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13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007

召开年：2007
召开地：Whistler(CA)
出版时间：-

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1.MODELLING OF GRAIN BOUNDARY CR DEPLETION IN AUSTENITIC STEELS

机译：奥氏体钢中晶界CR损耗的模拟
- 作者：Roy Faulkner;Youfa Yin;Yunnan Gao;Ian Armson;Paul Moreton
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
2.Temperature, Potential and Sensitization Effects on Intergranular Crack Growth and Crack-tip appearance of Cold Worked 316

机译：温度，电位和敏化作用对冷加工316晶粒间裂纹扩展和裂纹尖端外观的影响
- 作者：Koji Arioka;Takuyo Yamada;Takumi Terachi;Tomoki Miyamoto
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
3.FLOW EFFECTS ON THE STRESS CORROSION CRACKING OF SENSITIZED STAINLESS STEELS UNDER BWR ENVIRONMENTS

机译：压水堆环境下敏化不锈钢应力腐蚀开裂的流动效应
- 作者：Clinton Fong
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
- intergranular stress corrosion cracking;
- type 304 stainless steel;
- boiling water reactor;
- flow effect;
4.ANALYSIS OF COOLANT LEAKAGES FROM A LABORATORY GROWN AXIAL CRACK OF A STEAM GENERATOR TUBE

机译：汽轮机实验室实验室轴向裂纹冷却液泄漏的分析
- 作者：Seong Sik Hwang;Dong Jin Kim;Man Kyo Jung;Joung Soo Kim;Hong Pyo Kim
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
5.Lifetime Evaluation for IASCC Initiation of Cold Worked 316 Stainless Steel's BFB in PWR Primary Water

机译：压水堆原水中IASCC启动冷加工316不锈钢的BFB的终生评估
- 作者：K. Takakura;K. Nakata;M. Ando;K. Fujimoto;E. Wachi
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
6.DEFORMATION BEHAVIOR AROUND GRAIN BOUNDARIES FOR SCC PROPAGATION IN HARDENED LOW-CARBON AUSTENITIC STAINLESS STEEL BY MICRO HARDNESS TEST

机译：低硬度奥氏体不锈钢硬化过程中SCC传播的晶界边界变形行为
- 作者：Nobuo Nagashima;Masao Hayakawa;Takashi Tsukada;Yoshiyuki Kaji;Yukio Miwa;Masami Ando;Kiyotomo Nakata
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
7.PREDICTING FLOW ACCELERATED CORROSION

机译：预测流动加速腐蚀
- 作者：Bryan Poulson
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
8.A LABORATORY STRESS CORROSION CRACKING TEST INCORPORATING HEAT TRANSFER

机译：包含传热的实验室应力腐蚀开裂测试
- 作者：Bryan Poulson
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
9.EFFECT OF VARIATIONS IN NOBLE METAL CHEMICAL ADDITION PROCESS ON ELECTROCHEMICAL CATALYTIC RESPONSE IN HIGH TEMPERATURE WATER

机译：贵金属化学添加过程中的变化对高温水中电化学催化反应的影响
- 作者：Young-Jin Kim;Peter L. Andresen;Samson Hettiarachchi;Thomas P. Diaz
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
10.EFFECT OF CORROSION POTENTIAL ON CORROSION FATIGUE CRACK GROWTH OF LOW-ALLOY STEELS IN HIGH-TEMPERATURE WATER

机译：高温下腐蚀电位对低合金钢腐蚀疲劳裂纹扩展的影响
- 作者：Hans-Peter Seifert;Stefan Ritter
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
11.INFLUENCE OF BORON AND LITHIUM ON THE CRACK GROWTH RATE OF ALLOY 600 IN PWR PRIMARY ENVIRONMENT

机译：硼和锂对压水堆主要环境中合金600裂纹扩展速率的影响
- 作者：Kjell Norring;Pal Efsing;Per-Olof Andersson
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
12.INFLUENCE OF DELTA PHASE PRECIPITATION ON THE STRESS CORROSION CRACKING RESISTANCE OF ALLOY 718 IN PWR PRIMARY WATER

机译：δ相沉淀对压水堆原水中合金718应力腐蚀开裂性能的影响
- 作者：Julien Deleume;Jean-Marc Cloue;Eric Andrieu
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
13.The Impact of Power Uprates on the Effectiveness of Hydrogen Water Chemistry in a Boiling Water Reactor

机译：功率提升对沸水反应堆中氢水化学有效性的影响
- 作者：Mei-Ya Wang;Tsung-Kuang Yen;Charles F. Chu;John Wang;Ching Chang
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
14.THE EFFECT OF OXIDE STRUCTURE ON THE ELECTROCHEMICAL CHARACTERISTICS OF ZrO_2 TREATED TYPE 304 STAINLESS STEELS IN HIGH TEMPERATURE PURE WATER

机译：高温纯水中氧化物结构对ZrO_2处理的304不锈钢电化学性质的影响。
- 作者：Tsung-Kuang Yen;Yuan-Chin Chien;Bai-Young Wang;Chuen-Horng Tsai
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
- IGSCC, zirconium oxide, hydrothermal deposition, potentiodynamic polarization;
15.COMPARISON OF LABORATORY AND FIELD EXPERIENCE OF PWSCC IN ALLOY 182 WELD METAL

机译：PWSCC在182焊接金属中的实验室和现场经验的比较。
- 作者：P. Scott;M-C Meunier;F. Steltzlen;O. Calonne;M. Foucault;P. Combrade;C. Amzallag
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
16.DEFORMATION UNDER IRRADIATION OF 304L AND 316 AUSTENITIC STAINLESS STEELS

机译：304L和316奥氏体不锈钢辐照下的变形
- 作者：J. Gamier;P. Dubuisson;M. Delnondedieu;J.-P. Massoud;Y. Brechet;S. Leclercq;J. Besson;P. Scott;X. Averty;F. Rozenblum
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
17.IASCC SUSCEPTIBILITY OF AUSTENITIC STAINLESS STEELS AND ALLOY 690 IN HIGH DISSOLVED OXYGEN WATER ENVIRONMENT

机译：奥氏体不锈钢和690合金在高溶解氧水环境中的IASCC敏感性
- 作者：Y. Chen;O. K. Chopra;W. K. Soppet;N. L. Dietz Rago;W. J. Shack
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
18.RADIATION INDUCED MICROSTRUCTURE, STRAIN LOCALIZATION AND IODINE-INDUCED STRESS CORROSION CRACKING IN PROTON-IRRADIATED ZIRCALOY-4

机译：质子辐照的ZIRCALOY-4的辐射诱导微观结构，应变局部化和碘诱导的应力腐蚀开裂
- 作者：A. Serres;L. Fournier;G. S. Was
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
19.CRACK INITIATION DUE TO ENVIRONMENTALLY ASSISTED CRACKING IN CARBON AND LOW-ALLOY STEELS EXPOSED TO HIGH-TEMPERATURE WATER

机译：暴露于高温水中的碳和低合金钢在环境中的开裂会导致裂纹萌生
- 作者：Armin Roth;John Hickling
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
20.Correlation between IASCC Growth Behavior and Plastic Zone Size of Crack Tip in 3.5 dpa Neutron Irradiated Type 304L SS CT Specimen

机译：3.5 dpa中子辐照304L SS CT试样中IASCC生长行为与裂纹尖端塑性区尺寸的相关性
- 作者：Tomomi Nakamura;Masato Koshiishi;Tadahiko Torimaru;Yuji Kitsunai;Kenichi Takakura;Kiyotomo Nakata;Masami Ando;Yoshihide Ishiyama;Anders Jenssen
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
21.Effect of Yttrium Thin Film Surface Modification on Corrosion Layers Formed on 9Cr ODS Steel in Supercritical Water

机译：钇薄膜表面改性对超临界水中9Cr ODS钢形成腐蚀层的影响
- 作者：Yun Chen;Kumar Sridharan;Todd R. Allen
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
- coating;
- yttrium;
- ferritic steel;
- high temperature oxidation;
- supercritical water;
- reactive element effect;
22.HOT CELL CRACK INITIATION TESTING OF VARIOUS HEATS OF HIGHLY IRRADIATED 316 STAINLESS STEEL COMPONENTS OBTAINED FROM THREE COMMERCIAL PWRs

机译：从三种商业压水堆获得的高辐射316不锈钢成分的各种热的热池裂纹萌生测试
- 作者：Paula D. Freyer;Thomas R. Mager;Michael A. Burke
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
23.Effect of Dynamic Strain Aging on the Environmentally Assisted Cracking of Low-Alloy Steels in Oxygenated High-Temperature Water

机译：动态应变时效对氧化高温水中低合金钢环境辅助开裂的影响
- 作者：B. Devrient;A. Roth;K. Kuster;U. Ilg;M. Widera
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
24.FIELD EXPERIENCE ON WELD ASSEMBLIES BEHAVIOUR TOWARD FLOW-ACCELERATED CORROSION IN FRENCH NUCLEAR POWER PLANTS (NPP)

机译：法国核电站对加速腐蚀的焊接组件的现场经验
- 作者：Virginie Calonne-Chatelee;Yannick Thebault;Odile de Bouvier;Lionel Dejoux;Stephane Trevin;Ellen-Mary Pavageau
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
25.EFFECTS OF OVERSIZED SOLUTES IN 316SS ON RADIATION-INDUCED SEGREGATION AND SCC SUSCEPTIBILITY

机译：316SS中过大溶质对辐射诱导的偏析和SCC敏感性的影响
- 作者：M. J. Hackett;G. S. Was
- 会议名称：《》 | 2007年
26.Corrosion Product Deposition Behavior on Heated Zircaloy-4 Surface in Simulated PWR Primary Water

机译：模拟压水堆一次水在加热的Zircaloy-4表面上的腐蚀产物沉积行为
- 作者：Hirotaka Kawamura;Masahiro Furuya
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
- corrosion product;
- crud;
- boric acid concentration;
- zircaloy-4;
- pwr primary coolant;
27.IASCC properties and mechanical behavior of stainless steels irradiated up to 73dpa

机译：IASCC性能和高达73dpa的不锈钢的力学性能
- 作者：Hiromasa Nishioka;Koji Fukuya;Katsuhiko Fujii;Tadahiko Torimaru
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
28.EFFECT OF SULFATE IONS ON STRESS CORROSION CRACK PROPAGATION IN AUSTENITIC STAINLESS STEELS UNDER MODIFIED PWR PRIMARY CONDITIONS

机译：改性压水堆条件下硫酸盐对奥氏体不锈钢应力腐蚀裂纹扩展的影响
- 作者：Mikito Hayano;Kimihiro Koba;Manabu Kanzaki;Tetsuo Yokoyama;Hiroyuki Anada
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
29.OBSERVATIONS OF CHANNEL DEFORMATION IN MILDLY-DEFORMED, LOW-DOSE 304L AUSTENITIC STAINLESS STEEL

机译：低变形低剂量304L奥氏体不锈钢通道变形的观察
- 作者：Wade Karlsen;Kenji Dohi;Takeo Onchi
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
30.ATEM SEM STUDY OF THE OXIDES DEVELOPED IN SCC CRACKS AND AT THE SURFACE OF NICKEL BASED ALLOYS EXPOSED IN PRIMARY WATER

机译：初生水中暴露于SCC裂纹和镍基合金表面的氧化物的ATEM和SEM研究
- 作者：L. Legras;F. Delabrouille;F. Vaillant;J.M. Boursier
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
31.CGR BEHAVIOR OF LOW CARBON STAINLESS STEEL OF HARDENED HEAT AFFECTED ZONE IN PLR PIPING WELD JOINTS

机译：PLR焊接接头中低碳热硬化区低碳不锈钢的CGR行为
- 作者：Masami Ando;Kiyotomo Nakata;Mikiro Itow;Norihiko Tanaka;Masato Koshiishi;Ryouji Obata;Yukio Miwa;Yoshiyuki Kaji;Masao Hayakawa
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
32.A REVIEW OF WELDABILITY AND SCC BEHAVIOURS OF NI-BASE WELD METALS IN LABORATORY PWR ENVIRONMENT

机译：实验室压水堆环境中镍基焊接金属的可焊性和SCC行为综述
- 作者：Francois Vaillant;Jean-Marie Boursier;Laurent Legras;Bernard Yrieix;Emmanuel Lemaire;J. Champredonde;Claude Amzallag
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
33.NEW APPLICATIONS OF ORIENTATION IMAGING MICROSCOPY (OIM) FOR CHARACTERIZING NUCLEAR COMPONENT FAILURE MODES, RELIABILITY ASSESSMENT, AND FITNESS-FOR-SERVICE

机译：定向成像显微镜（OIM）在表征核成分失效模式，可靠性评估和适用性上的新应用
- 作者：E.M. Lehockey;A.M. Brennenstuhl;S. Pagan;M.A. Clark;V. Perovic
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
34.INVESTIGATIONS ON THE MECHANISMS OF PWSCC OF STRAIN HARDENED AUSTENITIC STAINLESS STEELS

机译：应变硬化奥氏体不锈钢的PWSCC机理研究
- 作者：T. Couvant;L. Legras;C. Pokor;F. Vaillant;Y. Brechet;J.M. Boursier;P. Moulart
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
35.Effect of chlorides and sulfates on the EAC of austenitic stainless steel in PWR environment

机译：压水堆环境中氯化物和硫酸盐对奥氏体不锈钢EAC的影响
- 作者：T. Couvant;E. Herms;P. Combrade;F. Vaillant;I. de Curieres;J.M. Boursier;O. Raquet;O. de Bouvier
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
- environmentally assisted cracking;
- 304l;
- 316l;
- pwr;
- chloride;
- sulfate;
36.THE ROLE OF LOCALIZED DEFORMATION IN IASCC OF PROTON-IRRADIATED AUSTENITIC STAINLESS STEELS

机译：局部变形在质子辐照奥氏体不锈钢中的IASCC中的作用
- 作者：Z. Jiao;G. S. Was;J. T. Busby
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
37.STRESS CORROSION CRACKING OF NEUTRON-IRRADIATED STAINLESS STEEL IN SUPERCRITICAL WATER

机译：超临界水中中子辐照不锈钢的应力腐蚀开裂
- 作者：S. Teysseyre;G. S. Was
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
38.COMPARISON OF THE EFFECTS OF HYDROGEN PEROXIDE AND OXYGEN ON OXIDE FILMS ON STAINLESS STEEL AND CORROSION BEHAVIORS IN HIGH TEMPERATURE WATER

机译：高温水中过氧化氢和氧气对不锈钢膜和腐蚀行为的影响
- 作者：Shunsuke Uchida;Tomonori Satoh;Takashi Tsukada;Yoshiyuki Satoh;Yoichi Wada
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
39.EVALUATION OF FLOW ACCELERATED CORROSION OF PWR SECONDRAY COMPONENTS BY CORROSION ANALYSIS COUPLED WITH FLOW DYNAMICS ANALYSIS

机译：流动动力学分析与腐蚀分析评价压水堆次要组分的流动加速腐蚀
- 作者：Shunsuke Uchida;Masanori Naitoh;Yasushi Uehara;Hidetoshi Okada;Derek H. Lister
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
40.Corrosion fatigue behavior of an Alloy 52-A508 weldment and low alloy steels under simulated BWR coolant conditions

机译：模拟BWR冷却液条件下52-A508合金焊件和低合金钢的腐蚀疲劳行为
- 作者：J. Y. Huang;M. C. Young;S. L. Jeng;J. J. Yeh;J. S. Huang;R. C. Kuo
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
- corrosion fatigue crack growth rate;
- acpd technique;
- dissimilar metal weldment;
- water chemistry;
41.AN OVERVIEW OF THE COOPERATIVE IASCC RESEARCH (CIR) PROGRAM

机译：合作IASCC研究（CIR）计划概述
- 作者：R. Pathania;K. Gott;P. Scott
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
42.The effect of oxide film on electrochemical corrosion potential of stainless steel in high temperature water

机译：高温水中氧化膜对不锈钢电化学腐蚀电位的影响。
- 作者：Tomonori Satoh;Shunsuke Uchida;Takashi Tsukada;Yoshiyuki Satoh;Kari Maekelae
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
43.NICKEL ALLOY PRIMARY WATER BULK SURFACE AND SCC CORROSION FILM ANALYTICAL CHARACTERIZATION AND SCC MECHANISTIC IMPLICATIONS

机译：镍合金主要水面和SCC腐蚀膜的分析表征及SCC机理
- 作者：David Morton;Nathan Lewis;Michael Hanson;Steve Rice;Paul Sander
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
44.SCC CRACK GROWTH RATE OF COLD-WORKED AUSTENITIC STAINLESS STEELS IN PWR PRIMARY WATER CONDITIONS

机译：PWR主水条件下冷作奥氏体不锈钢的SCC裂纹增长率
- 作者：Catherine Guerre;Olivier Raquet;Emmanuel Herms;Stephane Marie;Marc Le Calvar
- 会议名称：《13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems 2007》 | 2007年
- stress corrosion cracking;
- crack growth;
- stainless steels;