Proceedings of the

1 7th International Conference

on Nuclear Engineering

- 2009 -

VOLUME 1

PLANT OPERATIONS, MAINTENANCE,ENGINEERING, MODIFICATIONS AND LIFE CYCLE

COMPONENT RELIABILITY AND MATERIALS ISSUES

NEXT GENERATION SYSTEMS

presented at

17th INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING

JULY 12-16, 2009

BRUSSELS, BELGIUM

sponsored byNUCLEAR ENGINEERING DIVISION, ASME

THE JAPAN SOCIETY OF MECHANICAL ENGINEERS, JSME

THE CHINESE NUCLEAR SOCIETY, CNS

ASME

Three Park Avenue New York, N.Y. 10016

CONTENTS

PLANT OPERATIONS, MAINTENANCE, ENGINEERING,

MODIFICATIONS AND LIFE CYCLE

ICONE17-75058 1

Implementing Improvements to Nuclear Asset ManagementJessica Granger, Stephen M. Hess, and Charles A. Mengers

IC0NE17-75064 11

Risk-Informed Safety Margin Characterization

Stephen M. Hess, Nam Dinh, John P. Gaertner, and Ronaldo Szilard

ICONE17-75086 19

Integration of Degradation Models Into Generation Risk Assessment (GRA):

Challenges and Modeling ApproachesMikko I. Jyrkama, Mahesh D. Pandey, and Stephen M. Hess

ICONE17-75096 29

Actual Problems of VVER SG Tubing Service Life ManagementN. B. Trunov, V. S. Popadchuk, S. E. Davidenko, and Ft. Ju. Zhukov

ICONE17-75126 37

Ageing Management Status of HANARO Research Reactor

Hyungkyoo Kim, Hoansung Jung, Incheol Lim, Yeonggarp Cho, Jeongsoo Ryu, and

Youngchul Park

ICONE17-75162 43

Automated Operation With Redundant Ultrasonic Reactor Water Level Monitoring SystemVahid Askari

ICONE17-75315 49

Support for Component Monitoring and Condition-Based Maintenance of Heat Exchangersby Means of Data Validation

Ulrike Gocht, Michael Wagenknecht, Jana Haenel, Anke Traichel, and Michael Klein

ICONE17-75331 53

Managing CANDU Plant Ageing Using a Risk Informed Engineering ApproachKeith S. Dinnie

ICONE17-75333 61

New Non-Destructive Condition Monitoring Techniques for On-Site Assessment of

Low-Voltage Cables

Fabrice M. Guerout, Ladji Cisse, and Richard Boor

ICONE17-75337 71

Student Training Course Using the Experimental Fast Reactor Joyo and Related Facilities

Takafumi Aoyama, Chikara Ito, Yasushi Ohkawachi, Shigetaka Maeda, Soju Suzuki,

Keiji Chatani, and Toshikazu Takeda

vii

ICONE17-75341 81

Making FAC Calculations With BRT-CICERO and Updating to Version 3.0

Stephane Trevin, Matthieu Persoz, and Thomas Knook

ICONE17-75359 89

Aging Evaluation for the Extension of Qualified Life of Nuclear Power Plant Equipment

Through Modulated Poisson Processes

Pedro L. C. Saldanha and P. F. Frutuoso e Melo

ICONE17-75587 99

Remote-Controlled Inspection Robot for Nuclear Facilities in Underwater Environment

Harunobu Okihana, Keiji Iwata, and Yasuhiro Miwa

ICONE17-75642 -105

An Application of Main Steam Flow-Based Power Monitoring to OPR1000 Plants

Byung Ryul Jung, In Ho Song, Jung Hoon Kim, Byung Jin Lee, Se Jin Baik,

Joon Sung Kim, Jong Sun Lee, and Teuk Ki Choe

ICONE17-75671 111

Construction Aspects of the Doel 1 and 2 SGR ProjectsBert Kroes, Edmond Gobert, Xavier Delhaye, Peter Devolder, and Michel Sonville

ICONE17-75709 119

Application of Risk-Informed Methods to Improve Plant Operation at KozloduyNuclear Power Plant

Emil Kichev, Ivan Ivanov, Kaliopa Mancheva, Yasen Petrov, Vesselina Vladimirova,Gerald Andre, and Paul Stevenson

ICOIME17-75756 133

A Simple and Reliable System for Detecting and Measuring Gas Voids in Safety-RelatedFluid Systems

Herb Estrada and Ernest M. Hauser

ICONE17-75788 137

Aging Management of Nuclear Power Plant Reactor Internals

Frank J. Marx, Randy G. Lott, Cheryl L. Boggess, and Anne Demma

ICONE17-75795 145

The Application of Noise Analysis to Find the Miss-Connected LPRM Cables Before

Plant StartupOsamu Kubota, Akira Maki, and Tomomichi Uegata

ICONE17-75801 151

Economic Analysis Regarding the Introduction of a CANFLEX-IMU Fuel Into Wolsong Units

J. H. Park, J. Y. Jung, D. H. Kang, and P. W. Moon

ICONE17-75808 157

Seismic Spans for Cold Piping Based on Simplified Dynamic Analysis in APR1400

Joon-Ho Lee, Jae-Hwan Bae, In-Yeung Kim, andJik-Lae Jo

viii

ICONE17-75817 165

Development of Repair Technologies for J-Groove Welds of Drain and Instrument

Nozzle in Steam Generator

Kwang Soo Park, Chang Sig Kong, Seon Ho Lee, and Woo Sung Kim

ICONE17-75833 171

Condition Monitoring of Electrical Cables Using Line Resonance Analysis (LIRA)

Paolo F. Fantoni

ICOIME17-75843 179

The Utilization of the CMS (Condition Monitoring System) for the CBM

(Condition-Based Maintenance)

Hidetsugu Morota, Toshimitsu Miyazono, and Tatsuro Okumura

ICOIME17-75866 187

Application of the Relative Power Contribution Methodology to the Analysis of a

Control System Failure

Rogelio Castillo-Duran, Javier Ortiz-Villafuerte, Rodolfo Amador-Garcia,Edmundo del-Valle-Gallegos, Javier C. Palacios-Hernandez, and

Gabriel Calleros-Micheland

ICONE17-75874,

193

Development of Canned Motor Pump for Nuclear ApplicationNitin N. Page and Jagadish T. Kshisagar

ICON E17-75885 201

Power Uprate Impact Evaluations on Waste Heat of Nuclear Power Plants in Taiwan

Jinn-Jer Peir, Chun-Kuan Shih, Bau-Shei Pet, Yuh-Ming Ferng, and Wen-Sheng Hsu

ICOIME17-75897 209

The Impact of Flow Accelerated Corrosion (FAC) on Feeder Life Cycle ManagementMahesh D. Pandey, Mikko I. Jyrkama, and Edward M. Lehockey

ICONE17-75914 217

Performance Evaluation of Japanese Nuclear Power Plant Based on

Open Data and Information

Tadahisa Nagata and Ken-ichiro Sugiyama

ICONE17-75940 225

Measuring Surface Indications in Polyethylene PipingFrank J. Schaaf, Jr., Ernie W. McElroy, S. Steven teller, Jr., and Rachel L. Doss

ICONE17-76001 235

A New Shape of Expansion Loop to Compensate Thermal Expansion of Piping SystemsAurel M. Alessandrescu

ICONE17-76008 243

35 Years of Operating Experience of PHENIX NPP Sodium Cooled Fast Reactor

Didier Dall'Ava, Laurent Martin, and Bernard Vray

ICONE17-76050 255

Bayesian Nonparametric Analysis of Single Item Preventive Maintenance Strategies

Dmitriy Belyi, Paul Damien, Ernie Kee, David Morton, Elmira Popova, and Drew Richards

ix

COMPONENT RELIABILITY AND MATERIALS ISSUES

ICONE17-75025 263

The Influence of Chrome in the Oxidation Process of Steels in Flowing LBE

Taide Tan and Yitung Chen

ICON El 7-75027 269

Development of a SH Wave Single Unit Electromagnetic Acoustic Transducer (EMAT) for

MONJU Reactor Vessel In-Service InspectionYang Xu, Akihiro Tagawa, Kazunari Fujiki, Masashi Ueda, and Takuya Yamashita

ICONE17-75033 279Effect of PWHT Cycles on Impact Toughness of Austenitic Stainless Steel Weldments

M. M. Ibrahim, H. G. Mohamed, and Y. E. Tawfik

ICONE17-75063 289

Investigation of the Beltline Welding Seam and Base Metal of the Greifswald

WWER-440 Unit 1 Reactor Pressure Vessel

Jan Schuhknecht, Hans-Werner Viehrig, and Udo Rindelhardt

ICONE17-75108 297Positron Defect Studies of Neutron Irradiated Iron-Based Materials

Marlies Lambrecht and Abderrahim Almazouzi

ICONE17-75121 307Corrosion Behavior of FBR Structural Materials in High Temperature Supercritical C02

Tomohiro Furukawa, Yoshiyuki Inagaki, and Masanori Aritomi

ICONE17-75124 313

Temper-Bead Weld by Underwater Laser Beam WeldingTakeshi Fukuda, Wataru Kono, Masataka Tamura, Rie Sumiya, Nobuichi Suezono, and

Itaru Chida

ICONE17-75138 319

Development of Multifunction Laser Welding Head as Maintenance Technologies AgainstStress Corrosion Cracking for Nuclear Power Reactors

Itaru Chida, Naruhiko Mukai, Wataru Kono, Takahiro Miura, and Masaki Yoda

ICONE17-75195 327Effect of N Content on Mechanical Properties and Microstructure of Alloy 690

Kui Liu, Xianchao Hao, Ming Gao, Shuo Li, Yiyi Li, and Bofang Wan

ICONE17-75206 337Effect of Environmental and Material Conditions on SCC of Carbon Steels in HighTemperature Water

Sue Liu and Michael D. Wright

ICONEl 7-75209 351Mechanical Resistance in Liquid Lead-Bismuth of 316L/T91 Welded by Electron Beam

Ingrid Serre and Jean-Bernard Vogt

x

IC0NE17-75213 361

Corrosion Inhibition of Carbon Steel in Cooling System Media by Non-Toxic Linear

Sodium Octanoate

A. H. AH, O. E. Abdel Salam, A. F. Waheed, and H. Abdel-Karim

ICONE17-75215 371

Nondestructive Evaluation of Neutron Irradiation Damage on Austenitic Stainless Steels byMeasurement of Magnetic Flux Density

Shigeru Takaya, Yuji Nagae, Kazumi Aoto, Ichiro Yamagata, Shoichi Ichikawa,

Shotaro Konno, Ryuichiro Ogawa, and Eiichi Wakai

ICONE17-75233 375

Fracture Toughness Estimation for Small CT Specimen of Austenitic Stainless Steels UsingStretched Zone Width

Tadahiko Torimaru, Masanari Sugiyama, Hiroshi Sakamoto, Shigeaki Tanaka, and

Tomomi Nakamura

ICONE17-75255 387

A Review of Neural Network Application for Fault Diagnosis of NPP

He Wang

ICONE17-75272 393

Residual Life Assessment of Steam Generators with Alloy 600TT Tubing:Methods and Application

Ian de Curieres, Marie-Christine Meunier, and Pierre Joly

ICONE17-75274 401

Evolution of Microstructure, Microtexture and Texture in Dilute Zirconium Based Structural

Components of Pressurised Heavy Water Reactors

D. Srivastava, K. V. Mani Krishna, S. Neogy, G. K. Dey, I. Samajdar, and S. Banerjee

ICONE17-75292 411

Modelling of Fe-Cr Martensitic Steels Corrosion in Liquid Lead AlloysF. Balbaud-Celerier and L. Martinelli

ICONE17-75320 423

Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor

Pressure Vessel Steels

Naoki Soneda and Akiyoshi Nomoto

ICONE17-75322 431

Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessel

Steels in JapanNorimichi Yamashita, Masanobu Iwasaki, Koji Dozaki, and Naoki Soneda

ICONE17-75332-

441

Fatigue Flaw Tolerance Evaluation of Pressurizer Surge Line for Plant License

Renewal ApplicationsC. K. Ng, S. F. Hankinson, M. Salac, and S. A. Swamy

xi

ICONE17-75340 449

Analysis of Emerging NDE Techniques: Methods for Evaluating and ImplementingContinuous Online Monitoring

Stephen E. Cumblidge, Steven R. Doctor, Leonard J. Bond, Tom T. Taylor,

Timothy Ft. Lupoid, Amy B. Hull, and Shah N. Malik

ICONE17-75366 459

Bayesian Analysis of Piping Failure Frequency Using OECD/NEA Data

M. Wang, M. D. Pandey, and J. Riznic

ICONE17-75371 469

Operating Experience With Mechanical Seals in Reactor Shutdown Cooling PumpsG. Staniewski, A. Keshavarz, and W. J. Ferguson

ICOIME17-75378 481

Selection of Metal Electrodes for and Effect of Welding Treatment on Hardness and

Microstructure of Some Type of Austenitic Stainless Steels

M. M. Ibrahim, H. G. Mohamed, and Y. E. Tawfik

ICONE17-75416 493

Flow and Mass Transfer in Bends Under Flow-Accelerated Corrosion Wall ThinningConditions

John M. Pietralik and Chris S. Schefski

ICONE17-75420 503

The Impact of Probabilistic Modelling on Predicting the Remaining Life of Pipes in

Nuclear Plants

M. D. Pandey, D. Lu, and D. Komljenovic

ICONE17-75442 513

Flow Accelerated Corrosion Program in the Belgian Power Plants

Anne-Sophie Bogaert, Michel Desmet, and Arnaud Gendebien

ICONE17-75445 521

Situation of the Baffle-Former Bolts in Belgian Units

Robert Gerard and Frederic Somville

ICONE17-75485 529

Knowledge-Based Information Resource Management System for Materials of

Fast Reactors

Hsuan-Tsung (Sean) Hsieh, Ning Li, Yitung Chen, Kenny Kwan, Jen-Yuan Huang, and

Chang-Yeol Lee

ICONE17-75486 535

Fatigue Crack Growth Life Prediction of an Extruded Thick-Walled Cylinder With Internal

Axial Crack

M. A. Malik, I. Salam, and W. Muhammad

ICONE17-75500 543

Development of Ultrasonic Shot Peening Technique for Reactor Components to ImproveStructural Integrity Against Stress Corrosion Cracking

Shohei Kawano, Ayaka Kawagishi, Nobuichi Suezono, Kenichi Ueno, Ken Okuda,Minoru Obata, Ikuko Kameyama, and Yuusuke Watanabe

xii

ICONE17-75504 549

Creation of Automatic System for Monitoring, Forecasting and Control of Condition of

Lead-Bismuth (Lead) Coolant and Surfaces of Circuits of Nuclear Power Plants

P. N. Martynov, R. Sh. Askhadullin, A. A. Simakov, A. Yu. Chabari, M. E. Chernov,V. S. Lanskikh, and A. Yu. Legkikh

ICONE17-75506 555

Designing Mass Exchangers for Control of Oxygen Content in PB-BI (PB) Coolants in

Various Research Facilities

P. N. Martynov, Ft. Sh. Askhadullin, A. A. Simakov, A. Yu. Chaban', and A. Yu. Legkikh

ICONE17-75531 563

Influence of Impurities on Intergranular Corrosion of Extra High Purity Austenitic

Stainless Steels

Ikuo loka, Jun Suzuki, Takafumi Motoka, Kiyoshi Kiuchi, and Junpei Nakayama

ICONE17-75548 569

Corrosion Analysis of Reinforcing Steels in Mortar for Nuclear Facilities

Toshiyasu Nishimura

ICONE17-75551 575

Development of Alternative Reductant Application in PWR Primary SystemsMasafumi Domae, Hirotaka Kawamura, and Taku Ohira

ICONE17-75599 583

FFS Issues for Steam Generator Tube (Top of Tubesheet) Intergranular Attack/StressCorrosion Cracking

David Durance, Ken Sedman, John Roberts, and Jeff Gorman

ICONE17-75603 589

Thermal Fatigue in CANDU Stations

Metin Yetisir

ICONE17-75606 597

Development of Universal Methodology of Specimen Free Nondestructive Inspection(Control) of Mechanical Properties of NPP Equipment Metal in All Stages of Lifetime

Murat Bakirov, Sergei Chubarov, Igor Frolov, and Joerg Gastrock

ICONE17-75607,

605

Experimental Measurements of Eddy Current Signal From SG Tubes of Fast Breeder

Reactor Covered by a Thin Sodium Layer Using a SG Mock-UpToshihiko Yamaguchi, Ovidiu Mihalache, Masashi Ueda, and Shinya Miyahara

ICOIME17-75618 615

Crack Growth Model for the Probabilistic Assessment of Inspection Strategies for Steam

Generator Tubes

Brian Wolf, Shripad T. Revankar, and Jovica R. Riznic

ICONE17-75619 623

Iron-Copper-Nickel Many-Body Potential Consistent With ThermodynamicsGiovanni Bonny, Roberto C. Pasianot, Nicolas Castin, Dmitry Terentyev, and

Lorenzo Malerba

xiii

ICONE17-75630 627

Electromagnetic Pulse Technology as a Means of Joining Generation IV Cladding Materials

John McGinley

ICONE17-75662 633

The Vanishing Influence of Microstructure on Growing Short Cracks

/. Simonovski and L Cizelj

ICONE17-75685 641

Safe-End Replacement on Pressuizer Upper Nozzles

Xavier Pitoiset, Georges Dellopoulos, Jacques Weverbergh, Jean-Marc Cherasse,

John Flaherty, and Paul Evans

ICONE17-75695.. 649

Degradation of Alloy 800 Under Steam Generator Secondary Side Crevice Conditions

Y. C. Lu, G. Goszczynski, and S. Ramamurthy

ICONE17-75712 659

Degradation of Aged Plants by Corrosion: Radiation-Induced Corrosion Cells Inducing

"Long-Cell" Action

Genn Saji

ICONE17-75770 671

Quantification of the Long-Term Performance of Steels T91 and 316L in Oxygen-ContainingFlowing Lead-Bismuth Eutectic at 550°C

Carsten Schroer and Juergen Konys

ICONE17-75773 681

Corrosion, Corrosion Barrier Development and Mechanical Properties of Steels Foreseen as

Structural Materials in Liquid Lead Alloy Cooled Nuclear SystemsAlfons Weisenburger, Georg Muller, Annette Heinzel, Adrian Jianu, Heinrich Muscher,

and Martin Kieser

ICONE17-75781 687

Study on Nano-Oxide Powder Dispersed Ni-Electroplated Composites for ComponentsMaterials of NPPs

Joung Soo Kim, Myeng Jin Kim, Dong Jin Kim, and Hong Pyo Kim

ICONE17-75813 693

Heavy Liquid Metal Natural Circulation in a One-Dimensional LoopG. Coccoluto, P. Gaggini, V. Labanti, M. Tarantino, W. Ambrosini, N. Forgione, A. Napoli,and F. Oriolo

ICONE17-75821 701

Effects of Laser Peening Treatment on High Cycle Fatigue and Crack PropagationBehaviors in Austenitic Stainless Steel

Yasuo Ochi, Kiyotaka Masaki, Takashi Matsumura, Takaaki Ikarashi, and Yuji Sano

ICONE17-75900 709

Reaction Behavior of Carbon Dioxide With Liquid Sodium Pool

Shinya Miyahara, Hiroyasu Ishikawa, and Yoshio Yoshizawa

xiv

ICONE17-75904 , 717

Inspection of the Steam Generator Heat Transfer Tubes for FBR Monju Restart

Kenji Takahashi, Akira Shiina, Takahiro Onizawa, Shoji Ibaki, Toshihiko Yamaguchi, and

Akihiro Tagawa

ICONE17-75912 727

Weldability of Neutron Irradiated Stainless Steels by YAG Laser and Low-Heat-Input TIG

Welding TechniquesMasatoshi Sato, Kiyomoto Nakata, and Masayoshi Ozawa

ICONE17-75928 735

Analyses of the Failed Impulsion Lines of NPP Dukovany Steam Generator

M. Postler, J. Burda, and P. Tkadlcik

ICONE17-75935 743

Ti3SiC2 as a Candidate Material for Lead Cooled Fast Reactor

M. Utili, M. Agostini, G. Coccoluto, and E. Lorenzini

ICONE17-75936 749

LBE and Pb as Coolants for Generation IV Reactors: The Impurities Problem

A. Gessi, P. Agostin ,M. Agostini, and G. Coccoluto

ICONE17-75965 755

Bayesian Determination of Sample Sizes for Inspections of Feeder HangersFred M. Hoppe and Jovica Riznic

ICONE17-76011 765

Corrosion Behaviour of Steels in Lead-Bismuth Eutectic (LBE) in the LINCE LoopUp to 5000 h

Francisco Javier Martfn-Munoz, Laura Soler-Crespo, and D. Gomez-Briceno

ICONE17-76013 771

Study of the Influence of Surface Finishing on the Corrosion/Oxidation Behaviour of

Stainless Steels in Stagnant Lead Bismuth Eutectic

Francisco Javier Martm-Munoz, L. Soler-Crespo, and D. Gomez-Briceno

NEXT GENERATION SYSTEMS

ICONE17-75007 779

Analysis of FIV Characteristics on a Coaxial Double-Tube Type Hot Gas Duct for the VHTR

Kee-nam Song, Yong-wan Kim, and S.-C. Park

ICONE17-75032 787

Concept of a High Pressure Boiling Water Reactor, HP-BWR

Frigyes Reisch and Hernan Tinoco

ICONE17-75088 793

Development of Observation Techniques in Reactor Vessel of Experimental Fast Reactor JoyoMisao Takamatsu, Kazuyuki Imaizumi, Akinori Nagai, Takashi Sekine, and

Yukimoto Maeda

xv

IC0NE17-75131 803

Modeling of Sodium Two-Phase Flow with the TRACE Code

Aurelia Chenu, Konstantin Mikityuk, and Ftakesh Chawla

ICONE17-75136 813

Design and Analysis of the Axial Bypass Compressor Blade of the Supercritical

C02 Gas Turbine

Takao Ishizuka, Yasushi Muto, Masanori Aritomi, Nobuyoshi Tsuzuki, and

Hiroshige Kikura

1CONE17-75152 823

FAST Code System: Review of Recent Developments and Near-Future Plans

Konstantin Mikityuk

ICONE17-75216 831

Risk Assessment of Hydrogen Production System by Dimethyl Ether Steam Reforming

With the Use of Nuclear Power

Kazuo Koguchi, Shigeo Kasai, Makoto Takahashi, and Toshio Wakabayashi

ICONE17-75251 837

Frequency Domain Linear Stability Analysis of Simplified SupercriticalWater-Cooled Reactor

Pengfei Liu, Yanhua Yang, Aijun Xue, and Xu Cheng

ICONE17-75381 845

A Once-Through Fuel Cycle for Fast Reactors

Kevan D. Weaver, John Gilleland, Charles Ahlfeld, Charles Whitmer, and

George Zimmerman

ICONE17-75388 853

Molten Salt Reactors: A New Beginning for an Old Idea

David LeBlanc

ICONE17-75454 865

Thermal Evaluation for a Ultra High Temperature Reactor With Pebble Type Fuels

Motoo Fumizawa, Yuta Kosuge, and Hidenori Horiuchi

ICONE17-75499 873

Advanced Recycling Core Accommodating Oxide Fuel and Metal Fuel for Closed Fuel CycleKazumi Ikeda, James W. Maddox, Wataru Nakazato, and Shigeru Kunishima

ICONE17-75539 881

Three-Dimensional Core Behaviour Analysis of the Gas-Cooled Fast Reactor (GFR) DuringHypothetical Control Assembly Withdrawal Accidents

Gaetan Girardin, David Blanchet, Konstantin Mikityuk, Gerald Rimpault, and

Rakesh Chawla

ICONE17-75592 893

Operating Experience of Fast Breeder Test Reactor

K. V. Suresh Kumar, V. Ramanathan, and G. Srinivasan

xvi

ICONE17-75636 899

Aspects of Radiation Damage Effects in Iron-Chromium Alloys From the Point of View of

Atomistic Modelling

Dmitry Terentyev, Giovanni Bonny, and Nicolas Castin

ICONE17-75698 909

Advanced Recycling Reactor Design StudyMakoto Mito, Shigeru Kunishima, Kim O. Stein, Kazumi Ikeda, and Horoyuki Sato

ICONE17-75714 919

Ultimate Heat Sink Sizing Requirements on a Month-To-Month Basis

Dong Zheng, Allen T. Vieira, Julie M. Jarvis, and George P. Emsurak

ICONE17-75796 925

Power Conversion System (PCS) Options for Generation IV Nuclear Plant

Jenny Persson and Anthony J. Donaldson

ICONE17-75857 935

Design of a Decay Heat Removal System for EFIT Plant

Barbara Leoncini, Alessandro Alemberti, Luigi Mansani, and Alessandro Pini Prato

ICONE17-75863... 943

Computational Fluid Dynamics Analyses on Very High Temperature Reactor Air Ingress

Chang H. Oh, Eung S. Kim, Richard Schultz, David Petti, and Hyung S. Kang

ICONE17-75884 951

Sustainable Development of China With Nuclear Energy System Beyond Generation-IV

Zhiwei Zhou, Xu Hong, and Yongwei Yang

Author Index 957

xvii