Proceedings of the

17th International Conference

on Nuclear Engineering

- 2009 -

VOLUME 2

STRUCTURAL INTEGRITY

SAFETY AND SECURITY

ADVANCED APPLICATIONS OF NUCLEAR TECHNOLOGY

BALANCE OF PLANT FOR NUCLEAR APPLICATIONS

presented at

17th international conference on nuclear engineering

JULY 12-16, 2tsi»l*

BRUSSELS, BELCH A?

sponsored /»

nuclear engineering division, ASMI

THE JAPAN SOCIETY OF MECHANICAL ENGINEERS, JSMI

THE CHINESE NUCLEAR SOCIETY, C'V-

A S M E

Three Park Avenue New York, N.Y.

TIB/UB Hannover

133 265 536

10016

CONTENTS

STRUCTURAL INTEGRITY

ICONE17-75008 1

Development of a New Spacer Grid Form to Enhance the Integrity of Fuel Rod Support and

the Crush Strength of a Spacer Grid AssemblyKee-nam Song, Soo-bum Lee, Moon-Kyun Shin, Jae-Jun Lee, and Gyung-Jin Park

ICONE17-75081 11

A Comparative Parametric Study of Single Step and Double Step Swage Autofrettage in

Swaged Metal Tubes

Azaal M. Malik, Shahab Khushnood, Muddasar Khan, Ghutam Gilani, and

Musarrat Khan

ICONE17-75100 17

Investigation of Discrepancies in Waterhammer Structural Integrity Analysis Simulation

and Actual Vibration TestingKhalid Chaudhry and Andrei Blahoianu

ICONE17-75170 29

Reactor Vessel Closure Head Drop Analysis: Sensitivity Study on the Effects of

Representing Nonlinear Behavior in the Closure Head AssemblyWilliam C. Castillo, Joseph M. Hemic, III, George J. Demetri, Frank J. Marx, and

David H. Roarty

ICONE17-75175 37

Use of Shear Lugs for Anchorage to Concrete

Peter J. Carrato and Martin Reifschneider

ICONE17-75194 45

Detailed Engineering Customization: A Cost and Time Effective Approach in the

Manufacturing of Steel Structures

Ajaz Bashir Janjua, M. Shahid Khalil, and Sajjad Akbar

ICONE17-75203 53

Simulation of Vessel-With-Melt Deformation by SOCRAT/HEFEST Code

Alexander Filippov, Nikolay Drobyshevsky, Arkady Kiselev, and Valery Strizhov

ICONE17-75224 61

Assessment of Hill-Side Effect on RV CEDM Nozzles

Seung-Bum Ryu, Moon-Kil Park, Byeong-Wook Noh, and Jung-hun Lee

ICONE17-75225 67

Modeling and Simulation of Multi-Stage Autofrettage in Pressure Vessels

Afzaal M. Malik, Shahab Khushnood, Ghulam Gilani, Muddasar Khan, and

Musarrat Khan

vii

IC0NE17-75300 -75

Evaluation on the Behavior of Stacked Blocks Subject to a Harmonic Excitation

Woo-Seok Choi, Dong-Ok Kim, Keun-Bae Park, Jae-Man Noh, and Won-Jae Lee

ICONE17-75310 81

On Design Verification of Piping Supports Under Combined Stresses

Lennart G. Jansson and Lingfu Zeng

ICONE17-75330 89

Natural Crack Growth in BWR Shroud Support Dissimilar Metal Weld Joints

S. F. Hankinson, T. Hayashi, C. K. Ng, and S. A. Swamy

ICONE17-75349 97

The Use of Stochastic Models to Measure Damage Potential in Acceleration Time Series

Malek Brahimi, Sidi Berri, Abdelrazak Menasseri, and Abdelrachid Boulaouad

ICONE17-75355 101

Design by Analysis of Waste Packages at Yucca Mountain for Impact Loads

Randy J. James, Kenneth Jaquay, and Michael J. Anderson

ICOIME17-75433.... 113

FE Simulation of Welding Residual Stresses in Reactor Vessel Head Penetrations

Anne Teughels and Christian Maiekian

ICONE17-75436 123

Acoustic Loading of Steam Dryers: Load Attributes and Structural ResponseMichael Shehane, Eric M. Moore, and Arthur Ruggles

ICOIME17-75441 131

Stress Intensity Factors for Unusual Semi-Elliptical Surface Cracks With Ratio a/I Greater

Than 0.5

Christian Maiekian, Eric Wyart, Michael Savelsberg, David Lacroix, Nicolas Minjauw,

Audrey Wendling, and Anne Teughels

ICONE17-75459 143

Evaluation of the Isolation System Influence in the Seismic Loading Analysis Applied to a

Near Term Deployment Reactor

R. Lo Frano and G. Forasassi

ICONE17-75474 153

Nonlinear Analyses for Thermal Cracking in the Design of Concrete Structures

Randy J. James and Ai-Shen Liu

ICOIME17-75526 161

Contribution to the Design of Concrete Columns Reinforced With Externally Fiber Polymers

Ferran Prats Bella, Ramon Gonzalez-Drigo, and Adrina Bachiller Sana

ICOIME17-75547 171

Stress Classification Plane and Its Application in Finite Element AnalysisJianfeng Yang

viii

ICONE17-75565 181

An Approach for Assessing Fuel Assembly's Structural Integrity Under In-Core OperatingConditions Using Finite Element Method

Wei Zhao and Yuriy Aleshin

ICOIME17-75617 187

Analytical Investigation of Deaerator Steam Inlet Nozzle Corrosion Allowance in a

CAIMDU Station

Ali Keshavarz, Andrew K. AH, and Randy K. Lall

ICONE17-75649 197

Friction Welding of Mild Steel Components

Sajjad Akbar, M. Shahid Khalil, A. Bashir Janjua, and M. Amin

ICONE17-75661 205

Sensitivity Analysis by the Use of a Surrogate Model During Large Break LOCA on ZION

Nuclear Power Plant with CATHARE-2 V2.5 Code

Fabrice Fouet and Pierre Probst

ICONE17-75760 213

Wave Propagation Analysis of Piping Structures

Akemi Nishida

ICONE17-75797 221

The Development of Impact Analysis Methodology for CEDM Missile of APR1400

Tae Kyo Kang, Jin Seok Park, Hyun Min Kim, and In Yong Kim

ICONE17-75804 229

A Study of Some Key Parameters Used in the Environmental Fatigue Evaluation of a

Hot Leg Surge Nozzle

Tim F. Wiley, Tim J. Pournaras, Chris T. Kupper, Mark A. Gray, and Seth A. Swamy

ICOIME17-75814 235

Review of Recent Aging-Related Degradation Occurrences of Structures and Passive

Components in U. S. Nuclear Power Plants

Jinsuo Nie, Joseph I. Braverman, Charles H. Hofmayer, Young-Sun Choun,Min Kyu Kim, and In-Kil Choi

ICONE17-75825 245

Evaluation of Load-Time Functions Due to Impact of Soft Missiles

Daniela Ruch, Nico Herrmann, and Harald S. Muller

ICONE17-75858 253

Engineering Practices forTokamak Window Assemblies

C. Waldon, R. Morrell, D. Buckthorpe, M. Davies, and P. Sherlock

ICONE17-75916 265

Sensitivity Investigation of Specimen Shape on Elastic Behaviour of Perforated Plate

Chang-Hoon Ha, Tae-Jung Park, Moo-Yong Kim, Jae-Mean Koo, Chang-Sung Seok,

and Kwang-Sang Seon

ix

ICONE17-76002 273

A Study for the Practicality of the 3D Full Model in the SSI Analysis on the Nuclear

Power Plant

Youngsun Jang, Taeyoung Kim, Jongbo Lee, and Jonghak Kim

ICONE17-76059 281

Critical Velocity of Potential Flow in Interaction With a System of Plates

Y. Kerboua, A. A. Lakis, M. Thomas, L. Marcouilter, and M. H. Toorani

SAFETY AND SECURITY

ICONE17-75019 291

Research of Nuclear Power Plants Diagnosis Method Based on Data Fusion

Yong-kuo Liu, Hong Xia, and Chun-li Xie

ICONE17-75022 297

Seismic Isolation of Nuclear Structures by a Non-Oscillating System SERB TypeViorel Serban, Adrian Panait, Marian Androne, and George Alexandru Ciocan

ICONE17-75029 307

Approach on Component Selection for Ageing-Trend Analysis Within PSA Models

Shahen Poghosyan, Armen Amirjanyan, and Albert Malkhasyan

ICONE17-75039 313

Modelling of Material Properties Influence in Fuel-Coolant Interaction Codes

Mitja Ursic, Matjai Leskovar, Ivo Kljenak, and Borut Mavko

ICONE17-75071 323

On the Use of Binary Importance Decision for Risk-Informed Categorization of SSCs

Wei Zeng and Hongxing Yu

ICONE17-75078 331

Water-Ingress Accident of the 250MW Pebble-Bed Modular High TemperatureGas-Cooled Reactor

Zheng Yanhua and Shi Lei

ICONE17-75099 341

Analysis of the Quench-14 Bundle Test With M5® CladdingJonathan C. Birchley, Bernd Jaeckel, Martin Steinbriick, Juri Stuckert, and

Timothy J. Haste

ICONE17-75128 349

The Limit Exceedance Factor Importance Measure: An Application to the Prism

Reactor DesignB. C. Johnson and G. E. Apostolakis

ICONE17-75145 355

Validation of Calculated Skyshine Dose From Turbine Building by Using MCNP5 With

Experimental Data at Shimane Nuclear Power Station

Ryuichi Tayama, Kenichi Wakasugi, Ikunori Kawanaka, Yoshinobu Kadota, and

Yasuhiro Murakami

x

IC0NE17-75159 361

Numerical Simulation of the Behavior of Fission Products in the Primary Circuit of the VVER

During the LOCA Severe Accident

S. V. Tsaun, V. V. Bezlepkin, A. E. Kiselev, I. A. Potapov, V. F. Strizhov, and L I. Zaichik

iCOIMEl7-75177 369

Vulnerability of Nuclear Power Plants to Voltage Sag Induced by Disturbances in the

Transmission Grid: The Concept of Zone of Vulnerability for VoltageNick Abi-Samra, Alberto Del Rosso, and Frank Rahn

ICONE17-75196 379

Verification of Modified SCDAP/RELAP5 Against CANDU Fuel Deformation

Experimental Results

Mirea Mladin, Daniel Dupleac, and Hie Prisecaru

ICONE17-75211 387

Analysis of Rod Ejection Accident in a Research Reactor by the Coupled Code TechniqueTewfik Hamidouche, El Khider Si-Ahmed, Anis Bousbia-Salah, and Jack Legrand

ICOIMEl 7-75219 395

Natural Circulation and Creep Damage Analyses of Severe Accident for a TypicalPWR Plant

Osamu Kawabata and Masao Ogino

ICOIMEl 7-75223 403

Analytical Evaluation of Core Bowing Reactivity in the 4S Reactor

Satoshi Nishimura, Hirokazu Ohta, and Nobuyuki Ueda

ICOIME17-75227 413

Protection and Monitoring of Ionizing Radiation: Nuclear Medicine

Sajjad Akbar, M. Shahid Khalil, and Shahzad Ahmad

ICOIMEl 7-75239 421

Preliminary Analysis of Effect of the Intentional Depressurization on Fission Product

Behavior During TMLB' Severe Accident

Gaofeng Huang, Lili Tongr and Xuewu Cao

ICONE17-75249 427

Implementation of a Pressure Drop Model for the CFD Simulation of Clogged Containment

Sump Strainers

Alexander Grahn, Eckhard Krepper, Soren Alt, Wolfgang Kastner, Frank-Peter We/73,Alexander Kratzsch, and Rainer Hampel

ICOIME17-75252 439

Successive Accident Frequency Assessment From Initiating Event to Containment Failure

Naoki Hirokawa, Mitsuru Yoneyama, and Chikahiro Sato

ICOIME17-75263 445

Evaluation of Monju Core Damage Risk With Change of AOT Using Probabilistic Method

Masutake Sotsu and Kenichi Kurisaka

xi

ICOIME17-75266 455

Experimental Results of Reflood Bundle Test QUENCH-14 With M5® Cladding Tubes

Juri Stuckert, Mirco GroBe, Leo Sepold, and Martin Steinbruck

ICONE17-75304 463

Network Computing Infrastructure to Share Tools and Data in GNEP

Guehee Kim, Yoshio Suzuki, and Naoya Teshima

ICONE17-75306 471

A New Simulation Code for Analyzing Loss of Coolant Accidents in VVER-440/213 Reactors

Concerning Activity TransportAttila Madaras, Sandor Deme, Zoltan Hdzer, Edit Lang, Istvan Nemeth, Tamas Pazmandi,

and Peter Szanto

ICOIME17-75352 477

On-Line Workload Assessment by the PET Method

Gueorgui Petkov, Vladislav Georgiev, and Emil Stefanov

ICONE17-75360 483

Sources of Uncertainty in a Fire Probabilistic Safety Assessment

Stephen P. Meyer

ICOIME17-75364.. 487

Analysis and Characterization of Sequences in Atucha II PHWR

Pablo Zanocco, Jose Gonzalez, and Marcelo Gimenez

ICONE17-75365 495

RELAP Model for Atucha II PHWR

M. Schivo, G. Bedrossian, J. Gonzalez, P. Zanocco, M. Gimenez, M. Caputo, P. Serrano,

and 0. Mazzantini

ICONE17-75384 505

Safety Aspects of a PWR With an Inventive TRISO Fuel Particle CompositionAnwar Hussain and Cao Xinrong

ICONE17-75398 511

Investigation of Chemical Effects on Emergency Core Cooling Filtration Head Loss After

Loss of Coolant Accident

Jong Woon Park, Byung Gi Park, and Chang Hyun Kim

ICONE17-75414 519

ASTEC, COCOSYS, and LIRIC Interpretation of the Iodine Behaviour in the Large-ScaleTHAI Test lod-9

G. Weber, L. Bosland, F. Funke, G. Glowa, and T. Kanzleiter

ICONE17-75450 533

Core Melt Solidification Characteristics in RPV Lower Head-Experimental Results From

LIVE-Tests

Xiaoyang Gaus-Liu, Alexei Miassoedov, Thomas Cron, Jerzy Foit, Thomas Wenz, and

Silke Schmidt-Stiefel

xii

ICONE17-75455 541

Analysis of a BWR ATWS With Boron InjectionMarcus Eriksson and Ulf Bredolt

ICONE17-75456 551

Ex-Vessel Coolability Analysis for a Belgian NPP

Jarne R. Verpoorten, Michele Auglaire, and Frank Bertels

ICONE17-75457 563

Approach for the Analysis of a Shutdown Scenario in the Framework of the Validation of

Severe Accident Management Guidelines in BelgiumAntonio Cipollaro and Laurent Sallus

1COIME17-75464 575

A Hybrid Qualitative/Quantitative Uncertainty Importance Assessment Approach:Applications to Thermal-Hydraulics System Codes Calculations

Mohammad Pourgol-Mohammad and Kamran Sepanloo

ICONE17-75472 583

Validation of Severe Accident Management Guidance in BelgiumLaurence Oury, Zeynab Umidova, Michele Auglaire, and Antonio Cipollaro

ICONE17-75517 593

Fire PRA Database Development and ApplicationsChris Rochon, Babara R. Baron, Clarence L. Worrell, and Mark A. Ferrel

ICONE17 75518 601

New Approach for Environmental Protection During Severe Accidents at Nuclear

Power Plants

S. A. Kulyukhin, N. B. Mikheev, L. N. Falkovskii, L. A. Reshetov, M, Ya. Zvetkova,

V. P. Osipov, I. V. Yagodkin, S. S. Skvortsov, V. M. Berkovich, G. S. Taranov,M. M. Grigor'ev, A. A. Noskov, M. I. Mitrofanov, and V. M. Meshkov

ICONE17-75550 611

Quantification of the RELAP5 Model Uncertainty for Application to the Loss-Of-RHR Event

During the Mid-Loop OperationIkuo Kinoshita, Hiroichi Nagumo, Minoru Yamada, Yasuhiro Sasaki, and

Yoshitaka Yoshida

ICOIME17-75562 623

Closed Model for Calculation of Differential Pressure After a Loss of Coolant Accident in

Boiling Water Reactors

Alexander Kratzsch, Rainer Hampel, and Wolfgang Kastner

ICONE17-75595 629

Improvements in the German Fire PSA Methodology Demonstrated at a German BWR

Built to Earlier Standards

M. Rowekamp, O. Riese, and H. P. Berg

xiii

IC0NE17-75681 639

Reliability Analysis by Multilevel Flow Models: A Qualitative Analysis Method and Its

Application for FTA Validation

Ming Yang, Zhijian Zhang, Jie Liu, and Shengyuan Yan

ICONE17-75684 649

A Bayesian Framework for Model Uncertainty Considerations in Fire Simulation Codes

Mohammadreza Azarkhail, Victor Ontiveros, and Mohammad Modarres

ICONE17-75708 657

Break-Up of Gas Stratification in LWR Containment Induced by Negatively BuoyantJets and Plumes

Ralf Kapulla, Domenico Paladino, Guillaume Mignot, Robert Zboray, and Sanjeev Gupta

ICOIME17-75729 667

Safety Analysis of the Control Rod Drop Event Applying 3-D Neutronics/Thermal-HydraulicsCoupling Code SPARKLE

Yuta Maruyama, Satoshi Imura, Junto Ogawa, and Shuhei Miyake

ICONE17-75805 677

Lessons Learned and Insights From Implementation of EPRI Guidelines on Internal

Flooding at Fort Calhoun Station

Daniel L Sadlon, Rupert A. Weston, Raymond E. Schneider, John J. Fluehr III, andHarold A. Hackerott

ICONE17-75827 685

The Gasification of Graphite Matrix in Pebble Bed Reactors

Xinli Yu and Suyuan Yu

9CONE17-75852 691

Potential Ways to Modify the NRC Safety Goal PolicySteven A. Arndt and Richard Denning

IC0NE17-75861 699

Human Reliability, Experience and Error Probability: A New Benchmark

Romney B. Duffey and Tae Sung Ha

ICONE17-75881 705

MELCOR/VISOR PWR Desktop Simulator for Accident Analysis and TrainingAnka de With, Pieter H. Wakker, and Marcel L. F. Slootman

ICONE17-75887 713

Lessons Learned in Reviewing CCF Events

Ashley Mossa and Rupert Weston

ICOIME17-75927 719

Gas Phase Oxidation of Elemental Iodine in Containment Conditions

Teemu Karkela, Joachim Holm, Ari Auvinen, Christian Ekberg, Henrik Glanneskog,Unto Tapper, and Riitta Zilliacus

xiv

1C0NE17-75931 729

Assessment of Reliability of Emergency Core Cooling System (ECCS) of Bushehr

Nuclear Power Plant

Mohammad Sotoudeh and Kamran Sepanloo

ICONE17-75942 735

Experimental Investigation of Non-Condensable Gases Effect on Novovoronezh NPP-2

Steam Generator Condensation Power Under the Condition of Passive Safety Systems

Operation/. /. Kopytov, S. G. Kalyakin, V. M. Berkovich, O. V. Remizov, and A. V. Morozov

ICOIME17-75946 745

Effects of Ruthenium Release in Oxidizing Conditions on a BWR Source Term

Atso Suopajarvi, Teemu Karkeia, Ari Auvinen, and llona Lindholm

1COIME17-75972 751

Point Lepreau Refurbishment Project Level 2 PSA ApplicationsL. Comanescu, S. Sawh, M. Wei, B. Lee, A, Petrescu, A. F. Jean, D. F. Basque,

D. S. Mullin, A. Nainer, and R. K. Jaitly

ICONE17-76026 757

Westinghouse AP1000 Solution to Long-Term Cooling Debris Concerns

Terry L. Schulz, Timothy S. Andreychek, Yong J. Song, and Kevin F. McNamee

ICOINIE17-76033 765

Best Estimate Simulation and Uncertainty Analysis of LB LOCA for KudanKulam

VVER-1000 NPP

Luben Sabotinov, Abhishek Srivastava, and Pierre Probst

ICONE17-76042 777

Point Kinetics LOCA Scenarios Assessment at the Using of Hafnium Absorber in Advanced

CANDU Fuel Designslosif Prodea, Cristina Alice Margeanu, Hie Prisecaru, and Nicoiae Danila

ICONE17-76048 785

ACR-1000 Level 1 PSA SummaryU. Menon, S. Aprodu, R. Bettig, R. Henderson, T. Ha, P. Iliescu, B. Karimi, M. El-Mansi,

J. Robinson, K. Torabi, E. Eman, J. Wu, and P. Santamaura

ADVANCED APPLICATIONS OF NUCLEAR TECHNOLOGY

ICONE17-75052 793

Analysis for Digital Pulse Waveform of Cd (Zn) Te Detector

Yu-ming Di, Zhan-liang Li, Guo-Ming Fang, Feng Han, Xiao-lin Qiu, and Yuelei Wu

ICONE17-75141 799

Characteristics and Operation of Neutron Transmutation Doping in HANARO Reactor

Sang-Jun Park, Myong-Seop Kim, Ki-Doo Kang, and In-Cheol Lim

xv

IC0NE17-75229 807

Development of the CAD/MCNP Automatic Conversion Code GEOMIT

Hesham R. Nasif, Fukuzo Masuda, Hiromasa lida, Hidetsugu Morota, Satoshi Sato, and

Chikara Konno

ICONE17-75326 815

Allegro: The European Gas Fast Reactor Demonstrator ProjectChristian Poette, Valerie Brun-Magaud, Franck Morin, Jean-Frangois Pignatel,

Richard Stainsby, and Konstantin Mikityuk

ICONE17-75407 823

Development of a New Monte-Carlo Treatment Planning System for Boron Neutron

Capture TherapyHiroaki Kumada, Takemi Nakamura, Akira Matsumura, and Koji Ono

ICONE17-75417 831

Test Results From the Idaho National Laboratory 15kW High Temperature ElectrolysisTest Facility

Carl M. Stoots, Keith G. Condie, James E. O'Brien, J. Stephen Herring, and

Joseph J. Hartvigsen

ICONE17-75434 843

The 30 MeV Proton Beam Emittance Measurement via a Designed and Constructed Wire

Scanner and Using WinAGILE Beam Transport Code

Mitra Ghergherehchi, Ahmad Mohammadzadeh, and Hossein Afarideh

ICONE17-75473 847

System Analyses of High and Low-Temperature Interface Designs for a Nuclear-Driven

High-Temperature Electrolysis Hydrogen Production Plant

E. A. Harvego, J. E. O'Brien, and M, G. McKellar

ICONE17-75557 857

Current Status and Performance of the J-PARC Accelerators

Hiroyuki Sako

ICONE17-75579 867

Design of CT Reconstruction Software Based on the Air Container CT Inspection SystemJinhui Liu, Xincheng Xiang, and Zhifang Wu

ICONE17-75702 875

The Coupling of Nuclear Heat and Hydrogen Production Thermochemical CyclesZhaolin Wang, Greg Naterer, Kamiel S. Gabriel, Rob Gravelsins, and Venkata Daggupati

ICONE17-75787 885

Advanced Studies on Plutonium for Pu Isotope Transmutation and Pu SeparationAshraf Elasyed Mohamed Mohamed

ICONE17-75811 891

Evolving Innovative Reactor Design; Putting the I Into R&D

Romney Duffey and Hussam Khartabil

xvi

IC0NE17-75898 897

Non-Proliferative, Thorium-Based, Core and Fuel Cycle for Pressurized Water Reactors

Gilad Raitses, Michael Todosow, and Alex Galperin

ICONE17-75906 905

Advanced Application of BNCT in Advanced Cancers

Manue L. I. Sztejnberg and Tatjana Jevremovic

ICONE17-75907 915

iMASS: Evolved NRF Simulations for More Accurate Detection of Nuclear Threats

John Perry, Shanjie Xiao, and Tatjana Jevremovic

ICONE17-75939 923

Optimization of Dead-Layer Thickness for a HPGe Detector Using UCODE-MCNP Codes

Noha Shaaban, Wael El Gammal, and Hesham Nasif

ICONE17-75949 931

Why Massive Nuclear Deployment is Essential

Alistair I. Miller and Romney 8. Duffey

IC0IME17-76031 937

Experimental and Research Study of Novel Nuclear Concepts (Survey of Current Results

of ISTC Programs)L. V. Tocheny

BALANCE OF PLANT FOR NUCLEAR APPLICATIONS

ICONE17-75006 - 945

STP Balance of Plant Model Update Experience and Results

Ernie Kee, Fatma Yilmaz, Don Wakefield, and Steve Epstein

ICONE17-75087 955

A Lifecycle Management Program for NPP Turbine Balance of Plant

Toshinari Kawai, Katsuhiko Yamakami, Satoshi Hiraoka, and Jun Manabe

ICOIME17-75406 965

Equipment Reliability Based Ageing and Lifetime Management for Asco and Vandellos

Nuclear Power Plants

Xavier Jardi, Miguel Garcia, Xavier Castelo, Luis Martinez, and Isabel Mach

ICONE17-75490 975

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

Magnus Langenstein and Bemd Laipple

ICONE17-75527 983

A Comparative Study of Methodologies for Determining Plant Availabilities and

Initiator FrequenciesErnie Kee, Fatma Yilmaz, and Paul Nelson

xvii

IC0NE17-75546 993

Electrical Network Modeling and Electrical Transfer Simulation of C.N. Asco I and

C.N. Asco II, to Obtain Voltage and Frequency Limit Values Allowing the Electrical Transfer

From the Main Generator to the External 110kV Power Grid

Alberto Band Azcon and Jose Mollera Barriga

ICONE17-75602 1003

A Modern Approach to Condition-Based Maintenance of Reinforced Rubber CoolingSystem Expansion Joints Utilizing a Microwave Non-Destructive Inspection Method

Jack Little and Bob Stakenborghs

ICONE17-75743 1011

Simplified Approach to Establishing Bounding Main Steam Piping Support Load Increase

Due to Reactor Power UprateRobert Stakenborghs and Lindsey Dziuba

ICOIME17-76029 1021

Study on Pipe Wastage Mechanism by Liquid Droplet Impingement Erosion

Yuma Higashi, Tadashi Narabayashi, Yoichiro Shimazu, Masashi Tsuji, Shuichi Ohmori,

Michitsugu Mori, and Kenichi Tezuka

Author Index 1029

xviii