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75th International Conference on
ENVIRONMENTAL
DEGRADATION _________
of Materials in Nuclear Power Systems-Water Reactors
Proceedings of the
15th International Conference on
ENVIROMENTAL DEGRADATION
of Materials in Nuclear Power Systems - Water Reactors
sponsored by
TMS (The Minerals, Metals & Materials Society)
NACE International
ANS (American Nuclear Society)
co-sponsored by
The Japan Institute of Metals
Japan Society of Corrosion Engineering
held
August 7-11,2011 at the
Cheyenne Mountain Resort, Colorado Springs, Colorado
Editedby
Jeremy T. Busby,
Gabriel lIevbare, and Peter L. Andresen
Editors Jeremy T. Busby Gabriel Ilevbare Peter L. Andresen ISBN 978-3-319-48569-0 ISBN 978-3-319-48760-1 (eBook) DOI 10.1007/978-3-319-48760-1 Chemistry and Materials Science: Professional Copyright © 2016 by The Minerals, Metals, & Materials Society Published by Springer International Publishers, Switzerland, 2016 Reprint of the original edition published by lohn Wiley & Sons, Inc., 2011, 978-1-11813-241-8 This work is subject to copyright. All rights are reserved by the Publisher, whether the whole or part of the material is concerned, specifically the rights of translation, reprinting, reuse of illustrations, recitation, broadcasting, reproduction on microfilms or in any other physical way, and transmission or information storage and retrieval, electronic adaptation, computer software, or by similar or dissimilar methodology now known or hereafter developed. The use of general descriptive names, registered names, trademarks, service marks, etc. in this publication does not imply, even in the absence of a specific statement, that such names are exempt from the relevant protective laws and regulations and therefore free for general use. The publisher, the authors and the editors are safe to assume that the advice and information in this book are believed to be true and accurate at the date of publication. Neither the publisher nor the authors or the editors give a warranty, express or implied, with respect to the material contained herein or for any errors or omissions that may have been made. Printed on acid-free paper This Springer imprint is published by Springer Nature The registered company is Springer International Publishing AG The registered company address is: Gewerbestrasse 11, 6330 Charn, Switzerland
TABLE OF CONTENTS
15th International Conference on Environmental Degradation of
Materials in Nuclear Power Systems-Water Reactors
Preface ........................................................................................................................................................................ xxi
Conference Organizing Committee/Program Committee .........................................................................................xxiii
Session Chairs and Technical Reviewers .................................................................................................................. xxv
Student Volunteers .................................................................................................................................................. xxvii
Financial Sponsors .................................................................................................................................................... xxix
15th International Conference on Environmental Degradation of Materials in
Nuclear Power Systems-Water Reactors
Opening Session
Overview of NRC Proactive Management of Materials Degradation (PMMD) Program ............................................. 1
C. Carpenter, A. Hull, and G. Oberson
Questions & Answers .................................................................................................................................................. 11
Conditions for Long Term Operation of Nuclear Power Plants in Sweden ................................................................. 13
P. Ekström, K. Gott, and B. Brickstad
Alloy 690 and Its Weld Metals I
Current NRC Perspectives Concerning Primary Water Stress Corrosion Cracking .................................................... 25
D. Alley, and D. Dunn
Questions & Answers .................................................................................................................................................. 39
Evaluation of the Susceptibility to SCC Initiation of Alloy 690 in Simulated PWR Primary Water .......................... 41
T. Couvant, and K. Tsutsumi
Questions & Answers .................................................................................................................................................. 53
Role of Cavity Formation on Crack Growth of Cold-Worked Carbon Steel, TT 690 and MA 600 in High
Temperature Water ...................................................................................................................................................... 55
K. Arioka, T. Miyamoto, T. Yamada, and T. Terachi
Crack Growth Testing on Cold Worked Alloy 690 in Primary Water Environment ................................................... 71
D. Tice, S. Medway, N. Platts, and J. Stairmand
Questions & Answers .................................................................................................................................................. 89
One-Dimensional Cold Rolling Effects on Stress Corrosion Crack Growth in Alloy 690 Tubing
and Plate Materials ...................................................................................................................................................... 91
M. Toloczko, S. Bruemmer, and M. Olszta
Questions & Answers ................................................................................................................................................ 107
v
Alloy 690 and Its Weld Metals II
Cyclic and SCC Behavior of Alloy 690 HAZ in a PWR Environment ..................................................................... 109
B. Alexandreanu, Y. Chen, K. Natesan, and W. Shack
Questions & Answers ................................................................................................................................................ 127
Stress Corrosion Crack Growth Rate Testing of Novel Composite Arrest Specimens.............................................. 131
D. Morton, J. Mullen, E. Plesko, J. Sutliff, and N. Lewis
Questions & Answers ................................................................................................................................................ 147
Environmentally Assisted Crack Growth in Cold Worked Alloy 690TT in Primary Water at Low and High
Temperatures ............................................................................................................................................................. 149
Q. Peng, T. Shoji, J. Hou, Y. Takeda, and T. Yonezawa
Questions & Answers ................................................................................................................................................ 159
SCC of Alloy 690 and Its Weld Metals ..................................................................................................................... 161
P. Andresen, M. Morra, and K. Ahluwalia
Questions & Answers ................................................................................................................................................ 177
SCC Behavior of Alloy 152 Weld in PWR Environment .......................................................................................... 179
B. Alexandreanu, Y. Chen, K. Natesan, and W. Shack
Alloy 690 and Its Weld Metals III
Effect of Hot Cracks on EAC Crack Initiation and Growth in Nickel-Base Alloy Weld Metals .............................. 197
H. Hanninen, A. Toivonen, A. Brederholm, T. Saukkonen, W. Karlsen, U. Ehrnsten, and P. Aaltonen
Questions & Answers ................................................................................................................................................ 223
Stress Corrosion Crack Growth of Alloy 52M in Simulated PWR Primary Water ................................................... 225
M. Toloczko, S. Bruemmer, and M. Olszta
Cyclic and SCC Behavior of Alloy 52M/182 Weld Overlay in a PWR Environment .............................................. 245
B. Alexandreanu, Y. Chen, Y. Yang, K. Natesan, and W. Shack
SCC of High Cr Alloys in BWR Environments ........................................................................................................ 267
P. Andresen
Questions & Answers ................................................................................................................................................ 299
High-Resolution Characterizations of Grain Boundary Damage and Stress Corrosion Crack Tips in Cold-Rolled
Alloy 690 ................................................................................................................................................................... 301
S. Bruemmer, M. Olszta, M. Toloczko, and L. Thomas
Alloy 690 and Its Weld Metals IV
Research and Evaluation of Low Temperature Crack Propagation of Ni Base Alloys in Actual Plants ................... 315
K. Sakima, H. Suzuki, and H. Fujiwara
Questions & Answers ................................................................................................................................................ 327
vi
Penetrative Internal Oxidation from Alloy 690 Surfaces and Stress Corrosion Crack Walls during Exposure to PWR
Primary Water ........................................................................................................................................................... 331
M. Olszta, S. Bruemmer, D. Schreiber, and L. Thomas
Predicting Chromium Depletion of Nickel-Base Alloys ........................................................................................... 343
Y. Yin, F. Zhu, R. Faulkner, E. Miller, P. Moreton, I. Armson, and B. Borradaile
Questions & Answers ................................................................................................................................................ 355
BWR Initiation and Oxide Film Characterization I
In-situ and Ex-situ Oxide Characterization by Synchrotron X-ray (SPring-8) in Non-Sensitized 316 Stainless Steel
and High Temperature Water Combination ............................................................................................................... 357
T. Yonezawa, M. Watanabe, T. Shobu, and T. Shoji
Questions & Answers ................................................................................................................................................ 369
High Resolution Electron Microscopy Study on Oxide Films Formed on Nickel-Base Alloys X-750, 182 and 82 in
Simulated High Flow Velocity BWR Water Conditions ........................................................................................... 371
J. Chen, F. Lindberg, L. Belova, B. Forssgren, K. Gott, J. Lejon, and A. Jasiulevicius
Questions & Answers ................................................................................................................................................ 385
Destructive Examinations on Divider Plates from Decommissioned Steam Generators Affected by Superficial Stress
Corrosion Cracks ....................................................................................................................................................... 389
E. West, D. Morton, and N. Lewis
Questions & Answers ................................................................................................................................................ 405
Non-linear Dynamics of the Morphology at the Oxide / Metal Interface of Austenitic Steels in Simulated Light
Water Reactor Environments and Its Implications for SCC Initiation ...................................................................... 409
Y. Takeda, T. Sato, D. Yamauchi, T. Shoji, and A. Ohji
Questions & Answers ................................................................................................................................................ 421
BWR Initiation and Oxide Film Characterization II
The Effect of Cold Work on Microstructure and SCC Susceptibility in Simulated BWR Environment for Non-
Sensitized Austenitic Stainless Steels ........................................................................................................................ 425
Y. Sakakibara, and G. Nakayama
Behavior of Stress Corrosion Cracking for Type 316L Stainless Steel with Controlled Distribution of Surface Work
Hardened Layer in Simulated Boiling Water Reactors Environment ........................................................................ 439
Y. Miura, Y. Miyahara, M. Sato, K. Kako, and J. Tani
Questions & Answers ................................................................................................................................................ 451
Influence of Bulk and Surface Cold Work on Crack Initiation and Crack Growth of Austenitic Stainless Steels under
Simulated BWR Environment ................................................................................................................................... 453
B. Devrient, R. Kilian, K. Küster, and M. Widera
Questions & Answers ................................................................................................................................................ 469
vii
BWR Stainless Steels CGR I
Effect of Nitrogen Addition in 304 L Stainless Steel on the IGSCC Crack Growth Rate in Simulated BWR
Environment .............................................................................................................................................................. 471
S. Roychowdhury, V. Kain, and R. Prasad
Questions & Answers ................................................................................................................................................ 487
Characterization of Type 304L Stainless Steel: Comparison of ASTM A262 Practice A and Analytical Electron
Microscopy Techniques ............................................................................................................................................. 491
B. Miller, and M. Burke
Questions & Answers ................................................................................................................................................ 501
BWR Stainless Steels CGR II
The Effect of Grain Size on IGSCC in SS 316L in Simulated BWR Environment ................................................... 505
J. Stjärnsäter, B. Bengtsson, B. Forssgren, and H. Johansson
Questions & Answers ................................................................................................................................................ 519
An Investigation into Stress Corrosion Cracking of Dissimilar Metal Welds with 304L Stainless Steel and Alloy 82
in High Temperature Pure Water ............................................................................................................................... 521
T. Yeh, G. Huang, M. Wang, and C. Tsai
Questions & Answers ................................................................................................................................................ 531
Deformation Mode and Microstructure on Stress Corrosion Cracking Path and Kinetics in High Temperature Water
Environments ............................................................................................................................................................. 533
Z. Lu, T. Shoji, S. Yamazaki, F. Meng, T. Dan, Y. Takeda, and K. Negishi
Questions & Answers ................................................................................................................................................ 545
Corrosion Fatigue - BWR, PWR
Effect of Static Load Hold Periods on the Corrosion Fatigue Behavior of Austenitic Stainless Steels in Simulated
BWR Environments ................................................................................................................................................... 547
H. Seifert, S. Ritter, and H. Leber
Effects of Material Composition on Corrosion Fatigue Crack Growth of Austenitic Stainless Steels in High
Temperature Water .................................................................................................................................................... 561
N. Platts, D. Tice, K. Mottershead, L. McIntyre, and F. Scenini
Questions & Answers ................................................................................................................................................ 581
Fatigue Limit and Hysteresis Behavior of Type 304l SS in Air and PWR Water, at 150°C and 300°C ................... 583
H. Solomon, C. Amzallag, R. DeLair, and A. Vallee
NRC Research Activities on Environmentally-Assisted Fatigue............................................................................... 605
G. Stevens, and R. Tregoning
Questions & Answers ................................................................................................................................................ 617
viiiFuel and Fuel Related Materials I
PWR Fuel Deposit Analysis at a B&W Plant with a 24-Month Fuel Cycle .............................................................. 621
M. Pop, L. Lamanna, R. Harne, and J. Riddle
Questions & Answers ................................................................................................................................................ 627
Effect of DH Concentration on Crud Deposition on Heated Zircaloy-4 in Simulated PWR Primary Water ............ 633
H. Kawamura
Questions & Answers ................................................................................................................................................ 645
Use of AREVA BWR CRUD Model To Study High Zinc Operation at a US Plant ................................................. 649
M. Pop, L. Lamanna, M. Bell, J. Riddle, and A. Hoornik
Electrochemical Study of Pre- and Post-Transition Corrosion of Zr Alloys in PWR Coolant .................................. 655
J. Macak, R. Novotny, P. Sajdl, V. Renciukova, and V. Vrtílková
AREVA Fuel Condition Index for a Pressurized Water Reactor ............................................................................... 665
M. Pop, M. Bell, and B. Lockamon
Fuel and Fuel Related Materials II
Structure and Thermodynamical Properties of Zirconium Hydrides from First-Principle ........................................ 671
J. Blomqvist, J. Olofsson, A. Alvarez, and C. Bjerken
Questions & Answers ................................................................................................................................................ 681
Hydride Behavior in Zircaloy-4 during Thermomechanical Cycling ........................................................................ 683
K. Colas, A. Motta, M. Daymond, J. Almer, and Z. Cai
Fuel and Fuel Related Materials III PWR-BWR
Development of a Method for Studying the Influence of Stress State on the Iodine-Induced Stress Corrosion
Cracking of Zirconium Alloys ................................................................................................................................... 689
N. Mozzani, E. Andrieu, Q. Auzoux, C. Blanc, and D. Leboulch
Wear of Zircaloy-4 Grid Straps Due to Fretting and Periodic Impact with RV Internals Baffle Plates .................... 703
S. Davidsaver, S. Fyfitch, B. Friend, and J. Hyres
Questions & Answers ................................................................................................................................................ 717
Alloy 718 and X-750
Microstructure and SCC of Alloy X-750 ................................................................................................................... 719
P. Andresen, M. Morra, B. Carter, and J. Flores-Preciado
Questions & Answers ................................................................................................................................................ 741
Stress Corrosion Cracking and Crack Tip Characterization of Alloy X-750 in Boiling Water
Reactor Environments ............................................................................................................................................... 745
J. Gibbs, R. Ballinger, J. Jackson, D. Isheim, and H. Hanninen
Questions & Answers ................................................................................................................................................ 761
ixSCC Properties of Modified Alloy 718 in BWR Plant .............................................................................................. 763
Y. Katayama, M. Tsubota, Y. Saito, N. Tanaka, and S. Tanaka
Questions & Answers ................................................................................................................................................ 777
Influence of Chloride Ions as Contaminants on the Corrosion Behavior of Alloy 718 in Pool Water of Nuclear
Power Plants .............................................................................................................................................................. 781
J. Hugues, C. Blanc, E. Andrieu, and J. Cloué
BWR Low Alloy Steel
Stress Corrosion Cracking Behavior near the Fusion Boundary of Dissimilar Weld Joint with Alloy 182 - A533B
Low Alloy Steel ......................................................................................................................................................... 791
H. Abe, M. Ishizawa, and Y. Watanabe
Questions & Answers ................................................................................................................................................ 803
Effect of Chloride on Environmentally Assisted Cracking of Low Alloy Steels in Oxygenated Hightemperature
Water - General Corrosion......................................................................................................................................... 805
M. Herbst, A. Roth, E. Nowak, and U. Ilg
Questions & Answers ................................................................................................................................................ 821
BWR Stainless Steels CGR III
The Effect of Temperature on the Crack Growth Rate in Simulated BWR Environment ......................................... 827
J. Stjärnsäter, A. Jenssen, C. Jansson, K. Gott, B. Bengtsson, B. Forssgren, and H. Johansson
Questions & Answers ................................................................................................................................................ 839
Effects of Temperature and Corrosion Potential on SCC .......................................................................................... 849
P. Andresen, and R. Seeman
Questions & Answers ................................................................................................................................................ 879
Effect of Thermal Aging on SCC, Material Properties and Fracture Toughness of Stainless Steel Weld Metals ..... 883
T. Lucas, R. Ballinger, H. Hanninen, and T. Saukkonen
Questions & Answers ................................................................................................................................................ 901
Flow Assisted Corrosion
Flow Accelerated Corrosion of Carbon Steel in the Feedwater System of Pwr Plants - Behaviour of Welds
and Weld Assemblies ................................................................................................................................................ 907
C. Mansour, E. Pavageau, A. Faucher, F. Inada, K. Yoneda, C. Miller, and J. Bretelle
Questions & Answers ................................................................................................................................................ 921
Modelling Material Effects in Flow-Accelerated Corrosion ..................................................................................... 925
P. Phromwong, D. Lister, and S. Uchida
xPWR Oxide Films and Characterization
3D Atom-Probe Characterization of Stress and Cold-Work in Stress Corrosion Cracking of 304 Stainless Steel ... 939
K. Kruska, S. Lozano-Perez, T. Terachi, T. Yamada, D. Saxey, and G. Smith
Questions & Answers ................................................................................................................................................ 947
Effect of Dissolved Hydrogen, Surface Conditions and Composition on the Electronic Properties of the Oxide
Films Formed on Nickel-Base Alloys in PWR Primary Water ................................................................................. 953
A. Loucif, J. Petit, Y. Wouters, and P. Combrade
Questions & Answers ................................................................................................................................................ 965
Influence of Primary Water Chemistry on Oxides Formed on Alloy 600 and Alloy690........................................... 967
T. Devine
Characterizing Environmental Degradation in PWRs by 3D FIB Sequential Sectioning ......................................... 993
S. Lozano-Perez, N. Ni, K. Kruska, C. Grovenor, T. Terachi, and T. Yamada
Questions & Answers .............................................................................................................................................. 1005
PWR Secondary Side/Balance of Plant I
On the Microstructure of Alloy 600 SCC Cracks Observed by TEM on PWR SG Pulled Tubes and on
Laboratory Specimens ............................................................................................................................................. 1007
L. Legras, F. Delabrouille, S. Miloudi, E. Fargeas, O. De Bouvier, and Y. Thebault
Balance of Plant Corrosion Issues in Aging Nuclear Power Plants ......................................................................... 1023
G. Licina, and D. Dedhia
Questions & Answers .............................................................................................................................................. 1035
Containment Liner Corrosion .................................................................................................................................. 1037
D. Dunn, A. Pulvirenti, and P. Klein
Questions & Answers .............................................................................................................................................. 1049
PWR Secondary Side/Balance of Plant II
Electrochemical Studies of Steam Generator Tube Degradation in the Presence of Thiosulphate .......................... 1051
L. Chi, and Y. Lu
Questions & Answers .............................................................................................................................................. 1063
X-Ray Photoelectron Study of the Oxides Formed on Nickel Metal and Nickel-Chromium 20% Alloy Surfaces
under Reducing and Oxidizing Potentials in Basic, Neutral and Acidic Solutions ................................................. 1065
S. McIntyre, B. Payne, and P. Keech
Questions & Answers .............................................................................................................................................. 1083
xiSCC of Alloy 82, 182 Welds I
Interaction of Microstructure, Composition, and Cold Work on the Stress Corrosion Cracking of Alloy 82
Weld Metal .............................................................................................................................................................. 1087
D. Paraventi, and W. Moshier
Questions & Answers .............................................................................................................................................. 1103
Stress Corrosion Cracking Behavior of Dissimilar Metal Weldments in High Temperature
Water Environment.................................................................................................................................................. 1105
J. Huang, S. Jeng, J. Huang, R. Kuo, and M. Chiang
Questions & Answers .............................................................................................................................................. 1123
SCC Crack Growth Rate of Alloy 82 in PWR Primary Water Conditions - Effect of a Thermal Treatment .......... 1127
M. Le Calvar, C. Guerre, C. Duhamel, M. Sennour, and J. Crepin
SCC of Alloy 82, 182 Welds II
Initiation of PWSCC of Weld Alloys 182 ............................................................................................................... 1141
T. Couvant, and F. Vaillant
Questions & Answers .............................................................................................................................................. 1153
NRC/EPRI Welding Residual Stress Validation Program (Phase III) ..................................................................... 1155
M. Kerr, L. Fredette, H. Rathbun, and J. Broussard
Questions & Answers .............................................................................................................................................. 1167
IASCC Stainless Steels CGR I
Crack Growth Behavior of Irradiated Type 316 SS in Low Dissolved Oxygen Environment ................................ 1169
Y. Chen, B. Alexandreanu, Y. Yang, W. Shack, K. Natesan, E. Gruber, and A. Rao
Questions & Answers .............................................................................................................................................. 1183
Stress Corrosion Crack Initiation Susceptibility of Irradiated Austenitic Stainless Steels ...................................... 1187
K. Stephenson, Y. Ashida, J. Busby, and G. Was
Questions & Answers .............................................................................................................................................. 1201
Stress Corrosion Cracking Behavior of Type 304 Stainless Steel Irradiated under Different Neutron Dose
Rates at JMTR ......................................................................................................................................................... 1203
Y. Kaji, K. Kondo, Y. Aoyagi, Y. Kato, T. Taguchi, F. Takada, J. Nakano, H. Ugachi, T. Tsukada,
K. Takakura, and H. Sakamoto
Questions & Answers .............................................................................................................................................. 1217
In-Pile Tests for IASCC Growth Behavior of Irradiated 316L Stainless Steel under Simulated BWR Condition
in JMTR ................................................................................................................................................................... 1219
Y. Chimi, S. Kasahara, H. Ise, Y. Kawaguchi, J. Nakano, and Y. Nishiyama
Crack Growth Rates of Irradiated Commercial Stainless Steels in BWR and PWR Environments ........................ 1229
A. Jenssen, J. Stjärnsäter, and R. Pathania
xiiIASCC Stainless Steels CGR II
The Key Factors Affecting Crack Growth Behavior of Neutron-Irradiated Austenitic Alloys ............................... 1241
Y. Ashida, A. Flick, P. Andresen, and G. Was
Questions & Answers .............................................................................................................................................. 1255
Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steel WWER Reactor Core Internals ...... 1257
A. Hojna, M. Ernestova, O. Hietanen, R. Korhonen, L. Hulinova, and F. Oszvald
Questions & Answers .............................................................................................................................................. 1273
Slow Strain Rate Tensile Tests of Irradiated Austenitic Stainless Steels in Simulated PWR Environment ............ 1277
Y. Chen, B. Alexandreanu, W. Soppet, W. Shack, K. Natesan, and A. Rao
Questions & Answers .............................................................................................................................................. 1291
Irradiation Assisted Stress Corrosion Cracking of Stainless Steels in a PWR Environment
(A Combined Approach) ......................................................................................................................................... 1293
M. Le Millier, O. Calonne, J. Crépin, C. Duhamel, F. Gaslain, E. Héripré, O. Toader,
and Y. Vidalenc
A Preliminary Hybrid Model of Irradiation-Assisted Stress Corrosion Cracking of 300 Series Stainless Steels in
PWR Primary Environments ................................................................................................................................... 1309
E. Eason, G. Ilevbare, and R. Pathania
Questions & Answers .............................................................................................................................................. 1325
Irradiation Effects - General I
Oxidation of a Proton-irradiated 316 Stainless Steel in Simulated BWR NWC Environment ................................ 1329
Z. Jiao, and G. Was
Irradiation Creep and Irradiation Stress Relaxation of 316 and 304l Stainless Steels in Thermal and Fast
Neutron Spectrum Reactors ..................................................................................................................................... 1339
J. Foster, and T. Karlsen
Questions & Answers .............................................................................................................................................. 1351
Recent Insights on the Parametric Dependence of Irradiation Creep of Austenitic Stainless Steels ....................... 1355
F. Garner, E. Gilbert, and V. Neustroev
Questions & Answers .............................................................................................................................................. 1369
Cluster Dynamics Prediction of the Microstructure Evolution of 300-series Austenitic Stainless Steel under
Irradiation: Influence of Helium .............................................................................................................................. 1371
M. Zouari, L. Fournier, A. Barbu, and Y. Brechet
Irradiation Effects on Deformation
Role of Slip Behavior in the Irradiation Assisted Stress Corrosion Cracking in Austenitic Steels ......................... 1383
M. McMurtrey, and G. Was
Questions & Answers .............................................................................................................................................. 1395
xiiiEffect of Environment and Prestrain on IASCC of Austenitic Stainless Steels ....................................................... 1397
W. Lai, Z. Jiao, and G. Was
Questions & Answers .............................................................................................................................................. 1413
Influence of Localized Plasticity on IASCC Sensitivity of Austenitic Stainless Steels under PWR
Primary Water ......................................................................................................................................................... 1417
S. Cisse, E. Andrieu, B. Tanguy, L. Laffont, M. Lafont, and C. Guerre
Deformation Microstructures of 30 dpa AISI 304 Stainless Steel after Monotonic Tensile and Constant Load
Autoclave Testing .................................................................................................................................................... 1429
W. Karlsen, J. Pakarinen, A. Toivonen, and U. Ehrnstén
Questions & Answers .............................................................................................................................................. 1445
PWR Alloy 600 Oxidation and Mechanisms I
Degradation of Grain Boundary Strength by Oxidation in Alloy 600 ..................................................................... 1447
K. Fujii, T. Miura, H. Nishioka, and K. Fukuya
Questions & Answers .............................................................................................................................................. 1459
Evaluation of the Oxygen Diffusion Coefficient in Nickel-Base Alloys ................................................................. 1463
H. Nam, J. Yoon, J. Kim, I. Hwang, and K. Lee
Stress Corrosion Cracking of Alloy 600 in PWR Primary Water: Influence of Chromium, Oxygen
and Hydrogen Diffusion .......................................................................................................................................... 1477
C. Guerre, P. Laghoutaris, J. Chêne, L. Marchetti, R. Molins, C. Duhamel, and M. Sennour
Questions & Answers .............................................................................................................................................. 1489
Grain Boundary Oxidation and Embrittlement Prior to Crack Initiation in Alloy 600 in PWR Primary Water ...... 1491
L. Fournier, O. Calonne, P. Combrade, P. Scott, P. Chou, and R. Pathania
PWR Alloy 600 Oxidation and Mechanisms II
Electron Microscopy Characterizations and Atom Probe Tomography of Intergranular Attack in Alloy 600
Exposed to PWR Primary Water ............................................................................................................................. 1503
M. Olszta, D. Schreiber, L. Thomas, and S. Bruemmer
Questions & Answers .............................................................................................................................................. 1517
Grain Boundary Oxidation and Stress Corrosion Cracking in Nickel-base Alloys Strained in
Supercritical Water .................................................................................................................................................. 1519
T. Moss, M. Olszta, W. Grant, and G. Was
Questions & Answers .............................................................................................................................................. 1531
Quantitative Micro-nano (QMN) Approach to SCC Mechanism and Prediction-Starting a Third Meeting ........... 1535
R. Staehle
Questions & Answers .............................................................................................................................................. 1627
xivPWR Alloy 600 SCC I
Strain Path Effect on IGSCC Initiation and Oxidation of Alloy 182 Exposed to PWR Primary Water .................. 1631
T. Couvant, L. Legras, T. Ghys, P. Gambier, N. Huin, and G. Ilevbare
Questions & Answers .............................................................................................................................................. 1645
Experimental Study of Short Crack Coalescence in Nickel-Base Alloys In PWR Primary Water ......................... 1647
O. Calonne, L. Fournier, P. Combrade, P. Scott, and P. Chou
Questions & Answers .............................................................................................................................................. 1665
Mechanistic Study on PWSCC of Ni-Based Alloys Using Hump-SSRT Tests under Dry Hydrogen Gas
Environment, Simulated Primary Water and Rapid Straining Electrode Test in Simulated Primary Water ........... 1667
N. Totsuka, T. Terachi, and K. Takakura
Questions & Answers .............................................................................................................................................. 1683
Crystallographical Characterization of Initiation of Intergranular Stress Corrosion Cracking of Alloy 600
in PWR Environment ............................................................................................................................................... 1685
S. Fujimoto, M. Mochizuki, Y. Morita, Y. Mikami, H. Tsuchiya, and K. Nishimoto
Questions & Answers .............................................................................................................................................. 1697
Environmental Effects on PWSCC Initiation and Propagation in Alloy 600 .......................................................... 1699
A. Molander, K. Norring, P. Andersson, and P. Efsing
Questions & Answers .............................................................................................................................................. 1713
PWR Alloy 600 SCC II
Probabilistic Environmentally-Assisted Cracking Modeling for Primary Water Stress Corrosion Cracking of Alloy
600 ........................................................................................................................................................................... 1715
T. Lee, J. Yoon, H. Nam, and I. Hwang
Questions & Answers .............................................................................................................................................. 1729
The Role of Lattice Curvature on the SCC Susceptibility of Alloy 600 .................................................................. 1731
F. Leonard, F. Di Gioacchino, R. Cottis, F. Vaillant, J. Quinta da Fonseca, F. Carrette,
and G. Ilevbare
Questions & Answers .............................................................................................................................................. 1745
PWSCC Susceptibility in Heat-Affected Zones of Alloy 600 ................................................................................. 1747
T. Couvant, T. Brossier, and C. Cossange
Questions & Answers .............................................................................................................................................. 1757
Quantitative Residual Strain Analyses on Strain Hardened Nickel Based Alloy .................................................... 1759
T. Yonezawa, T. Maeguchi, T. Goto, and H. Juan
The Study of Stress Corrosion Cracking on Alloy 600 C-Ring Samples by Polychromatic X-Ray
Microdiffraction....................................................................................................................................................... 1773
S. McIntyre, J. Chao, M. Suominen Fuller, R. Newman, A. Carcea, M. Kunz, and N. Tamura
Questions & Answers .............................................................................................................................................. 1783
xvPWR Degradation Management
Proposed Coordinated U.S. PWR Reactor Vessel Surveillance Program: An Updated Summary Including
Program Optimization ............................................................................................................................................. 1787
R. Hosler, S. Davidsaver, T. Hardin, D. Weakland, and G. Troyer
Developing PWR Aging-Management Strategies for Reactor Vessel Internals ...................................................... 1801
S. Davidsaver, S. Fyfitch, and H. Xu
Development of the Extremely Low Probability of Rupture (xLPR) Code ............................................................. 1811
D. Rudland, and C. Harrington
Questions & Answers .............................................................................................................................................. 1827
Databases of Operationally Induced Damage .......................................................................................................... 1829
K. Gott
Questions & Answers .............................................................................................................................................. 1843
PWR Water Chemistry and Mitigation
Introduction to a New Real-Time Water Chemistry Measurement System ............................................................. 1847
J. Yeon, K. Song, and M. Yun
Questions & Answers .............................................................................................................................................. 1855
Comparison of DBU, NH3, DMA, ETA, and Morpholine Interactions with Ferrous Chloride Solution
and Carbon Steel Surfaces ....................................................................................................................................... 1859
S. Nasrazadani, A. Reid, J. Stevens, R. Theimer, and B. Fellers
Questions & Answers .............................................................................................................................................. 1877
Role of Dissolved Hydrogen in Water in Corrosion of Alloy 600 in High Temperature Water ............................. 1879
Q. Peng, T. Shoji, J. Hou, K. Sakaguchi, and Y. Takeda
Questions & Answers .............................................................................................................................................. 1889
Quantifying the Benefit of Chemical Mitigation of PWSCC via Zinc Addition or Hydrogen Optimization .......... 1893
C. Marks, M. Dumouchel, R. Reid, and G. White
Questions & Answers .............................................................................................................................................. 1907
Super Critical Water
Computational Thermodynamics for Interpreting Oxidation of Structural Materials in Supercritical Water ......... 1909
L. Tan, Y. Yang, T. Allen, and J. Busby
Questions & Answers .............................................................................................................................................. 1919
Stress Corrosion Cracking of Austenitic Alloys in Supercritical Water .................................................................. 1923
G. Cao, V. Firouzdor, and T. Allen
Questions & Answers .............................................................................................................................................. 1937
xviComparison of the Oxidation Behavior of the 14CrODS Alloy in Steam and Supercritical Water ........................ 1939
J. Bischoff, and A. Motta
Questions & Answers .............................................................................................................................................. 1949
Grain Boundary Engineering and Air Oxidation Behavior of Alloy 690 ................................................................ 1951
P. Xu, L. Zhao, K. Sridharan, and T. Allen
Questions & Answers .............................................................................................................................................. 1965
BWR Water Chemistry and Mitigation I
Developments in SCC Mitigation by Electrocatalysis ............................................................................................. 1967
P. Andresen, and Y. Kim
Questions & Answers .............................................................................................................................................. 1989
Use of Noble Metal Nanoparticle for SCC Mitigation in BWRs............................................................................. 1993
Y. Kim, P. Andresen, and S. Hettiarachchi
Questions & Answers .............................................................................................................................................. 2003
The Influence of Minor Additions of Platinum Group Metals on Stress Corrosion Cracking in Austenitic
Stainless Steels ........................................................................................................................................................ 2005
K. Govender, F. Scenini, S. Lyon, O. Necib, and A. Sherry
Questions & Answers .............................................................................................................................................. 2021
The Effect of On-Line Noble Metal Addition on the Shut Down Dose Rates of Boiling Water Reactors .............. 2023
R. Cowan, J. Varela, and S. Garcia
Questions & Answers .............................................................................................................................................. 2037
Effects of Hydrogen on SCC Growth Rate of Ni Alloys in BWR Water ................................................................ 2039
P. Andresen, and P. Chou
Technical Basis for Water Chemistry Control of IGSCC in Boiling Water Reactors ............................................. 2061
B. Gordon, and S. Garcia
Questions & Answers .............................................................................................................................................. 2077
BWR Water Chemistry and Mitigation II
Water Chemistry in the Primary Coolant Circuit of a Boiling Water Reactor during Startup Operations .............. 2079
T. Yeh, and M. Wang
Simulation of Water Radiolysis by Sonochemistry: Effects on the Electrochemical Behavior of
a Stainless Steel ....................................................................................................................................................... 2091
O. Lavigne, Y. Takeda, and T. Shoji
Questions & Answers .............................................................................................................................................. 2101
Protective Insulated Coating for SCC Mitigation in BWRs .................................................................................... 2103
Y. Kim, and P. Andresen
Questions & Answers .............................................................................................................................................. 2117
xviiInfluence of Treating Temperature on the Deposition of TiO2 on Type 304 Stainless Steels for Corrosion
Mitigation in High Temperature Pure Water ........................................................................................................... 2121
T. Yeh, Y. Huang, and C. Tsai
Questions & Answers .............................................................................................................................................. 2135
Irradiation Effects - General II
Irradiation Microstructure of Austenitic Steels and Cast Steels Irradiated in the BOR-60 Reactor at 320°C ......... 2137
Y. Yang, Y. Chen, Y. Huang, T. Allen, and A. Rao
Questions & Answers .............................................................................................................................................. 2149
PWR Field Experience I
Laboratory Stress Corrosion Cracking Propagation in a Superficial Cold-Worked Layer in SG Divider Plates
in Alloy 600 ............................................................................................................................................................. 2151
F. Vaillant, T. Couvant, S. Miloudi, Y. Thebault, D. Deforge, E. Lemaire, C. Leseigneur,
and P. Le-Delliou
Destructive Examinations on Divider Plates from Decommissionned Steam Generators Affectined by
Superficial Stress Corrosion Cracks ........................................................................................................................ 2171
S. Miloudi, E. Firmin, D. Deforge, F. Vaillant, and E. Lemaire
Questions & Answers .............................................................................................................................................. 2185
Investigations on Core Basket Bolts from a VVER 440 Power Plant ..................................................................... 2189
U. Ehrnsten, P. Kytömäki, and O. Hietanen
Questions & Answers .............................................................................................................................................. 2201
Laboratory Analysis of a Reactor Coolant Pump Seal ............................................................................................ 2207
M. Sullivan, and J. Hyres
PWSCC of Thermocoax Pressurizer Heaters in Austenitic Stainless Steel and Remedial Actions
to Preventing SCC ................................................................................................................................................... 2219
J. Champredonde, Y. Thebault, P. Moulart, T. Couvant, K. Dubourgnoux, Y. Neau, J. Fageon,
D. Lecharpentier, A. Breuil, and V. Derouet
PWR Field Experience II
Residual Stress Measurement and the Effect of Heat Treatment in Cladded Control Rod Drive Specimens ......... 2231
E. Kingston, A. Bowman, J. Katsuyama, M. Udagawa, and K. Onizawa
Questions & Answers .............................................................................................................................................. 2245
Detailed Root Cause Analysis of SG Tube ODSCC Indications within the Tube Sheets of NPP Biblis Unit A .... 2247
R. Kilian, J. Beck, H. Lang, T. Schönherr, and M. Widera
Questions & Answers .............................................................................................................................................. 2261
Laboratory Investigation of a Leaking Type 316 Socket Weld in a Boron Injection Tank Sampling Line ............. 2263
H. Xu, S. Fyfitch, R. Hosler, and J. Hyres
xviiiPressure Tests on SG Pulled Tubes at TSP Level .................................................................................................... 2275
M. Boccanfuso, and C. Mathon
Implications of Steam Generator Fouling on the Degradation of Thermal and Material Performance ................... 2287
C. Turner
Questions & Answers .............................................................................................................................................. 2301
Key Issues Related to Corrosion Protection of Brackish Water and Sea Water Bearing Components in Cooling
Water Systems ......................................................................................................................................................... 2303
E. Nowak, B. Bengtsson, B. Forssgren, B. Hall, and E. Johansson
PWR Initiation and CGR Stainless Steels I
Understanding the Limits of Lattice Orientation Data Analysis in Environmental Degradation Studies ................ 2321
F. Di Gioacchino, J. Quinta da Fonseca, D. Wright, and F. Scenini
Questions & Answers .............................................................................................................................................. 2333
A Microstructural Investigation on the Effect of Cold Work on Environmentally Assisted Cracking of
Austenitic Stainless Steels ....................................................................................................................................... 2335
D. Wright, F. Di Gioacchino, J. Quinta da Fonseca, F. Scenini, S. Nouraei, K. Mottershead,
and D. Tice
Questions & Answers .............................................................................................................................................. 2347
Plastic Strain and Residual Stress Distributions in an AISI 304 Stainless Steel BWR Pipe Weld .......................... 2351
T. Saukkonen, M. Aalto, I. Virkkunen, U. Ehrnsten, and H. Hanninen
Assessment of Lean Grade Duplex Stainless Steels for Nuclear Power Applications............................................. 2369
G. Young, J. Tucker, D. Eno, N. Lewis, E. Plesko, and P. Sander
PWR Initiation and CGR Stainless Steels II
Effects of Thermo-Mechanical Treatments on Deformation Behavior and IGSCC Susceptibility of Stainless
Steels in PWR Primary Water Chemistry ................................................................................................................ 2381
S. Nouraei, D. Tice, K. Mottershead, and D. Wright
Questions & Answers .............................................................................................................................................. 2403
Previously Unpublished Manuscripts from the 14th International Conference
on Environmental Degradation of Materials in Nuclear Power Systems,
23-29th August 2009, Virginia Beach, VA, USA
SCC Initiation Testing of Alloy 600 in High Temperature Water ........................................................................... 2407
R. Etien, E. Richey, D. Morton, and J. Eager
The Effects of Deaerated Water on the Toughness of Nickel-based Alloys ............................................................ 2419
E. Richey, and G. Young
Physical Metallurgy, Weldability, and In-service Performance of Nickel-chromium Filler Metals Used in
Nuclear Power Systems ........................................................................................................................................... 2431
G. Young, R. Etien, M. Hackett, J. Tucker, and T. Capobianco
xixAuthor Index ............................................................................................................................................................ 2443
Subject Index ........................................................................................................................................................... 2447
xxPreface
The production of electricity from light water nuclear reactors occupies a central
role in meeting worldwide energy requirements. The importance of nuclear
power is expected to increase as worldwide demand for energy increases because
of relatively cheap electricity generating cost, and near zero carbon emissions.
If nuclear power is going to continue making a contribution to worldwide energy
demands, power plants must be operated in a safe and cost effective nature.
Central to these safety and reliability goals is effective materials degradation
management. Effective materials management must include both the maintenance
of existing plants and in the choice and use of materials in the new plants.
3DUWLFXODUDWWHQWLRQPXVWEHSDLGWRWKHFXUUHQWO\DJLQJZRUOGZLGHÀHHWRIUHDFWRUV
DQGSRZHUSODQWVDVWKHVHFRQVWLWXWHDVLJQL¿FDQWSRUWLRQRIWKHZRUOG¶VQXFOHDU
power generating assets. As at January 2011, 174 of the 442 reactors currently in
operation worldwide (representing ~39%) are 30 years or older, compared with
only 84 (representing 19%) 20 years or younger. Many of these aging plants
are being considered for extended service to 60 or even 80 years. Materials
degradation issues sensitive to long term operation therefore need to be part of
current proactive asset management plans.
The goals of any good materials degradation management plan must include the
following elements:
Maximization of the Operating Life and Reliability of Water Passive
Long-lived Components to Support Current and Extended Operations
Prediction of Component Degradation Mechanisms and Their Rate of
Occurrence to Estimate Inspection Frequency and the End of Component
Useful Life
Anticipation of Impacts on Plant Operations Related to Implementing
Materials Management Activities
Performance of Proactive Fundamental Research to Understand the
Physical Bases of Degradation Mechanisms and Development of
Physically Based Models, and Where Possible Development of Mitigation
Techniques to Retard or Prevent Degradation
Consistent with its tradition since inception, this 15th Edition of the International
Conference on Materials Degradation in Light Water Reactors focuses on subject
DUHDVFULWLFDOWRWKHVDIHDQGHI¿FLHQWUXQQLQJRIQXFOHDUUHDFWRUV\VWHPVWKURXJK
WKH H[FKDQJH DQG GLVFXVVLRQ RI UHVHDUFK UHVXOWV DV ZHOO DV ¿HOG RSHUDWLQJ DQG
management experience. These exchanges and discussions contribute to all four
elements listed above for effective asset management.
xxiThis Conference featured the presentation of about 150 papers, spread over 40
sessions in about 20 different areas relevant to LWRs including SCC of nickel
alloys and stainless steels, fuel and fuel related materials, corrosion fatigue,
ÀRZDVVLVWHGFRUURVLRQ,$6&&DQGLUUDGLDWLRQHIIHFWVVXSHUFULWLFDOZDWHUDQG
materials degradation management. The conference was attended by over 200
scientists and engineers from 17 countries, representing power plant operators,
NSSS vendors, regulators, national laboratories, research institutes, universities,
DQGRWKHURUJDQL]DWLRQVDI¿OLDWHGZLWKWKHQXFOHDUDQGQXFOHDUVHUYLFHLQGXVWULHV
The organizers recognize the help of a dedicated group of individuals who made
this 15th Edition of the Conference a success and these proceedings possible. The
Program Committee, Session Chairs and Technical Reviewers listed below played
VLJQL¿FDQWUROHVLQRUJDQL]LQJWKHVHVVLRQVFRQGXFWLQJSDSHUUHYLHZVDQGFKHFNV
and facilitated near-perfect technical presentation sessions. These activities
UHTXLUHGDVLJQL¿FDQWFRPPLWPHQWRIWKHLUWLPHDQGWKH\DUHJUHDWO\DSSUHFLDWHG
The Organizers are thankful to their respective employers for making them
available for participating in planning, organizing and serving at the conference.
The assistance of the University of Michigan students who facilitated the
question-and-answer element in each session is acknowledged. Felicia Bellamy-
Roseberry and Nancy Ward, both of Oak Ridge National Laboratory, USA are
acknowledged for their assistance in generating electronic copies of the question
and answer sheets. We thank The Minerals, Metals, and Materials Society (TMS)
for their assistance with conference planning, paper review, and publication of
these proceedings.
Special thanks go to the Conference General Chair, Jeremy Busby of Oak Ridge
National Laboratory, and the Assistant Technical Program Chair Peter Andresen
of GE Global Research Center for their tireless efforts in ensuring the success of
this conference.
Gabriel Ilevbare
Technical Program Chair
xxiiConference Organizing Committee
Conference General Chair: Jeremy Busby, Oak Ridge National Laboratory, USA
Technical Program Chair: Gabriel Ilevbare, Electric Power Research Institute, USA
Assistant Technical Program Chair: Peter Andresen, GE Global Research Center, USA
Program Committee
Todd Allen, University of Wisconsin, USA
Koji Arioka, Institute of Nuclear Safety System, Inc, Japan
Peter Andresen, GE Global Research Center, USA
Steve Bruemmer3DFL¿F1RUWKZHVW1DWLRQDO/DERUDWRU\86$
Jeremy Busby, Oak Ridge National Lab, USA
Gene Carpenter, U.S. Nuclear Regulatory Commission, USA
Pål Efsing, Ringhals AB, Sweden
Ulla Ehrnsten, VTT Technical Research Centre, Finland
6WHYH)\¿WFK, Areva, USA
Barry Gordon, Structural Integrity Associates, Inc, USA
Ron Horn, GE Power and Water, USA
Il Soon Hwang, Seoul National University, Korea
Gabriel Ilevbare, Electric Power Research Institute, USA
Rich Jacko, Westinghouse Electric Corp., USA
Christer Jansson, Vattenfall Power Consultant AB, Sweden
Anders Jenssen, Studsvik AB, Sweden
Renate Kilian, Areva GmbH, Germany
Hong Pyo Kim, Korea Atomic Energy Research Institute, Korea
Peter King, Babcock & Wilcox, Canada
Bill Mills, Bechtel Bettis Inc., USA
Dave Morton, Bechtel KAPL, USA
Larry Nelson, JLN Consulting, USA
Hans-Peter Seifert, Paul Scherrer Institute, Switzerland
Robert Tapping, Atomic Energy of Canada Limited, Chalk River Nuclear Labs, Canada
Francois Vaillant, Electricité de France, France
Gary Was, University of Michigan, USA
TK Yeh, National Tsing Hua University, Taiwan
Toshio Yonezawa, Tohoku University, Japan
xxiiiSession Chairs and Technical Reviewers
Al Ahluwalia, Electric Power Research Institute, USA
Bogdan Alexandreanu, Argonne National Laboratory, USA
Todd Allen, University of Wisconsin, USA
David Alley, U.S. Nuclear Regulatory Commission, USA
Peter Andresen, GE Global Research Center, USA
Koji Arioka, Institute of Nuclear Safety System, Inc, Japan
Ian Armson, Rolls Royce, UK
Jean-Luc Bretelle, Electricité de France, France
Stephen Bruemmer,3DFL¿F1RUWKZHVW1DWLRQDO/DERUDWRU\86$
Jeremy Busby, Oak Ridge National Laboratory, USA
Art Byers, Westinghouse, USA
Gene Carpenter, U.S. Nuclear Regulatory Commission, USA
Bob Carter, Electric Power Research Institute, USA
Yiren Chen, Argonne National Laboratory, USA
Bo Cheng, Electric Power Research Institute, USA
Peter Chou, Electric Power Research Institute, USA
Thierry Couvant, Electricité de France, France
Al Csontos, U.S. Nuclear Regulatory Commission, USA
Damien Daforge, Electricité de France, France
Anne Demma, Electric Power Research Institute, USA
Darell Dunn, U.S. Nuclear Regulatory Commission, USA
Kurt Edsinger, Electric Power Research Institute, USA
Ernest Eason, Modeling & Computing Services, LLC, USA
Pål Efsing, Ringhals AB, Sweden
Ulla Ehrnsten, VTT Technical Research Centre, Finland
Lionel Fournier, Areva NP SAS, France
Katsuhiko Fujii, Institute of Nuclear Safety System, Inc, Japan
Frank Garner, Radiation Effects Consulting LLC, USA
Jeff Gorman, Dominion Engineering, USA
Karen Gott, MatSafe AB, Sweden
Catherine Guerre&RPPLVVDULDWjO¶eQHUJLH$WRPLTXH)UDQFH
Hannu Hanninen, Helsinki University of Technology, Finland
Ron Horn, GE Power and Water, USA
James Hyres, Babcock and Wilcox, USA
Gabriel Ilevbare, Electric Power Research Institute, USA
John Jackson, Idaho National Laboratory, USA
Anders Jenssen, Studsvik AB, Sweden
xxvSession Chairs and Technical Reviewers (continued)
Wade Karlsen, VTT Technical Research Centre, Finland
Matthew Kerr, U.S. Nuclear Regulatory Commission, USA
Renate Kilian, Areva GmbH, Germany
Young Kim, GE Global Research Center, USA
Laurent Legras, Electricité de France, France
Tiangan Lian, Electric Power Research Institute, USA
George Licina, Structural Integrity Inc, USA
Derek Lister, University of New Brunswick, Canada
Carine Mansour, Electricité de France, France
David Morton, Bechtel KAPL, USA
Larry Nelson, JLN Consulting, USA
Roger Newman, University of Toronto, Canada
Samaneh Nouraei, Serco, UK
Matt Olszta3DFL¿F1RUWKZHVW1DWLRQDO/DERUDWRU\86$
Denise Paraventi, Bechtel Bettis, USA
Raj Pathania, Electric Power Research Institute, USA
Qunjia Peng, Institute of Metals Research, China
Richard Reid, Electric Power Research Institute, USA
Raul Rebak, GE Global Research Center, USA
In Hyoung Rhee, Soon Chun Hyang University, Korea
Hans-Peter Seifert, Paul Scherrer Institute, Switzerland
Tetsuo Shoji, Tohoku University, Japan
Harvey Solomon, Retired GE GRC, currently Solomon Metallurgical Consulting LLC
Jean Smith, Electric Power Research Institute, USA
Johan Stjarnsater, Studsvik AB, Sweden
Yoichi Takeda, Tohoku University, Japan
Bob Tapping, Atomic Energy of Canada Limited, Canada
Kurt Terrani, Oak Ridge National Laboratory, USA
Sebastian Teysseyre, Idaho National Laboratory, USA
Mychailo Toloczko3DFL¿F1RUWKZHVW1DWLRQDO/DERUDWRU\86$
François Vaillant, Electricité de France, France
Juan Varela, GE Power and Water, USA
Gary Was, University of Michigan, USA
Eric Willis, Electric Power Research Institute, USA
TK Yeh, National Tsing-Hua University, Taiwan
Toshio Yonezawa, Tohoku University, Japan
George Young, Bechtel Knolls, USA
xxviStudent Volunteers
Thomas Eiden, University of Wisconsin, USA
Wei-Jen Lai, University of Michigan, USA
Tyler Moss, University of Michigan, USA
Mike McMurtrey, University of Michigan, USA
Brandon Semerau, University of Wisconsin, USA
Kale Stephenson, University of Michigan, USA
xxviiFinancial Sponsors
xxixFinancial Sponsors (continued)
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