://doi.org/10.1115/ICONE22-30062

Abstract

View Articletitled, Dynamic Behavior of the AMB’s Vertical Arranged Rotor During Its Drop Process

PDF

Topics: Rotors , Damping , Stiffness , Bearings , Bracing (Construction) , Computer simulation , Design , Dynamic models , Friction , Helium

An Experimental Study on Insulating Property of Helium in High Temperature Gas Cooled Reactor

Shan Yue, Xingnan Liu, Zhengang Shi

ICONE 2014; V001T03A004https://doi.org/10.1115/ICONE22-30077

Abstract

View Articletitled, An Experimental Study on Insulating Property of Helium in High Temperature Gas Cooled Reactor

PDF

Topics: Gas cooled reactors , Helium , High temperature , Electrical components , Testing , Coolants , Design , Electrodes , High pressure (Physics) , Nuclear industry

The FEM Calculation of Iron Loss in the Active Magnetic Bearing

Peicai Wu, Xingnan Liu, Guojun Yang, Zhengang Shi

ICONE 2014; V001T03A005https://doi.org/10.1115/ICONE22-30085

Abstract

View Articletitled, The FEM Calculation of Iron Loss in the Active Magnetic Bearing

PDF

Topics: Finite element methods , Finite element model , Iron , Magnetic bearings , Eddy current losses , Lamination , Rotors , Silicon steel , Bearings , Copper

Research About Eddy Effect and Dynamic Force of the Magnetic Thrust Bearing

Xingnan Liu, Ni Mo, Guojun Yang, Zhengang Shi, Suyuan Yu

ICONE 2014; V001T03A006https://doi.org/10.1115/ICONE22-30123

Abstract

View Articletitled, Research About Eddy Effect and Dynamic Force of the Magnetic Thrust Bearing

PDF

Topics: Eddies (Fluid dynamics) , Thrust bearings , Bearings , Finite element analysis , Electromagnetic force , Lamination , Magnetic bearings

Evaluation of Dynamic Loads due to Steam Condensation in Boiling Water Reactor ABWR Containment

Tsutomu Shioyama, Masashi Nakane, Takuya Miyagawa, Makoto Ukai, Masanobu Watanabe, Tsuyoshi Hagiwara

ICONE 2014; V001T03A007https://doi.org/10.1115/ICONE22-30141

Abstract

View Articletitled, Evaluation of Dynamic Loads due to Steam Condensation in Boiling Water Reactor ABWR Containment

PDF

Topics: Boiling water reactors , Condensation , Containment , Steam , Stress , Design , Oscillations , Acoustics , Boiling , Computational methods

Improvement of the System for Passive Heat Removal Through Steam Generators (SG PHRS) on NPP With VVER-1200 in the Light of “Fukushima” Accident

Vladimir Bezlepkin, Sergey Semashko, Sergey Alekseev, Marina Ivanova, Teimuraz Vardanidze, Yuriy Petrov

ICONE 2014; V001T03A008https://doi.org/10.1115/ICONE22-30240

Abstract

View Articletitled, Improvement of the System for Passive Heat Removal Through Steam Generators (SG PHRS) on NPP With VVER-1200 in the Light of “Fukushima” Accident

PDF

Topics: Accidents , Boilers , Fukushima nuclear disaster, Japan, 2011 , Heat , Nuclear power stations , Fuels , Preservation , Alternating current (Electricity) , Construction , Failure

Structural Analysis for Assembly by Integrating Parts

Norihiro Nakajima, Akemi Nishida, Yoshiaki Kawakami, Tatsuo Okada, Osamu Tsuruta, Kazuhiro Sawa, Kazuhiko Iigaki

ICONE 2014; V001T03A009https://doi.org/10.1115/ICONE22-30251

Abstract

View Articletitled, Structural Analysis for Assembly by Integrating Parts

PDF

Topics: Manufacturing , Structural analysis , Computers , Finite element analysis , High temperature , Nuclear power

Development of Deep Hole Drilling Technology for Tube Sheet of Steam Generator

Shinichiro Ueda, Takuya Yagishita, Jun Maeno, Masanari Okuda

ICONE 2014; V001T03A010https://doi.org/10.1115/ICONE22-30341

Abstract

View Articletitled, Development of Deep Hole Drilling Technology for Tube Sheet of Steam Generator

PDF

Topics: Boilers , Drilling , Cutting , Machinery , Stress , Drills (Tools) , Engines , Measurement systems , Motors , Nuclear power stations

Evaluation of Vibration Characteristics for Reactor Coolant Pump Considering Fluid Flow Effect

Ik Joong Kim, Min Chul Kim, Gyu Ho Jang, Dae Hee Jeong, Oak Sug Kim, Sang Youn Bang, Seong Hun Park

ICONE 2014; V001T03A011https://doi.org/10.1115/ICONE22-30356

Abstract

View Articletitled, Evaluation of Vibration Characteristics for Reactor Coolant Pump Considering Fluid Flow Effect

PDF

Topics: Fluid dynamics , Nuclear reactor coolants , Pumps , Vibration , Fluids , Finite element analysis , Bearings , Manufacturing , Rotors , Spectroscopy

The Use of Experimental Design for the Shrink-Fit Assembly of Multi-Ring Flywheel

Yujin Wang, DeZhong Wang, Junlian Yin, Yaoyu Hu

ICONE 2014; V001T03A012https://doi.org/10.1115/ICONE22-30359

Abstract

View Articletitled, The Use of Experimental Design for the Shrink-Fit Assembly of Multi-Ring Flywheel

PDF

Topics: Experimental design , Flywheels , Manufacturing , Coolants , Stress , Wall thickness , Damage , Design , Flow (Dynamics) , Fuels

Dynamic Stability Analysis of Cans in Reactor Coolant Pump Subjected to Axial Flow

Wenbo Ning, Dezhong Wang

ICONE 2014; V001T03A013https://doi.org/10.1115/ICONE22-30367

Abstract

View Articletitled, Dynamic Stability Analysis of Cans in Reactor Coolant Pump Subjected to Axial Flow

PDF

Topics: Axial flow , Dynamic stability , Nuclear reactor coolants , Pumps , Shells , Stability , Flow (Dynamics) , Fluids , Accidents , Buckling

3D FEA Elastoplastic Structural Analysis of Hypothetically Cracked Monju FBR Core Support Structures

Daniel Garcia-Rodriguez, Shinichiro Matsubara

ICONE 2014; V001T03A014https://doi.org/10.1115/ICONE22-30382

Abstract

View Articletitled, 3D FEA Elastoplastic Structural Analysis of Hypothetically Cracked Monju FBR Core Support Structures

PDF

Topics: Finite element analysis , Structural analysis , Shells , Accidents , Breeder reactors , Design , Earthquakes , Fracture (Materials) , Reliability , Solid models

Effect of Two-Phase Flow Structure in Decontamination Factor of Filtered Containment Venting System

Taizo Kanai, Masahiro Furuya, Takahiro Arai, Nobuyuki Tanaka, Yoshihisa Nishi, Kenetsu Shirakawa, Satoshi Nishimura, Masaaki Satake

ICONE 2014; V001T03A015https://doi.org/10.1115/ICONE22-30385

Abstract

View Articletitled, Effect of Two-Phase Flow Structure in Decontamination Factor of Filtered Containment Venting System

PDF

Topics: Containment , Decontamination , Two-phase flow , Vessels , Aerosols , Water , Mass spectrometry , Sodium , Steam , Test facilities

A Study of Heat Transfer Calculation Method of Reactor Vessel Metallic Insulation

Yan Dapeng, Ying Luo

ICONE 2014; V001T03A016https://doi.org/10.1115/ICONE22-30446

Abstract

View Articletitled, A Study of Heat Transfer Calculation Method of Reactor Vessel Metallic Insulation

PDF

Topics: Computational methods , Heat transfer , Metal insulation , Reactor vessels , Thermal conductivity , Temperature , Radiation (Physics) , Computer simulation , Corrosion , Geometry

Study on the Dynamic Characteristics of the Water-Lubricated Tilting-Pad Radial Bearing Considering Temperature-Viscosity Effect

Yu Li, Dezhong Wang, Weiguo Gu

ICONE 2014; V001T03A017https://doi.org/10.1115/ICONE22-30502

Abstract

View Articletitled, Study on the Dynamic Characteristics of the Water-Lubricated Tilting-Pad Radial Bearing Considering Temperature-Viscosity Effect

PDF

Topics: Bearings , Temperature , Viscosity , Water , Friction , Stress , Damping , Load bearing capacity , Stability , Stiffness

Numerical Analysis of Rotordynamic Coefficients of Annular Flow in Canned Motor RCP

Yaoyu Hu, Dezhong Wang, Junlian Yin, Yujin Wang

ICONE 2014; V001T03A018https://doi.org/10.1115/ICONE22-30511

Abstract

View Articletitled, Numerical Analysis of Rotordynamic Coefficients of Annular Flow in Canned Motor RCP

PDF

Topics: Engines , Flow (Dynamics) , Motors , Numerical analysis , Impellers , Axial flow , Computational fluid dynamics , Fluids , Nuclear reactor coolants , Nuclear reactors

Study on the Rod Drop Performance of High-Temperature Gas-Cooled Reactor

He Yan, Xingzhong Diao

ICONE 2014; V001T03A019https://doi.org/10.1115/ICONE22-30516

Abstract

View Articletitled, Study on the Rod Drop Performance of High-Temperature Gas-Cooled Reactor

PDF

Topics: Very high temperature reactors , Emergencies , Rods , Gravity (Force) , Pressure , Pressure vessels , Reactor vessels , Reliability , Safety , Scram

Buckling Analysis of Tube for Steam Generator According to ASME B&PV Code

Jungpyo Kong, Changhoon Ha, Minki Cho, Seunghoon Yeo, Tae-Jung Park

ICONE 2014; V001T03A020https://doi.org/10.1115/ICONE22-30598

Abstract

View Articletitled, Buckling Analysis of Tube for Steam Generator According to ASME B&PV Code

PDF

Topics: Boilers , Buckling , Pressure , External pressure , Collapse , Finite element analysis , Computer software , Eigenvalues , Failure , Heat transfer

Seismic Test on Double-Layer Model of HTR-PM Graphite Structure

Shigang Lai, Libin Sun, Li Shi, Zhengming Zhang

ICONE 2014; V001T03A021https://doi.org/10.1115/ICONE22-30600

Abstract

View Articletitled, Seismic Test on Double-Layer Model of HTR-PM Graphite Structure

PDF

Topics: Graphite , Excitation , Bricks , Manufacturing , Carbon , Displacement , Dynamic response , Bearings , Damping , Electromagnetic spectrum

Improvement of Probabilistic Fracture Mechanics Analysis Code for Reactor Piping Considering Large Earthquakes

Yoshihito Yamaguchi, Jinya Katsuyama, Makoto Udagawa, Kunio Onizawa, Yutaka Nishiyama, Yinsheng Li

ICONE 2014; V001T03A022https://doi.org/10.1115/ICONE22-30643

Abstract

View Articletitled, Improvement of Probabilistic Fracture Mechanics Analysis Code for Reactor Piping Considering Large Earthquakes

PDF

Topics: Earthquakes , Fracture mechanics , Pipes , Failure , Fracture (Materials) , Probability , Sensitivity analysis , Evaluation methods

Flow-Induced Vibration Suppression of Jet Pump in Boiling Water Reactor by Slip Joint Extension

Masanobu Watanabe, Kunihiko Kinugasa, Hiroyuki Adachi, Hajime Mori

ICONE 2014; V001T03A023https://doi.org/10.1115/ICONE22-30700

Abstract

View Articletitled, Flow-Induced Vibration Suppression of Jet Pump in Boiling Water Reactor by Slip Joint Extension

PDF

Topics: Boiling water reactors , Flow-induced vibrations , Jet pumps , Flow (Dynamics) , Vibration , Leakage , Damping , Diffusers , Leakage flows , Power uprate

Experimental Investigation Into Buckling Failure of Slender Metal Plates in Severe Accident Conditions

Byeongnam Jo, Wataru Sagawa, Koji Okamoto

ICONE 2014; V001T03A024https://doi.org/10.1115/ICONE22-30829

Abstract

View Articletitled, Experimental Investigation Into Buckling Failure of Slender Metal Plates in Severe Accident Conditions

PDF

Topics: Accidents , Buckling , Failure , Metals , Plates (structures) , Stress , Engineering simulation , High temperature , Simulation , Temperature

Sloshing Suppression Method for a Rectangular Pool Using Immersed Blocks and Baffle Plates

Urara Watanabe, Hiroshi Niwa, Akira Tsuyuki, Masahiko Warashina, Ryo Ito, Masanobu Watanabe

ICONE 2014; V001T03A025https://doi.org/10.1115/ICONE22-30893

Abstract

View Articletitled, Sloshing Suppression Method for a Rectangular Pool Using Immersed Blocks and Baffle Plates

PDF

Topics: Plates (structures) , Sloshing , Water , Excitation , Vibration tests , Waves , Earthquakes , Flow (Dynamics) , Spent fuel storage

Effect of Support Friction in Thermal Stress of VVER-1000 RCS for NOP Condition

Truong Quang Nguyen, Ihn Namgung

ICONE 2014; V001T03A026https://doi.org/10.1115/ICONE22-30904

Abstract

View Articletitled, Effect of Support Friction in Thermal Stress of VVER-1000 RCS for NOP Condition

PDF

Topics: Friction , Thermal stresses , Boilers , Reactor vessels , Temperature , Stress , Nozzles , Nuclear reactor coolants , Pumps , Yield stress

Fretting Wear of the Zr Fuel Rod Cladding

Ladislav Pecinka, Jaroslav Svoboda, Vladimír Zeman

ICONE 2014; V001T03A027https://doi.org/10.1115/ICONE22-31103

Abstract

View Articletitled, Fretting Wear of the Zr Fuel Rod Cladding

PDF

Topics: Cladding systems (Building) , Fuel rods , Wear , Zirconium , Fuels , Nuclear power stations , Pressurized water reactors , Damage , Failure , Flow (Dynamics)

Effects of Aging on the Thermal Conductivity of the AP1000® Containment Vessel Inorganic Zinc Coating

Thomas A. Kindred, Richard F. Wright

ICONE 2014; V001T03A028https://doi.org/10.1115/ICONE22-31157

Abstract

View Articletitled, Effects of Aging on the Thermal Conductivity of the AP1000® Containment Vessel Inorganic Zinc Coating

PDF

Topics: Containment vessels , Thermal conductivity , Zinc coatings , Containment , Shells , Coating processes , Coatings , Corrosion , Cooling , Design

Plant Event Signatures on Neutron Noise Data

Jianfeng Yang

ICONE 2014; V001T03A029https://doi.org/10.1115/ICONE22-31167

Abstract

View Articletitled, Plant Event Signatures on Neutron Noise Data

PDF

Topics: Neutrons , Noise (Sound) , Pressurized water reactors , Maintenance , Nuclear power stations , Power stations

Non-Linear Analysis of AP1000 Auxiliary and Shield Building Subjected to Combined Accident Thermal and Seismic Loadings

J. Jennifer Zhang, Lee J. Tunon-Sanjur

ICONE 2014; V001T03A030https://doi.org/10.1115/ICONE22-31263

Abstract

View Articletitled, Non-Linear Analysis of AP1000 Auxiliary and Shield Building Subjected to Combined Accident Thermal and Seismic Loadings

PDF

Topics: Accidents , Concrete cracking , Finite element model , Reinforced concrete , Computer simulation , Concretes , Design , Fracture (Materials) , Stiffness , Structural design

Codes, Standards, Licensing and Regulatory Issues

Comparison of ASME Code NB-3200 and NB-3600-Based Environmental Fatigue Calculations for Piping Components

Kyeongjin Yang, Daesu Kim, Dongjae Lee, Joonho Lee, Sangbae Lee, Inyeung Kim

ICONE 2014; V001T07A001https://doi.org/10.1115/ICONE22-30166

Abstract

View Articletitled, Comparison of ASME Code NB-3200 and NB-3600-Based Environmental Fatigue Calculations for Piping Components

PDF

Topics: ASME Standards , Fatigue , Pipes , Stress , Light water reactors , Accounting , Coolants , Design , Nuclear power stations , Piping design

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (2) Development of Evaluation Tools Based on LRFD

Hideo Machida, Tai Asayama, Daigo Watanabe, Kiminobu Hojo, Masaaki Hayashi

ICONE 2014; V001T07A002https://doi.org/10.1115/ICONE22-30525

Abstract

View Articletitled, Elaboration of the System Based Code Concept — Activities in JSME and ASME: (2) Development of Evaluation Tools Based on LRFD

PDF

Topics: Japan Society of Mechanical Engineers , Reliability , Collapse , Design , Bending (Stress) , Buckling , Cylinders , Failure , Failure mechanisms , Fatigue

Concept of Standard System Based on China Current Nuclear Power Construction

Yuelan Yan

ICONE 2014; V001T07A003https://doi.org/10.1115/ICONE22-30530

Abstract

View Articletitled, Concept of Standard System Based on China Current Nuclear Power Construction

PDF

Topics: China , Nuclear construction , Nuclear power , Construction , Nuclear power stations , Absorption , ASME Standards , Building codes , Design

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (1) Overview

Tai Asayama, Takayuki Miyagawa, Koji Dozaki, Yoshio Kamishima, Masaaki Hayashi, Hideo Machida

ICONE 2014; V001T07A004https://doi.org/10.1115/ICONE22-30567

Abstract

View Articletitled, Elaboration of the System Based Code Concept — Activities in JSME and ASME: (1) Overview

PDF

Topics: Japan Society of Mechanical Engineers , Reliability , ASME Boiler and Pressure Vessel Code , Collaboration , Design , Engineering standards , In-service inspection , Liquid metals , Mechanical engineers , Sodium fast reactors

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (3) Guidelines on Structural Reliability Evaluation for FBR

Shigeru Takaya, Hideo Machida, Yoshio Kamishima

ICONE 2014; V001T07A005https://doi.org/10.1115/ICONE22-30570

Abstract

View Articletitled, Elaboration of the System Based Code Concept — Activities in JSME and ASME: (3) Guidelines on Structural Reliability Evaluation for FBR

PDF

Topics: Japan Society of Mechanical Engineers , Reliability , Failure , Breeder reactors , Crack propagation , Creep , Damage , Fatigue , Modeling , Probability

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (4) Joint Efforts of JSME and ASME

Tai Asayama, Shigeru Takaya, Masaki Morishita, Frank Schaaf

ICONE 2014; V001T07A006https://doi.org/10.1115/ICONE22-30572

Abstract

View Articletitled, Elaboration of the System Based Code Concept — Activities in JSME and ASME: (4) Joint Efforts of JSME and ASME

PDF

Topics: Japan Society of Mechanical Engineers , ASME Boiler and Pressure Vessel Code , Flow (Dynamics) , In-service inspection , Liquid metals , Mechanical engineers , Safety , Sodium fast reactors

A Comparison of Creep-Fatigue Assessment and Modelling Methods

Rami H. Pohja, Stefan B. Holmström

ICONE 2014; V001T07A007https://doi.org/10.1115/ICONE22-30640

Abstract

View Articletitled, A Comparison of Creep-Fatigue Assessment and Modelling Methods

PDF

Topics: Creep , Fatigue , Modeling , Damage , Design , Cycles , Fatigue damage , Rupture , Steel , Tensile strength

Chinese Innovative Patent Technologies for the Reactor Pressure Vessel

Qian Shi, Tianqi Zhang, Xiang Fang, Wei Peng

ICONE 2014; V001T07A008https://doi.org/10.1115/ICONE22-30694

Abstract

View Articletitled, Chinese Innovative Patent Technologies for the Reactor Pressure Vessel

PDF

Topics: Patents , Reactor vessels , Nuclear power , China , Design , Safety , Containers , Design methodology , Economics , Innovation

Japanese Codes and Standards for Dual Purpose Metal Casks for Spent Nuclear Fuel

Toshiari Saegusa, Makoto Hirose, Norikazu Irie, Masashi Shimizu

ICONE 2014; V001T07A009https://doi.org/10.1115/ICONE22-30696

Abstract

View Articletitled, Japanese Codes and Standards for Dual Purpose Metal Casks for Spent Nuclear Fuel

PDF

Topics: Engineering standards , Metals , Spent nuclear fuels , Storage , Stress , Containment vessels , Japan Society of Mechanical Engineers , Safety , Design , Nuclear power stations

Comparison of Nuclear Fitness for Service Codes: ASME Section XI and RSE-M AFCEN Codes

Claude Faidy

ICONE 2014; V001T07A010https://doi.org/10.1115/ICONE22-30713

Abstract

View Articletitled, Comparison of Nuclear Fitness for Service Codes: ASME Section XI and RSE-M AFCEN Codes

PDF

Topics: Fitness-for-service , In-service inspection , Pressurized water reactors , Light water reactors , Maintenance , Nuclear power stations , Pressure , Surveillance , Boiling , Boiling water reactors

Fatigue Design Rules in Pressure Vessel Codes Uncertainties and Remaining Open Points

Claude Faidy

ICONE 2014; V001T07A011https://doi.org/10.1115/ICONE22-30715

Abstract

View Articletitled, Fatigue Design Rules in Pressure Vessel Codes Uncertainties and Remaining Open Points

PDF

Topics: Fatigue design , Pressure vessels , Uncertainty , Fatigue , Fatigue analysis , Materials properties , Boilers , Damage , Electromagnetic scattering , Fatigue testing

Global Materials Research as a Tool for Future Code Development

Wolfgang Hoffelner

ICONE 2014; V001T07A012https://doi.org/10.1115/ICONE22-30969

Abstract

View Articletitled, Global Materials Research as a Tool for Future Code Development

PDF

Topics: Materials research , Collaboration , Design , Nuclear power stations , Materials properties , Computers , Finite element analysis , Materials degradation , Power stations

Testing of Statistical Procedures for Use in Optimization of Reactor Performance Under Aged Conditions

Dumitru Serghiuta, John Tholammakkil, Naj Hammouda, Anthony O’Hagan

ICONE 2014; V001T07A013https://doi.org/10.1115/ICONE22-31054

Abstract

View Articletitled, Testing of Statistical Procedures for Use in Optimization of Reactor Performance Under Aged Conditions

PDF

Topics: Optimization , Testing , Algorithms , Design , Safety , Scalars

AP1000^® Plant Application of Defense in Depth

Terry L. Schulz, Julie Gorgemans

ICONE 2014; V001T07A014https://doi.org/10.1115/ICONE22-31058

Abstract

View Articletitled, AP1000® Plant Application of Defense in Depth

PDF

Topics: Defense industry , Safety , Plant design , Design , Pressurized water reactors , Accidents , Construction , Maintenance , Probabilistic risk assessment

Current Implementation of the Quality Assurance Program at the United States Los Alamos National Laboratory

Taunia Van Valkenburg, Ernie F. Petru, Paula R. Diepolder, Gary M. Sandquist

ICONE 2014; V001T07A015https://doi.org/10.1115/ICONE22-31059

Abstract

View Articletitled, Current Implementation of the Quality Assurance Program at the United States Los Alamos National Laboratory

PDF

Topics: Quality control , Design , Manufacturing , Project management , Risk , Weapons

Fatigue Assessment of Class 1 Nuclear Power Piping According to ASME BPV Code: Why Other Alternatives?

Lingfu Zeng, Lennart G. Jansson

ICONE 2014; V001T07A016https://doi.org/10.1115/ICONE22-31074

Abstract

View Articletitled, Fatigue Assessment of Class 1 Nuclear Power Piping According to ASME BPV Code: Why Other Alternatives?

PDF

Topics: Fatigue , Nuclear power , Pipes , Finite element analysis , Stress , ASME Boiler and Pressure Vessel Code , Damage , Design , Reliability

Technical Basis of Fatigue Crack Growth Rate Curve for Ni-Base Alloy in BWR Water Environment

Takuya Ogawa, Masao Itatani, Toshiyuki Saito, Hiroshi Nagase, Satoru Aoike, Hideki Yoneda

ICONE 2014; V001T07A017https://doi.org/10.1115/ICONE22-31143

Abstract

View Articletitled, Technical Basis of Fatigue Crack Growth Rate Curve for Ni-Base Alloy in BWR Water Environment

PDF

Topics: Alloys , Boiling water reactors , Fatigue cracks , Water , Stress , Fitness-for-service , Corrosion , Fracture (Materials) , Japan Society of Mechanical Engineers , ASTM International

Evaluation of Fatigue Life of Pressurized Water Reactor Internals Considering Light-Water Reactor Coolant Environmental Effect for Aging Management Program

Jianfeng Yang, Paul O’Brien

ICONE 2014; V001T07A018https://doi.org/10.1115/ICONE22-31169

Abstract

View Articletitled, Evaluation of Fatigue Life of Pressurized Water Reactor Internals Considering Light-Water Reactor Coolant Environmental Effect for Aging Management Program

PDF

Topics: Coolants , Fatigue life , Light water reactors , Pressurized water reactors , Fatigue , Design , Alloys , Cycles , ASME Boiler and Pressure Vessel Code , Carbon