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20170124071221.6 |
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|a (OCoLC)798928656
|z (OCoLC)880963312
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|a 10.1002/9781118456835
|b Wiley InterScience
|n http://www3.interscience.wiley.com
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|a TK9006
|b .I58 2011
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|a 621.48/3
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|a MAIN
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|a International Conference on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
|n (15th :
|d 2011 :
|c Colorado Springs, Colo.)
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|a 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors :
|b proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-- Water Reactors ; held August 7-11, 2011 at the Cheyenne Mountain Resort, Colorado Springs, Colorado /
|c edited by Jeremy T. Busby, Gabriel Ilevbare, and Peter L. Andresen.
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|a Fifteenth International Conference on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors
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|a Hoboken :
|b Wiley,
|c [2011]
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|c ©2011
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|a 1 online resource
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|a text
|b txt
|2 rdacontent
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|a computer
|b c
|2 rdamedia
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|a online resource
|b cr
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|a Description from online resource; title from PDF title page (viewed June 10, 2014).
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|a Includes bibliographical references and indexes.
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|a International conference proceedings.
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|a Overview of NRC Proactive Management of Materials Degradation (PMMD) Program / C E Gene Carpenter, Amy Hull, Greg Oberson -- Questions & Answers -- Conditions for Long Term Operation of Nuclear Power Plants in Sweden / Peter Ekstr̲m, Karen Gott, Bj̲rn Brickstad -- Current NRC Perspectives Concerning Primary Water Stress Corrosion Cracking / David Alley, Darrell Dunn -- Questions & Answers -- Evaluation of the Susceptibility to SCC Initiation of Alloy 690 in Simulated PWR Primary Water / Kazuya Tsutsumi, Thierry Couvant -- Questions & Answers -- Role of Cavity Formation on Crack Growth of Cold-Worked Carbon Steel, TT 690 and MA 600 in High Temperature Water / Koji Arioka, Tomoki Miyamoto, Takuyo Yamada, Takumi Terachi -- Crack Growth Testing on Cold Worked Alloy 690 in Primary Water Environment / David R Tice, Stuart L Medway, Norman Platts, John W Stairmand -- Questions & Answers -- One Dimensional Cold Rolling Effects on Stress Corrosion Crack Growth in Alloy 690 Tubing and Plate Materials / Mychailo B Toloczko, Matthew J Olszta, Stephen M Bruemmer -- Questions & Answers -- Cyclic and SCC Behavior of Alloy 690 HAZ in a PWR Environment / Bogdan Alexandreanu, Yiren Chen, Ken Natesan, Bill Shack -- Questions & Answers -- Stress Corrosion Crack Growth Rate Testing of Novel Composite Arrest Specimens / David S Morton, John V Mullen, Eric Plesko, John Sutliff, Nathan Lewis -- Questions & Answers -- Environmentally Assisted Crack Growth in Cold Worked Alloy 690TT in Primary Water at Low and High Temperatures / Qunjia Peng, Tetsuo Shoji, Juan Hou, Yoichi Takeda, Toshio Yonezawa -- Questions & Answers -- SCC of Alloy 690 and its Weld Metals / Peter L Andresen, Martin M Morra, Kawaljit Ahluwalia -- Questions & Answers -- SCC Behavior of Alloy 152 Weld in a PWR Environment / Bogdan Alexandreanu, Yiren Chen, Ken Natesan, Bill Shack -- Effect of Hot Cracks on EAC Crack Initiation and Growth in Nickel-Base Alloy Weld Metals / Hannu H̃nninen, Aki Toivonen, Anssi Brederholm, Tapio Saukkonen, Wade Karlsen, Ulla Ehrnsten, Pertti Aaltonen -- Questions & Answers -- Stress Corrosion Crack Growth of Alloy 52M in Simulated PWR Primary Water / MB Toloczko, MJ Olszta, SM Bruemmer -- Cyclic and SCC Behavior of Alloy 52M/182 Weld Overlay in a PWR Environment / Bogdan Alexandreanu, Yiren Chen, Ken Natesan, Bill Shack -- SCC of High CR Alloys in BWR Environments / Peter L Andresen -- Questions & Answers -- High-Resolution Characterizations of Grain Boundary Damage and Stress Corrosion Cracks in Cold-Rolled Alloy 690 / S M Bruemmer, M J Olszta, M B Toloczko, L E Thomas -- Research and Evaluation of Low Temperature Crack Propagation of NI Base Alloys in Actual Plants / Kimihisa Sakima, Harutaka Suzuki, Hideki Fujiwara -- Questions & Answers -- Penetrative Internal Oxidation from Alloy 690 Surfaces and Stress Corrosion Crack Walls during Exposure to PWR Primary Water / Matthew J Olszta, Daniel K Schreiber, Larry E Thomas, Stephen M Bruemmer -- Predicting Chromium Depletion of Nickel Base Alloys / Youfa Yin, Feng Zhu, Roy Faulkner, Ed Miller, Paul Moreton, Ian Armson, Bryan Borradaile -- Questions & Answers -- In-situ and Ex-situ Oxide Characterization by Synchrotron X-ray (SPring-8) in Non-Sensitized 316 Stainless Steel and High Temperature Water Combination / Toshio Yonezawa, Masashi Watanabe, Takahisa Shobu, Tetsuo Shoji -- Questions & Answers -- 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 / Jiaxin Chen, Fredrik Lindberg, Lyubov Belova, Bj̲rn Forssgren, Karen Gott, Johan Lejon, Audrius Jasiulevicius -- Questions & Answers -- Oxide Film Characterization along Crack Paths in Stainless Steel in Aerated and Deaerated Water Environments / Elaine West, David Morton, Nathan Lewis -- Questions & Answers -- 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 / Yoichi Takeda, Takayuki Sato, Daisuke Yamauchi, Tetsuo Shoji, Akio Ohji -- Questions & Answers -- The Effect of Cold Work on Microstructure and SCC Susceptibility in Simulated BWR Environment for Non-Sensitized Austenitic Stainless Steels / Yohei Sakakibara, Guen 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 / Yasufumi Miura, Yuichi Miyahara, Masaru Sato, Kenji Kako, Jun-Ichi Tani -- Questions & Answers -- Influence of Bulk and Surface Cold Work on Crack Initiation and Crack Growth of Austenitic Stainless Steels under Simulated BWR Environment / Bastian Devrient, Renate Kilian, Karin Kuster, Martin Widera -- Questions & Answers -- Effect of Nitrogen Addition in 304L Stainless Steel on the IGSCC Crack Growth Rate in Simulated BWR Environment / S Roychowdhury, V Kain, RC Prasad -- Questions & Answers -- Characterization of Type 304L Stainless Steel: Comparison of ASTM A262 Practice a and Analytical Electron Microscopy Techniques / BD Miller, MG Burke -- Questions & Answers -- The Effect of Grain Size on IGSCC in SS 316L in Simulated BWR Environment / Johan Stj̃rns̃ter, Bengt Bengtsson, Bj̲rn Forssgren, Hannah Johansson -- Questions & Answers -- An Investigation into Stress Corrosion Cracking of Dissimilar Metal Welds with 304L Stainless Steel and Alloy 82 in High Temperature Pure Water / Tsung-Kuang Yeh, Guan-Ru Huang, Chuen-Horng Tsai, Mei-Ya Wang -- Questions & Answers -- Deformation Mode and Microstructure on Stress Corrosion Cracking Path and Kinetics in High Temperature Water Environments / Zhanpeng Lu, Tetsuo Shoji, Seiya Yamazaki, Fanjiang Meng, Tichun Dan, Yoichi Takeda, Koji Negishi -- Questions & Answers -- Effect of Static Load Hold Periods on the Corrosion Fatigue Behavior of Austenitic Stainless Steels in Simulated BWR Environments / HP Seifert, S Ritter, H Leber -- Effects of Material Composition on Corrosion Fatigue Crack Growth of Austenitic Stainless Steels in High Temperature Water / Norman Platts, David Tice, Kevin Mottershead, Laura Mcintyre, Fabio Scenini -- Questions & Answers -- Fatigue Limit and Hysteresis Behavior of Type 304L Stainless Steel in Air and PWR Water, at 150ʻC and 300ʻC / H D Solomon, C Amzallag, AJ Vallee, AJ Vallee, RE Delair -- NRC Research Activities on Environmentally-Assisted Fatigue / Gary L Stevens, Robert L Tregoning -- Questions & Answers -- PWR Fuel Deposit Analysis at a B & W Plant with a 24 Month Fuel Cycle / Mike G Pop, Larry S Lamanna, Richard Harne, John Riddle -- Questions & Answers -- Effect of DH Concentration on Crud Deposition on Heated Zircaloy-4 in Simulated PWR Primary Water / Hirotaka Kawamura -- Questions & Answers -- Use of the Areva BWR Crud Model to Study High Zinc Operation at a US Plant / Mike G Pop, Larry Lamanna, Merl Bell, John Riddle, Alfred Hoornik -- Electrochemical Study of Pre -- and Post-Transition Corrosion of Zr Alloys in PWR Coolant / Jan Mac̀k, Radek Novotny, Petr Sajdl, Veronika Renciukov, Vera Vrtltv.
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|a Areva Fuel Condition Index for a Pressurized Water Reactor / Mike G Pop, Merl Bell, Brian Lockamon -- Structure and Thermodynamical Properties of Zirconium Hydrides from First-Principle / Jakob Blomqvist, Johan Olofsson, Anna-Maria Alvarez, Christina Bjerǩn -- Questions & Answers -- Hydride Behavior in Zircaloy-4 during Thermomechanical Cycling / Kimberly Colas, Arthur Motta, Mark R Daymond, Jonathan Almer, Zhonghou Cai -- Development of a Method for Studying the Influence of Stress State on the Iodine-Induced Stress Corrosion Cracking of Zirconium Alloys / Nathanael Mozzani, Quentin Auzoux, David Le Boulch, Eric Andrieu, Christine Blanc -- Wear of Zircaloy-4 Grid Straps Due to Fretting and Periodic Impacting with RV Internals Baffle Plates / Sarah Davidsaver, Stephen Fyfitch, Brian Friend, James Hyres -- Question from and affiliation -- Microstructure and SCC of Alloy X-750 / Peter L Andresen, Juan Flores-Preciado, Martin M Morra, Robert Carter -- Question from and affiliation -- Stress Corrosion Cracking and Crack Tip Characterization of Alloy X-750 in Boiling Water Reactor Environments / JP Gibbs, RG Ballinger, JH Jackson, D Isheim, H H̃nninen -- Question from and affiliation -- SCC Properties of Modified Alloy 718 in BWR Plant / Yoshinori Katayama, Motoji Tsubota, Yoshiaki Saito, Norihiko Tanaka, Shigeaki Tanaka -- Question from and affiliation -- Influence of Chloride Ions as Contaminants on the Corrosion Behavior of Alloy 718 in Pool Water of Nuclear Power Plants / Jonathan Hugues, Eric Andrieu, Christine Blanc, Jean-Marc Cloue -- Stress Corrosion Cracking Behavior near the Fusion Boundary of Dissimilar Weld Joint with Alloy 182-A533B Low Alloy Steel / Hiroshi Abe, Makoto Ishizawa, Yutaka Watanabe -- Question from and affiliation -- Effect of Chloride on Environmentally Assisted Cracking of Low Alloy Steels in Oxygenated High-Temperature Water -- General Corrosion / Matthias Herbst, Armin Roth, Erika Nowak, Ulf Ilg -- Question from and affiliation -- The Effect of Temperature on the Crack Growth Rate of Stainless Steel and NI-Alloys in Simulated BWR Environment / Johan Stj̃rns̃ter, Anders Jenssen, Christer Jansson, Karen Gott, Bj̲rn Forssgren, Bengt Bengtsson, Hannah Johansson -- Question from and affiliation -- Effects of Temperature and Corrosion Potential on SCC / Peter L Andresen, Russell A Seeman -- Question from and affiliation -- Effect of Thermal Aging on SCC, Material Properties and Fracture Toughness of Stainless Steel Weld Metals / T Lucas, R G Ballinger, H Hanninen, T Saukkonen -- Question from and affiliation -- Flow Accelerated Corrosion of Carbon Steel in the Feedwater System of PWR Plants -- Behaviour of Welds and Weld Assemblies / C Mansour, EM Pavageau, A Faucher, F Inada, K Yoneda, C Miller, J-L Bretelle -- Question from and affiliation -- Modelling Material Effects in Flow-Accelerated Corrosion / P Phromwong, Derek Lister, S Uchida -- 3D Atom-Probe Characterization of Stress and Cold-Work in Stress Corrosion Cracking of 304 Stainless Steel / K Kruska, S Lozano-Perez, D W Saxey, T Terachi, T Yamada, G D W Smith -- Question from and affiliation.
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| 505 |
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|a 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 / A Loucif, J-P Petit, Y Wouters, P Combrade -- Question from and affiliation -- Influence of Primary Water Chemistry on Oxides Formed on Alloy 600 and Alloy 690 / Thomas M Devine -- Characterizing Environmental Degradation in PWRs by 3D FIB Sequential Sectioning / Sergio Lozano-Perez, Na Ni, Karen Kruska, Chris Grovenor, Takumi Terachi, Takuyo Yamada -- Question from and affiliation -- On the Microstructure of Alloy 600 SCC Cracks Observed by TEM on PWR SG Pulled Tubes and on Laboratory Specimens / L Legras, O De Bouvier, F Delabrouille, E Fargeas, S Miloudi, Y Thebault -- Balance of Plant Corrosion Issues in Aging Nuclear Power Plants / George Licina, Dilip Dedhia -- Question from and affiliation -- Containment Liner Corrosion / Darrell Dunn, April Pulvirenti, Paul Klein -- Question from and affiliation -- Electrochemical Studies of Steam Generator Tube Degradation in the Presence of Thiosulphate / Lisheng Chi, Yucheng Lu -- Question from and affiliation -- 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 / Brad P Payne, Peter G Keech, N Stewart McIntyre -- Question from and affiliation -- Interaction of Microstructure, Composition, and Cold Work on the Stress Corrosion Cracking of Alloy 82 Weld Metal / DJ Paraventi, WC Moshier -- Question from and affiliation -- Stress Corrosion Cracking Behavior of Dissimilar Metal Weldments in High Temperature Water Environments / J Y Huang, M F Chiang, R C Kuo, J S Huang, S L Jeng -- Question from and affiliation -- SCC Crack Growth Rate of Alloy 82 in PWR Primary Water Conditions -- Effect of a Thermal Treatment -- / C Guerre, C Duhamel, M Sennour, J Cřpin, M Le Calvar -- Initiation of PWSCC of Weld Alloy 182 / Thierry Couvant, Francois Vaillant -- Questions & Answers -- NRC/EPRI Welding Residual Stress Validation Program -- Phase III / M Kerr, Lf Fredette, Hj Rathbun, Je Broussard -- Question from and affiliation -- Crack Growth Behavior of Irradiated Type 316 SS in Low Dissolved Oxygen Environment / Y Chen, B Alexandreanu, Y Yang, W J Shack, K Natesan, E E Gruber, A S Rao -- Question from and affiliation -- Stress Corrosion Crack Initiation Susceptibility of Irradiated Austenitic Stainless Steels / Kale J Stephenson, Yugo Ashida, Jeremy T Busby, Gary S Was -- Question from and affiliation -- Stress Corrosion Cracking Behavior of Type 304 Stainless Steel Irradiated under Different Neutron Dose Rates at JMTR / Yoshiyuki Kaji, Keietsu Kondo, Yoshiteru Aoyagi, Yoshiaki Kato, Taketoshi Taguchi, Fumiki Takada, Junichi Nakano, Hirokazu Ugachi, Takashi Tsukada, Kenichi Takakura, Hiroshi Sakamoto -- Question from and affiliation -- In-Pile Tests for IASCC Growth Behavior of Irradiated 316L Stainless Steel under Simulated BWR Condition in JMTR / Yasuhiro Chimi, Shigeki Kasahara, Hideo Ise, Yoshihiko Kawaguchi, Junichi Nakano, Yutaka Nishiyama -- Crack Growth Rates of Irradiated Commercial Stainless Steels in BWR and PWR Environments / Anders Jenssen, Johan Stj̃rns̃ter, Raj Pathania.
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| 505 |
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|a The Key Factors Affecting Crack Growth Behavior of Neutron-Irradiated Austenitic Alloys / Yugo Ashida, Alexander Flick, Peter L Andresen, Gary S Was -- Question from and affiliation -- Irradiation Assisted Stress Corrosion Cracking of Austenitic Stainless Steel WWER Reactor Core Internals / Anna Hojǹ, Miroslava Ernestov̀, Ossi Hietanen, Ritva Korhonen, Ludmila Hulinov̀, Ferenc Oszvald -- Question from and affiliation -- Slow Strain Rate Tensile Tests of Irradiated Austenitic Stainless Steels in Simulated PWR Environment / Y Chen, B Alexandreanu, W K Soppet, W J Shack, K Natesan, A S Rao -- Question from and affiliation -- Irradiation Assisted Stress Corrosion Cracking of Stainless Steels in a PWR Environment (A Combined Approach) / Morgane Le Millier, Olivier Calonne, J̌r̥me Cřpin, Cecilie Duhamel, Fabrice Gaslain, Eva Heripre, Ovidiu Toader, Yoann Vidalenc -- A Preliminary Hybrid Model of Irradiation-Assisted Stress Corrosion Cracking of 300 Series Stainless Steels in PWR Primary Environments / E D Eason, G Ilevbare, R Pathania -- Question from and affiliation -- Oxidation of a Proton-Irradiated 316 Stainless Steel in Simulated BWR NWC Environment / Zhijie Jiao, Gary Was -- Irradiation Creep and Irradiation Stress Relaxation of 316 and 304L Stainless Steels in Thermal and Fast Neutron Spectrum Reactors / John Paul Foster, Torill M Karlsen -- Question from and affiliation -- Recent Insights on the Parametric Dependence of Irradiation Creep of Austenitic Stainless Steels / F A Garner, E R Gilbert, V S Neustroev -- Question from and affiliation -- Cluster Dynamics Prediction of the Microstructure Evolution of 300-Series Austenitic Stainless Steel under Irradiation: Influence of Helium / M Zouari, L Fournier, A Barbu, Y Břchet -- Role of Slip Behavior in the Irradiation Assisted Stress Corrosion Cracking in Austenitic Steels / MD Mcmurtrey, GS Was -- Question from and affiliation -- Effect of Environment and Prestrain on IASCC of Austenitic Stainless Steels / W Lai, Z Jiao, G S Was -- Question from and affiliation -- Influence of Localized Plasticity on IASCC Sensitivity of Austenitic Stainless Steels under PWR Primary Water / Sarata Cisš, Benoit Tanguy, Lydia Laffont, Marie-Christine Lafont, Catherine Guerre, Eric Andrieu -- Deformation Microstructures of 30 dpa AISI 304 Stainless Steel after Monotonic Tensile and Constant Load Autoclave Testing / Wade Karlsen, Jnne Pakarinen, Aki Toivonen, Ulla Ehrnsťn -- Questions & Answers -- Degradation of Grain Boundary Strength by Oxidation in Alloy 600 / Katsuhiko Fujii, Terumitsu Miura, Hiromasa Nishioka, Koji Fukuya -- Questions & Answers -- Evaluation of the Oxygen Diffusion Coefficient in Nickel-Base Alloys / Hyo On Nam, Jae Young Yoon, Ji Hyun Kim, Il Soon Hwang, Kyu Hwan Lee -- Stress Corrosion Cracking of Alloy 600 in PWR Primary Water: Influence of Chromium, Hydrogen and Oxygen Diffusion / C Guerre, P Laghoutaris, J Ch̊ne, L Marchetti, R Molins, C Duhamel, M Sennour -- Question to Catherine GUERRE -- Grain Boundary Oxidation and Embrittlement Prior to Crack Initiation in Alloy 600 in PWR Primary Water / L Fournier, O Calonne, P Combrade, P Scott, P Chou, R Pathania.
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|a Electron Microscopy Characterizations and Atom Probe Tomography of Intergranular Attack in Alloy 600 Exposed to PWR Primary Water / Matthew J Olszta, Daniel K Schreiber, Larry E Thomas, Stephen M Bruemmer -- Question from and affiliation -- Grain Boundary Oxidation and Stress Corrosion Cracking in Nickel-Base Alloys Strained in Supercritical Water / Tyler Moss, Matthew J Olszta, William Grant, Gary S Was -- Question from and affiliation -- Quantitative Micro-Nano (QMN) Approach to SCC Mechanism and Prediction-Starting a Third Meeting / Roger W Staehle -- Question from and affiliation -- Strain Path Effect on IGSCC Initiation and Oxidation of Alloy 182 Exposed to PWR Primary Water / Thierry Couvant, Laurent Legras, Thierry Ghys, Paul Gambier, Nicolas Huin, Gabriel Ilevbare -- Question from and affiliation -- Experimental Study of Short Crack Coalescence in Nickel-Base Alloys in PWR Primary Water / O Calonne, L Fournier, P Combrade, P Scott, P Chou -- Question from and affiliation -- 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 / Nobuo Totsuka, Takumi Terachi, Kenichi Takakura -- Question from and affiliation -- Crystallographical Characterization of Initiation of Intergranular Stress Corrosion Cracking of Alloy 600 in PWR Environment / Shinji Fujimoto, Masahito Mochizuki, Yuya Morita, Yoshiki Mikami, Hiroaki Tsuchiya, Kazutoshi Nishimoto -- Question from and affiliation -- Environmental Effects on PWSCC Initiation and Propagation in Alloy 600 / Anders Molander, Kjell Norring, Per-Olof Andersson, P̄l Efsing -- Question from and affiliation -- Probabilistic Environmentally Assisted Cracking Modeling for Primary Water Stress Corrosion Cracking of Alloy 600 / Taehyun Lee, Jaeyoung Yoon, Hyoon Nam, Ilsoon Hwang -- Question from and affiliation -- The Role of Lattice Curvature on the SCC Susceptibility of Alloy 600 / Fabien L̀onard, Fabio Di Gioacchino, Robert A Cottis, Francois Vaillant, Joao Quinta Da Fonseca, Florence Carrette, Gabriel Ilevbare -- Question from and affiliation -- PWSCC Susceptibility in Heat Affected Zones of Alloy 600 / Thierry Couvant, Thomas Brossier, Christian Cossange -- Question from and affiliation -- Quantitative Residual Strain Analyses on Strain Hardened Nickel Based Alloy / Toshio Yonezawa, Takaharu Maeguchi, Toru Goto, Hou Juan -- The Study of Stress Corrosion Cracking on Alloy 600 C-Ring Samples by Polychromatic X-Ray Microdiffraction / Jing Chao, Marina L Suominen Fuller, N Stewart McIntyre, Anatolie G Carcea, Roger C Newman, Martin Kunz, Nobumichi Tamura -- Question from and affiliation -- Proposed Coordinated U.S. PWR Reactor Vessel Surveillance Program: An Updated Summary Including Program Optimization / Ryan Hosler, Sarah Davidsaver, Timothy Hardin, Dennis Weakland, Greg Troyer -- Developing PWR Aging-Management Strategies for Reactor Vessel Internals / SB Davidsaver, S Fyfitch, H Xu -- Development of the Extremely Low Probability of Rupture (xLPR) Code / David L Rudland, Craig Harrington -- Question from and affiliation -- Databases of Operationally Induced Damage / Karen Gott -- Question from and affiliation.
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|a Introduction to a New Real-Time Water Chemistry Measurement System / Jei-Won Yeon, Myung-Hee Yun, Kyuseok Song -- Question from and affiliation -- Comparison of DBU, NH, DMA, ETA, and Morpholine Interactions with Ferrous Chloride Solution and Carbon Steel Surfaces / S Nasrazadani, A Reid, J Stevens, R Theimer, B Fellers -- Question from and affiliation -- Role of Dissolved Hydrogen in Water in Corrosion of Alloy 600 in High Temperature Water / Qunjia Peng, Tetsuo Shoji, Juan Hou, Kazuhiko Sakaguchi, Yoichi Takeda -- Question from and affiliation -- Quantifying the Benefit of Chemical Mitigation of PWSCC via Zinc Addition or Hydrogen Optimization / Chuck Marks, Matthew Dumouchel, Richard Reid, Glenn White -- Question from and affiliation -- Computational Thermodynamics for Interpreting Oxidation of Structural Materials in Supercritical Water / Lizhen Tan, Ying Yang, Todd R Allen, Jeremy T Busby -- Question from and affiliation -- Stress Corrosion Cracking of Austenitic Alloys in Supercritical Water / Guoping Cao, Vahid Firouzdor, Todd Allen -- Question from and affiliation -- Comparison of the Corrosion Behavior of the 14CR ODS Alloy in Steam and Supercritical Water / Jeremy Bischoff, Arthur T Motta -- Question from and affiliation -- Grain Boundary Engineering and Air Oxidation Behavior of Alloy 690 / Peng Xu, Liang Y Zhao, Kumar Sridharan, Todd R Allen -- Question from and affiliation -- Developments in SCC Mitigation by Electrocatalysis / Peter L Andresen, Young J Kim -- Question from and affiliation -- Use of Noble Metal Nanopartice for SCC Mitigation in BWRs / Young-Jin Kim, Peter L Andresen, Samson Hettiarachchi -- Question from and affiliation -- The Influence of Minor Additions of Platinum Group Metals on Stress Corrosion Cracking in Austenitic Stainless Steels / K Govender, F Scenini, S Lyon, O Necib, A Sherry -- Question from and affiliation -- The Effect of On-Line Noble Metal Addition on the Shut down Dose Rates of Boiling Water Reactors / Robert L Cowan, Juan Varela, Susan E Garcia -- Question from and affiliation -- Effects of Hydrogen on SCC Growth Rate of NI Alloys in BWR Water / Peter L Andresen, Peter Chou -- Technical Basis for Water Chemistry Control of IGSCC in Boiling Water Reactors / Barry Gordon, Susan Garcia -- Question from and affiliation -- Water Chemistry in the Primary Coolant Circuit of a Boiling Water Reactor during Startup Operations / Tsung-Kuang Yeh, Mei-Ya Wang -- Simulation of Water Radiolysis by Sonochemistry: Effects on the Electrochemical Behavior of a Stainless Steel / O Lavigne, Y Takeda, T Shoji -- Question from and affiliation -- Protective Insulated Coating for SCC Mitigation in BWRs / Young-Jin Kim, Peter L Andresen -- Question from and affiliation -- Influence of Treating Temperature on the Deposition of TIO on Type 304 Stainless Steels for Corrosion Mitigation in High Temperature Pure Water / Tsung-Kuang Yeh, Yu-Jen Huang, Chuen-Horng Tsai -- Question from and affiliation -- Irradiation Microstructure of Austenitic Steels and Cast Steels Irradiated in the BOR-60 Reactor at 320ʻC / Yong Yang, Yiren Chen, Yina Huang, Todd Allen, Appajosula Rao -- Question from and affiliation -- Laboratory Stress Corrosion Cracking Propagation in a Superficial Cold-Worked Layer in SG Divider Plates in Alloy 600 / Fraṅois Vaillant, C̀cile Leseigneur, Patrick Le-Delliou, Thierry Couvant, Salem Miloudi, Yannick Th̀bault, Damien Deforge, Emmanuel Lemaire.
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|a Destructive Examinations on Divider Plates from Decommissioned Steam Generators Affected by Superficial Stress Corrosion Cracks / Salem Miloudi, Erwan Firmin, Damien Deforge, Francis Vaillant, Emmanuel Lemaire -- Question from and affiliation -- Investigations on Core Basket Bolts from a VVER 440 Power Plant / Ulla Ehrnsťn, Petri Kyt̲m̃ki, Ossi Hietanen -- Question from and affiliation -- Laboratory Analysis of Reactor Coolant Pump Seals / Michael Sullivan, James Hyres -- PWSCC of Thermocoax Pressurizer Heaters in Austenitic Stainless Steel and Remedial Actions to Preventing SCC / Y Thebault, P Moulart, K Dubourgnoux, J Champredonde, T Couvant, Y Neau, J-M Fageon, D Lecharpentier, A Breuil, V Derouet -- Residual Stress Measurement and the Effect of Heat Treatment in Cladded Control Rod Drive Specimens / Ashley Bowman, Ed Kingston, Jinya Katsuyama, Makoto Udagawa, Kunio Onizawa -- Question from and affiliation -- Detailed Root Cause Analysis of SG Tube ODSCC Indications within the Tube Sheets of NPP Biblis Unit A / R Kilian, J Beck, H Lang, T Sch̃nherr, M Widera -- Question from and affiliation -- Laboratory Investigation of a Leaking Type 316 Socket Weld in a Boron Injection Tank Sampling Line / Hongqing Xu, Steve Fyfitch, Ryan Hosler, James Hyres -- Pressure Tests on SG Pulled Tubes at TSP Level / Marc Boccanfuso, C̀dric Mathon -- Implications of Steam Generator Fouling on the Degradation of Material and Thermal Performance / Carl W Turner -- Question from and affiliation -- Key Issues Related to Corrosion Protection of Brackish Water and Seawater Bearing Components in Cooling Water Systems / Erika Nowak, Bengt Bengtsson, Bj̃rn Forssgren, Bj̃rn Hall, Elisabeth Johansson -- Understanding the Limits of Lattice Orientation Data Analysis in Environmental Degradation Studies / Fabio Di Gioacchino, Jôo Quinta Da Fonseca, David Wright, Fabio Scenini -- Question from and affiliation -- Microstructural Investigation on the Effect of Cold Work on Environmentally Assisted Cracking of Austenitic Stainless Steel / David Wright, Fabio Di Gioacchino, Fabio Scenini, Jôo Quinta Da Fonseca, Samaneh Nouraei, Kevin Mottershead, David Tice -- Question from and affiliation -- Plastic Strain and Residual Stress Distributions in an AISI 304 Stainless Steel BWR Pipe Weld / Tapio Saukkonen, Miikka Aalto, Iikka Virkkunen, Ulla Ehrnsťn, Hannu H̃nninen -- Assessment of Lean Grade Duplex Stainless Steels for Nuclear Power Applications / George A Young, Julie D Tucker, Nathan Lewis, Eric Plesko, Paul Sander -- Effects of Thermo-Mechanical Treatments on Deformation Behavior and IGSCC Susceptibility of Stainless Steels in PWR Primary Water Chemistry / S Nouraei, D R Tice, K J Mottershead, D M Wright -- Question from and affiliation -- SCC Initiation Testing of Alloy 600 in High Temperature Water / Robert A Etien, Edward Richey, David S Morton, Julie Eager -- The Effects of Deaerated Water on the Toughness of Nickel-Based Alloys / Edward Richey, George A Young -- Physical Metallurgy, Weldability, and In-Service Performance of Nickel-Chromium Filler Metals Used in Nuclear Power Systems / George A Young, Robert A Etien, Micah J Hackett, Julie D Tucker, Thomas E Capobianco.
|
| 650 |
|
0 |
|a Nuclear power plants
|x Corrosion
|v Congresses.
|
| 650 |
|
0 |
|a Water cooled reactors
|x Corrosion
|v Congresses.
|
| 650 |
|
0 |
|a Nuclear power plants
|x Materials
|x Effect of radiation on
|v Congresses.
|
| 650 |
|
7 |
|a Nuclear power plants
|x Corrosion.
|2 fast
|0 (OCoLC)fst01040465
|
| 650 |
|
7 |
|a Nuclear power plants
|x Materials
|x Effect of radiation on.
|2 fast
|0 (OCoLC)fst01040599
|
| 650 |
|
7 |
|a Water cooled reactors
|x Corrosion.
|2 fast
|0 (OCoLC)fst01171671
|
| 655 |
|
4 |
|a Electronic books.
|
| 655 |
|
7 |
|a Conference papers and proceedings.
|2 fast
|0 (OCoLC)fst01423772
|
| 700 |
1 |
|
|a Busby, Jeremy T.,
|d 1972-
|
| 700 |
1 |
|
|a Ilevbare, Gabriel.
|
| 700 |
1 |
|
|a Andresen, Peter L.
|
| 776 |
0 |
8 |
|i Print version:
|a International Conference on Environmental Degradation of Materials in Nuclear Power Systems--Water Reactors.
|t 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors : proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors ; held August 7-11, 2011 at the Cheyenne Mountain Resort, Colorado Springs, Colorado.
|d Hoboken, N.J. : John Wiley & Sons, 2012, ©2011
|z 9781118132418
|
| 856 |
4 |
0 |
|u https://doi.org/10.1002/9781118456835
|z Full Text via HEAL-Link
|
| 994 |
|
|
|a 92
|b DG1
|
