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International conference on environmental degradation of materials in nuclear power systems water reactors

召开年：2009
召开地：Virginia Beach, VA(US)
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1.FAC Mitigation Technology in BWR

机译：BWR中的FAC缓解技术
- 作者：Young-Jin Kim
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
2.CRACK GROWTH RATE TESTING OF FAST REACTOR IRRADIATED TYPE 304L AND 316 SS IN BWR AND PWR ENVIRONMENTS

机译：快速反应堆辐照的304L和316 SS在BWR和PWR环境中的裂纹扩展速率测试
- 作者：Anders Jenssen;Johan Stjarnsater;Raj Pathania
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
3.EFFECTS OF ALLOY COMPOSITION OF CARBON STEEL ON THE FLOW ACCELERATED CORROSION AND OXIDE FILM PROPERTIES IN NEUTRAL WATER CONDITION

机译：碳钢合金成分对中性水流加速腐蚀及氧化膜性能的影响
- 作者：Tomonori Satoh;Hirokazu Ugachi;Takashi Tsukada;Shunsuke Uchida
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
4.LONG RANGE ORDERING OF ALLOY 690

机译：合金690的长期订购
- 作者：F. DELABROUILLE;D. RENAUD;F. VAILLANT;J. MASSOUD
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
5.FORMATION OF CRACK EMBRYOS PRIOR TO CRACK GROWTH IN HIGH TEMPERATURE WATER

机译：高温水中裂纹增长之前裂纹胚胎的形成
- 作者：Koji Arioka;Tomoki Miyamoto;Takuyo Yamada;Takumi Terachi
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
6.DEFORMATION LOCALISATION AND EAC IN INHOMOGENEOUS MICROSTRUCTURES OF AUSTENITIC STAINLESS STEELS

机译：奥氏体不锈钢不均匀组织中的变形局部化和EAC
- 作者：Ulla Ehrnsten;Tapio Saukkonen;Wade Karlsen;Hannu Hanninen
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
7.Characteristic of Grain Boundary Having SCC Susceptibility for Low Carbon Austenitic Stainless Steel in High Temperature Water

机译：低碳奥氏体不锈钢在高温水中具有SCC敏感性的晶界特征
- 作者：Yohei Sakakibara;Keiji Kubushiro;Guen Nakayama
- 会议名称：《》 | 2010年
8.3-D CHARACTERIZATION OF SCC IN COLD WORKED STAINLESS STEELS

机译：冷加工不锈钢中SCC的3-D表征
- 作者：Sergio Lozano-Perez;David Saxey;Takumi Terachi;Takuyo Yamada;Lionel Cervera-Gontard
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
9.SCC Retardation and Propagation Behavior in Dissimilar Weldment of Alloy 182 and Low Alloy Steel

机译：182合金和低合金钢在异种焊缝中的SCC延迟和传播行为
- 作者：Tatsuya Kubo;Mikiro Itow;Norihiko Tanaka;Toshiyuki Saito
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
10.INFLUENCE OF DYNAMIC STRAIN AGEING ON THE CRACK GROWTH RATES AND CRACK TIP PLASTICITY OF LOW-ALLOY STEELS IN OXYGENATED HIGH-TEMPERATURE WATER

机译：动态应变时效对高温高温低合金钢的裂纹扩展速率和裂纹尖端塑性的影响
- 作者：B. Devrient;A. Roth;K. Kuster;M. Widera;U. Ilg
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
11.ISSUES AND ADVANCES IN THE ASSESSMENT OF FLOW ACCELERATED CORROSION

机译：流动加速腐蚀评估中的问题和进展
- 作者：Yogendra. S. Garud
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
12.Evaluation of Wall Thinning Rate due to Flow Accelerated Corrosion with the Coupled Models of Electrochemical Analysis and Double Oxide Layer Analysis

机译：电化学分析和双氧化层分析耦合模型评估流动加速腐蚀引起的壁变薄率
- 作者：Shunsuke Uchida;Masanori Naito;Yasushi Uehara;Hidetoshi Okada;Seiichi Koshizuka;Derek H. Lister
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
13.Electrochemical Corrosion Potential (ECP) Reduction and Crack Mitigation Experiences With NobleChem? and On-Line NobleChem?

机译：NobleChem的电化学腐蚀电位（ECP）降低和裂纹缓解经验？和在线NobleChem？
- 作者：S. Hettiarachchi;R.M. Horn;P.L. Andresen;Y.J. Kim
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
14.Impact of Power Coastdown Operations on the Effectiveness of Hydrogen Water Chemistry in Boiling Water Reactors

机译：动力滑行运行对沸水反应堆中氢水化学有效性的影响
- 作者：Tsung-Kuang Yeh;Mei-Ya Wang;Charles F. Chu;Ching Chang
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
15.A NEW CONCEPT SENSOR FOR DETERMINATION OF OXYGEN AND HYDROGEN PEROXIDE CONCENTRATIONS IN NUCLEAR REACTOR COOLANT

机译：测定核反应堆冷却剂中氧气和过氧化氢浓度的新概念传感器
- 作者：Tomonori Satoh;Yukio Miwa;Takashi Tsukada;Shunsuke Uchida
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
16.CHARACTERIZATION OF PWR CRUD PHASES AND THEIR VARIATION UNDER PLANT OPERATION BY TRANSMISSION ELECTRON MICROSCOPY

机译：透射电子显微镜在工厂操作下压水堆压挤相的表征及其变化
- 作者：H. Bergqvist;J. Chen;D. Jadernas;B. Bengtsson
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
17.The Influence of ZrO_2 Treatment on the Electrochemical Behavior of Hydrogen Peroxide on Type 304 Stainless Steels in High Temperature Water

机译：ZrO_2处理对304不锈钢在高温水中过氧化氢电化学行为的影响。
- 作者：T. K. Yeh;P. I. Wu;C. H. Tsai
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
18.RADIATION INDUCED 'LONG CELL' (MACROCELL) CORROSION IN PWRs AND BWRs

机译：辐射导致压水堆和压水堆中的“长细胞”（宏观细胞）腐蚀
- 作者：Genn Saji
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
19.SELECTION OF WATER CHEMISTRY FOR SUCCESSFUL OPERATION OF WATER-COOLED FUSION MACHINES

机译：水冷式熔接机成功运行的水化学选择
- 作者：Andrei Y. Petrov;Jan B. Berry;Otakar Jonas;Lee Machemer
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
20.POSSIBLE ALTERNATIVES TO SODIUM PHOSPHATE FOR NON-VOLATILE pH CONTROL IN STEAM GENERATORS

机译：用于蒸汽发生器中非挥发性pH控制的磷酸钠替代品
- 作者：Bryan Poulson;Vince Evans;Geoff Bignold
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
21.Evaluation of the Effects 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潜能的影响评价
- 作者：Shunsuke Uchida;Tomonori Satoh;Takashi Tsukada;Takahiro Miyazawa;Yoshiyuki Satoh;Keizo Ishii
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
22.Effect of Ni/Fe Ratio and Ni Concentration on Crud Deposition Behavior on Heated Zircaloy-4 Surface in Simulated PWR Primary Water

机译：Ni / Fe比和Ni浓度对模拟压水堆原水加热的Zircaloy-4表面粗粒沉积行为的影响
- 作者：Hirotaka Kawamura;Masahiro Furuya
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
- corrosion product;
- crud;
- nickel concentration;
- ni/fe ratio;
- zircaloy-4;
- pwr primary coolant;
23.STUDIES OF IRON REDOX STATES, CORROSION POTENTIALS AND OXYGEN REDUCTION IN A SIMULATED FEEDWATER TRAIN

机译：模拟饲料废水中铁的氧化还原态，腐蚀电位和氧还原的研究
- 作者：Stefan Forsberg;Peter Gillen;Per-Olof Andersson;Jerzy A. Sawicki
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
24.OXIDE INVESTIGATION FORMED ON ALLOY 600 IN LEADED AQUEOUS SOLUTIONS

机译：含铅水溶液中600合金上的氧化物调查
- 作者：Dong-Jin Kim;Mi Ae Kim;Hyuk Chul Kwon;Seong Sik Hwang;Joung Soo Kim;Jun Hwa Hong;Hong Pyo Kim
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
25.CRITERIA FOR INITIATION OF IRRADIATION-ASSISTED STRESS CORROSION CRACKING IN STAINLESS STEELS IN PWR SYSTEMS

机译：压水堆系统中钢中辐照辅助应力腐蚀开裂的初始化标准
- 作者：Stephen Fyfitch;Hongqing Xu;Peter Scott;Lionel Fournier;Anne Demma
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
26.INFLUENCE OF M ICROSTRUCTURE ON IASCC GROWTH BEHAVIOR OF NEUTRON IRRADIATED TYPE 304 AUSTEN ITIC STAIN LESS STEELS IN SIMULATED BWR CONDITION

机译：微观结构对模拟BWR条件下中子辐照304型奥氏体不锈钢的IASCC生长行为的影响
- 作者：Yoshiyuki Kaji;Yukio Miwa;Akira Shibata;Junichi Nakano;Takashi Tsukada;Kenichi Takakura;Kiyotomo Nakata
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
27.CRACK GROWTH BEHAVIOR OF NEUTRON IRRADIATED L-GRADE AUSTENITIC STAINLESS STEELS IN SIMULATED BWR CONDITIONS

机译：模拟BWR条件下中子辐照L级奥氏体不锈钢的裂纹扩展行为
- 作者：Kenichi Takakura;Kiyotomo Nakata;Shigeaki Tanaka;Tomomi Nakamura;Kazuhiro Chatani;Yoshiyuki Kaji
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
28.IASCC Properties of Cold Worked 316 Stainless Steel in PWR Primary Water

机译：PWR一次水冷加工316不锈钢的IASCC特性
- 作者：Kenichi Takakura;Kiyotomo Nakata;Koji Fujimoto;Kimihisa Sakima;Noboru Kubo
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
29.INTERGRANULAR CRACKING BEHAVIOR OF IRRADIATED AUSTENITIC ALLOYS IN SUPERCRITICAL WATER

机译：超临界水中辐照奥氏体合金的晶间断裂行为
- 作者：G. S. Was;R. Zhou;E. A. West;Z. Jiao
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
30.CRACK GROWTH RATES AND FRACTURE TOUGHNESS OF NEUTRON IRRADIATED GRAIN- BOUNDARY-ENGINEERED AUSTENITIC STAINLESS STEELS

机译：中子辐照的晶界-奥氏体不锈钢的裂纹扩展速率和断裂韧性
- 作者：Y. Chen;O. K. Chopra;Y. Yang;W. J. Shack;B. Alexandreanu;E. E. Gruber;A. S. Rao
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
31.CRACK GROWTH RATE AND FRACTURE TOUGHNESS OF AUSTENITIC STAINLESS STEELS IN A PWR PRIMARY WATER ENVIRONMENT

机译：压水堆主要水环境中奥氏体不锈钢的裂纹扩展速率和断裂韧性
- 作者：J.K. McKinley;E.W. Deemer;R.J. Jacko;R.G. Lott
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
32.AN ATOM PROBE TOMOGRAPHY STUDY OF PROTON-IRRADIATED AUSTENITIC STAINLESS STEELS

机译：质子辐照奥氏体不锈钢的原子探针层析成像研究
- 作者：Z. Jiao;G. S. Was;P. Chou
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
33.The Investigation of the Damages of Irradiated 316L Stainless Steel Used for the Hafnium Plate Type of Control Rods in BWR Plants

机译：BWR厂WR板式控制棒用辐照316L不锈钢的损伤研究
- 作者：S. Ooki;A. Miyazaki;H. Tezuka;M. Taguchi;S. Suzuki
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
34.MODELLING GRAIN BOUNDARY CHROMIUM DEPLETION IN AUSTENITIC ALLOYS

机译：模拟奥氏体合金中晶界的铬损耗
- 作者：Youfa Yin;Roy G Faulkner;Paul Moreton;Ian Armson
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
35.CHARACTERIZATION OF IASCC CRACK TIP IN HIGHLY IRRADIATED STAINLESS STEELS

机译：高辐照不锈钢中IASCC裂纹尖端的表征
- 作者：Koji Fukuya;Hiromasa Nishioka;Katsuhiko Fujii;Yuji Kitsunai
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
36.Effect of Chemical Compositions on IGSCC Resistance for Strain Hardened Low Carbon Austenitic Stainless Steels in High Temperature Water

机译：化学成分对高温水中应变硬化低碳奥氏体不锈钢抗IGSCC的影响
- 作者：Toshio Yonezawa;Hiroshi Kanasaki;Masaki Taneike;Yasuhiro Sakaguchi;Suguru Ooki;Hideshi Tezuka;Kenro Takamori;Shunichi Suzuki
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
37.EVALUATION OF LOCALIZED DEFORMATON AT LOW STRAIN LEVELS IN AUSTENITIC STAINLESS STEEL IRRADIATED BY PROTON

机译：质子辐照奥氏体不锈钢低应变水平局部变形的评价。
- 作者：Takashi TANNO;Akira HASEGAWA;Shuto SASAKI;Shuhei NOGAMI;Manabu SATOU
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
38.CRACKING BEHAVIOR OF IRRADIATED HEAT-AFFECTED ZONE SPECIMENS OF TYPE 304 AND 304L STAINLESS STEEL WELDS IN HIGH-PURITY WATER

机译：304和304L不锈钢在高纯水中辐照热影响区试样的开裂行为
- 作者：Y. Chen;W. J. Shack;B. Alexandreanu;E. E. Gruber;A. S. Rao
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
39.FRACTURE TOUGHNESS OF IRRADIATED STAINLESS STEEL IN NUCLEAR POWER SYSTEMS

机译：核动力系统中辐照不锈钢的断裂韧性
- 作者：Stephen Fyfitch;Hongqing Xu;Anne Demma;Robert Carter;Ron Gamble;Peter Scott
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
40.MICROSTRUCTURE AND GRAIN BOUNDARY CHEMISTRY EVOLUTION IN AUSTENITIC STAINLESS STEELS IRRADIATED IN THE BOR-60 REACTOR UP TO 120 DPA

机译：BOR-60反应器中高达120 DPA辐照的奥氏体不锈钢的微观结构和晶粒边界化学变化
- 作者：Alexandra-Evelyne Renault;Cedric Pokor;Jerome Gamier;Joel Malaplate
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
41.DOSE DEPENDENCE OF RADIATION HARDENING OF AUSTENITIC STEELS IN BOR-60 AT PWR-RELEVANT TEMPERATURES

机译：压水堆温度下BOR-60中奥氏体钢辐射硬化的剂量依赖性
- 作者：Yong Yang;Yiren Chen;Todd R. Allen;Omesh K. Chopra
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
42.IMPACT OF Ni-59 (n, a) AND (n, p) REACTIONS ON DPA RATE, HEATING RATE, GAS GENERATION AND STRESS RELAXATION IN LMR, LWR AND CANDU? REACTORS

机译：Ni-59（n，a）和（n，p）反应对LMR，LWR和Candu中DPA速率，加热速率，气体生成和应力松弛的影响？反应器
- 作者：F. A. Garner;L. R. Greenwood;E. R. Gilbert;Malcolm Griffiths
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
43.A NEW DEFORMATION MODE OBSERVED IN AUSTENITIC LOW-NICKEL STAINLESS STEELS IRRADIATED TO HIGH NEUTRON EXPOSURE AT 310-432C

机译：奥氏体低镍不锈钢在310-432C辐照高中子辐照下观察到的新变形模式
- 作者：M. N. Gusev;D. A. Toktogulova;O. P. Maksimkiri;F. A. Garner
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
44.INFLUENCE OF SURFACE PEENING ON THE WELD ABILITY OF NEUTRON-IRRADIATED STAINLESS STEEL

机译：表面针刺对中子辐照不锈钢焊接性能的影响
- 作者：Masato Koshiishi;Tomomi Nakamura;Kyoichi Asano
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
45.IRRADIATION CREEP AND IRRADIATION STRESS RELAXATION OF 316 AND 304L STAINLESS STEEL

机译：316和304L不锈钢的辐照蠕变和辐照应力松弛。
- 作者：John Paul Foster;Torill Karlsen
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
46.THE EFFECT OF PRIOR COLD-WORK ON THE DEFORMATION BEHAVIOR OF NEUTRON IRRADIATED AISI 304 AUSTENITIC STAINLESS STEEL

机译：预先冷作对中子辐照AISI 304奥氏体不锈钢的变形行为的影响
- 作者：Wade Karlsen;Steven Van Dyck
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
- irradiation;
- cold-work;
- deformation;
- tem;
47.REVIEW ON ELECTROCHEMICAL CORROSION OF ZIRCONIUM ALLOYS IN HIGH TEMPERATURE WATER

机译：高温水中锆合金的电化学腐蚀研究进展
- 作者：Raul B. Rebak;Yang-Pi Lin;Young-Jin Kim
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
48.THE ATOMIC SCALE STRUCTURE AND CHEMISTRY OF THE ZIRCALOY-4 METAL-OXIDE INTERFACE

机译：ZIRCALOY-4金属氧化物界面的原子尺度结构和化学性质
- 作者：Daniel Hudson;Na Ni;Sergio Lozano-Perez;David Saxey;Colin English;George D. W. Smith;John Sykes;Chris Grovenor
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
49.THE EFFECT OF RESIDUAL STRESS ON GROWTH OF OXIDE SCALE ON ZIRCONIUM ALLOYS

机译：残余应力对锆合金氧化皮生长的影响
- 作者：E. Polatidis;P.G. Frankel;M. Preuss
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
50.CORROSION AND HYDRIDING PERFORMANCE OF ALLOY M5? IN U.S. REACTORS

机译：M5合金的腐蚀和氢化性能？在美国反应堆中
- 作者：M. T. Machut;G. L. Garner;J. P. Mardon;P. B. Hoffmann
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
51.CRACK GROWTH RATE AND HYDRIDE CRACKING WITH TEMPERATURE IN DELAYED HYDRIDE CRACKING OF ZIRCONIUM ALLOYS

机译：锆合金延迟氢化裂解中的裂纹扩展速率和温度的氢化裂解
- 作者：Young S. Kim
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
52.INFLUENCE OF ZIRCONIUM HYDRIDES ON ZIRCALOY-4 CORROSION IN PWR SIMULATED CONDITIONS IN LABORATORY

机译：实验室模拟压水堆中氢化锆对ZIRCALOY-4腐蚀的影响
- 作者：Caroline Bisor-Melloul;Marc Tupin;Philippe Bossis;Jacques Chene;Francois Jomard
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
53.EVALUATION OF AUSTENITIC STAINLESS STEEL DRY STORAGE CASK STRESS CORROSION CRACKING SUSCEPTIBILITY

机译：奥氏体不锈钢干贮桶应力腐蚀开裂性的评价
- 作者：Mekonen Bayssie;Darrell Dunn;Aladar Csontos;Leonardo Caseres;Todd Mintz
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
54.CORROSION RESISTANCE OF ALLOY 22 IN CHLORIDE PLUS SILICATE SOLUTIONS

机译：合金22在氯化物加硅酸盐溶液中的耐蚀性。
- 作者：Ricardo M. Carranza;Mauricio Rincon Ortiz;Martin A. Rodriguez;Raul B. Rebak
- 会议名称：《》 | 2010年
55.Corrosion of Radioactive Waste Drum Materials by Various Thiobacillus Strains

机译：各种硫杆菌菌株对放射性废料桶材料的腐蚀
- 作者：F.I.Chou;M. Y. Wang;H. P. Chung;H. W. Wen
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
56.TIMODAZ: LINING STABILITY UNDER THERMAL LOAD

机译：TIMODAZ：热负荷下的衬里稳定性
- 作者：Jaroslav Pacovsky
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
57.BUILD-UP OF DEPOSITS IN STEAM GENERATORS: A SAFETY ISSUE

机译：建立蒸汽发生器中的沉积物：一个安全问题
- 作者：M. Le Calvar;A Vergnault;H. Bodineau;F. Balestreri;T. Sollier
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
58.PROPOSED COORDINATED U.S. PWR REACTOR VESSEL SURVEILLANCE PLAN: A SUMMARY

机译：拟议的美国压水堆反应堆容器监视计划：摘要
- 作者：Ryan Hosier;J. Brian Hall;Jack Spanner;Stephen Byrne
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
59.IMPROVING REGULATORY PRACTICES THROUGH THE OECD-NEA STRESS CORROSION CRACKING AND CABLE AGEING PROJECT (SCAP)

机译：通过OECD-NEA应力腐蚀开裂和电缆老化项目（SCAP）改善法规实践
- 作者：Akihiro Yamamoto;Alejandro Huerta;Karen Gott;Bengt Lydell
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
60.REVIEW OF CORROSION EXPERIENCE WITH AGED COMPONENTS IN RUSSIAN NPPs

机译：俄罗斯核电厂老化成分的腐蚀实验研究
- 作者：G. Saji;B.T. Timofeev;V.A. Yurmanov
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
61.REACTOR PRESSURE VESSEL ISSUES FOR THE LIGHT-WATER REACTOR SUSTAINABILITY PROGRAM

机译：轻型反应堆可持续性计划的反应堆压力容器问题
- 作者：Randy K. Nanstad;G. Robert Odette
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
62.SERVICE EXPERIENCE WITH ALLOY 600 AND ASSOCIATED WELDS IN OPERATING PWRS, INCLUDING REPAIR ACTIVITIES AND REGULATORY AND CODE ACTIONS

机译：在操作PWRS时使用合金600和相关焊条的服务经验，包括维修活动以及法规和法规行动
- 作者：Warren H. Bamford;Nathan A. Palm
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
63.MODELING AND SIMULATION OF AGING EFFECTS IN IRRADIATED PWR REACTOR INTERNALS COMPONENTS

机译：辐照压水堆反应器内部组件老化效应的建模和模拟
- 作者：Glenn A. Gardner;Frank J. Marx;Joe Rashid;Anne Demma;Tamas Liszkai
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
64.INFLUENCE OF TAYLOR FACTOR ON IASCC IN SCW AND SIMULATED BWR ENVIRONMENTS

机译：Taylor因子对SCW和模拟BWR环境中IASCC的影响
- 作者：E. A. West;Z. Jiao;G. S. Was
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
65.Stress Corrosion Cracking Behavior of Cast Stainless Steels

机译：铸造不锈钢的应力腐蚀开裂行为
- 作者：Sebastien Teysseyre;Jeremy Busby;Gary S. Was
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
66.OXIDATION PERFORMANCE IN SUPERCRITICAL WATER

机译：超临界水中的氧化性能
- 作者：T.R. Allen;K. Sridharan;X. Ren;L. Tan;Y. Chen;D.C. Foley;K.T. Hartwig;X. Zhang
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
67.GENERAL CORROSION OF NEUTRON IRRADIATED CANDIDATE ALLOYS FOR FUEL CLADDINGS OF SUPERCRITICAL WATER-COOLED REACTOR

机译：超临界水冷反应器燃料熔覆中子辐照的扁桃酸酯合金的一般腐蚀
- 作者：Shigeki Kasaharal;Junya Kanedal;Yumiko Tsuchiya;Satoshi Mimura;Minoru Narui;Masanori Yamazaki;Tatsuo T. Shikama;Hideki Matsui
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
68.THE OXIDATION BEHAVIOR OF CANDIDATE MATERIALS FOR ADVANCED ENERGY SYSTEMS IN STEAM AT TEMPERATURES BETWEEN 650°C AND 800°C

机译：蒸汽在650°C至800°C的温度下高级能量系统中扁桃体材料的氧化行为
- 作者：J. M. Sarver
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
69.CORROSION OF AUSTENITIC STAINLESS STEELS IN SUPERCRITICAL AQUEOUS SOLUTIONS

机译：奥氏体不锈钢在超临界水溶液中的腐蚀
- 作者：Xueyong Guan;Digby D. Macdonald
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
70.MICROSTRUCTURE AND OXIDATION MECHANISMS OF FERR1TIC-MARTENSITIC ALLOY HCM12A IN SUPERCRITICAL WATER

机译：亚铁-马氏体合金HCM12A在超临界水中的组织和氧化机理
- 作者：P. Ampornrat;Y.B. Chen;L.M. Wang;G. S. Was
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年
71.COMPARISON OF THE OXIDE STRUCTURE FORMED ON 9CrODS STEEL AND NF616 IN SUPERCRITICAL WATER

机译：超临界水中9CrODS钢和NF616形成的氧化物结构的比较
- 作者：J. Bischoff;A.T. Motta;X. Ren;T.R. Allen
- 会议名称：《International conference on environmental degradation of materials in nuclear power systems water reactors》 | 2010年