Post on 15-May-2020
transcript
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