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International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors

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1.Stress Corrosion Cracking of A286 Reactor Coolant Pump Turning Vane Bolts

机译：A286反应器冷却剂泵转动叶片螺栓应力腐蚀开裂
- 作者：Michael R. Ickes;Andrew M. Ruminski
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
2.Impact of the startup temperature and primary chemistry program on the oxidation and release of corrosion products from alloy 690 steam generator

机译：启动温度和原发性化学计划对合金690蒸汽发生器腐蚀产物的氧化和释放
- 作者：Flambard Julie;Carrette Florence;Monchy-Leroy Carole;Martin Bachet;Hadrien Perron;Andrieu Eric;Laffont Lydia
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
3.INFLUENCE OF MEAN STRESS AND PWR ENVIRONMENT ON FATIGUE BEHAVIOR OF A 304L SS

机译：平均压力和PWW环境对304LSS的疲劳行为的影响
- 作者：Ziling Peng;Gilbert Hénaff;Jean-Christophe Le Roux;Romain Verlet
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
4.MICROSTRUCTURE OF NI AND X-750 IRRADIATED AT LOW AND HIGH TEMPERATURES

机译：在低温和高温下照射Ni和X-750的微观结构
- 作者：W. Li;C. Judge;L. Walters
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
5.In-situ monitoring of the corrosion behavior and impurity enrichment of steam generator tube materials under PWR secondary side thermal hydraulic and heat transfer conditions

机译：原位监测PWR二次侧热液压和传热条件下的蒸汽发生器管材料腐蚀行为和杂质富集
- 作者：Caitlin Huotilainen;Essi J?ppinen;Tiina Ik?l?inen;Seppo Peltonen;Timo Saario;Konsta Sipil?
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
6.Corrosion Behavior of Candidate Alloys used in Supercritical Water Environment

机译：超临界水环境中候选合金的腐蚀行为
- 作者：Hsuan-Kan Lin;Tsung-Kuang Yeh;Mei-Ya Wang
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
7.INVESTIGATING THE ROLE OF HYDROGEN ON STRESS CORROSION CRACKING BY MICROMECHNAICAL TESTING

机译：调查氢对微孔试验应力腐蚀开裂的作用
- 作者：Edward Roberts;Edmund Tarleton;Florence Carrette;Sergio Lozano-Perez
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
8.ASSESSMENT OF DEFORMATION MECHANISMS IN NEUTRON-IRRADIATED ACCIDENT-TOLERANT FeCrAl ALLOYS VIA IN SITU MECHANICAL TESTING AND TEM ANALYSIS

机译：通过原位机械测试和TEM分析评估中子辐射的事故贫化群合金的变形机制
- 作者：M. N. Gussev;D. Zhang;K. G. Field
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
9.NEXT GENERATION OF NOBLE METAL APPLICATION FOR BOILING WATER REACTORS

机译：沸水反应器的下一代贵金属应用
- 作者：Joe Giannelli;Erica Libra-Sharkey;Collin Custer;George Inch;Andrew Odell;Michelle Mura;Mike Ford
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
10.The Stress Intensity Factor Dependence of 304 Stainless Steel SCC growth in Deaerated Water

机译：脱液水中304不锈钢SCC生长的应力强度因子依赖性
- 作者：David Morton
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
11.Characterizing Fatigue Damage in Zr-2.5Nb

机译：在Zr-2.5nb中表征疲劳损伤
- 作者：H.M. Nordin;M. Mattucci;A. Phillion;T.M. Karlsen
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
12.EMPIRICAL EQUATIONS OF CRACK GROWTH RATES BASED ON DATA FITTING OF NEUTRON IRRADIATED STAINLESS STEEL UNDER HIGH TEMPERATURE WATER SIMULATING BOILING WATER REACTOR CORE CONDITIONS

机译：高温水模拟沸水反应器核心条件下基于中子辐照不锈钢数据配件的裂纹增长率的经验方程
- 作者：Shigeki Kasahara;Yasuhiro Chimi;Kuniki Hata;Koji Fukuya;Katsuhiko Fujii
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
13.EFFECT OF AERATED TRANSIENTS ON OXIDATION AND SCC OF STAINLESS STEELS IN PWR PRIMARY WATER

机译：曝气瞬变对PWR初级水中不锈钢氧化和SCC的影响
- 作者：Marc MAISONNEUVE;Cécilie DUHAMEL;Catherine GUERRE;Jér?me CREPIN;Ian DE CURIERES
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
14.Irradiation damage and IASCC of printed 316L for use as fuel cladding

机译：印刷316L的辐照损伤和IASCC用作燃料包层
- 作者：M. McMurtrey;R. O’Brien;C. Sun;C. Shiau;F. Teng
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
15.UNDERSTANDING THE ROLE OF GRAIN BOUNDARY MIGRATION ON THE INITIATION STAGES OF PWSCC

机译：了解谷物边界迁移对PWSCC发起阶段的作用
- 作者：L. Volpe;M.G. Burke;F. Scenini
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
16.EFFECT OF STRAIN AND STRAIN RATE ON CRACK INITIATION OF 316L STEEL IN THE SIMULATED PWR WATER

机译：应变和应变率对模拟PWR水中316L钢裂纹启动的影响
- 作者：Anna Hojná;Mariia Zimina;Luká? Horák
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
17.USE OF ON-LINE MONITORING TECHNIQUES FOR EVALUATIONS OF LEAD STRESS CORROSION CRACKING (PBSCC) AND A PBSCC INHIBITOR

机译：使用在线监测技术进行铅应力腐蚀裂解（PBSCC）和PBSCC抑制剂的评估
- 作者：Brent Capell;Jared Smith
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
18.DEVELOPMENT AND VALIDATION OF A NEW EXPERIMENTAL DEVICE FOR STUDIES OF IODINE STRESS CORROSION CRACKING OF ZIRCONIUM ALLOYS

机译：锆合金碘胁迫腐蚀裂纹研究新实验装置的开发与验证
- 作者：Kamila WILCZYNSKA;Matthew BONO;David LE BOULCH;Marion FREGONESE;Valérie CHABRETOU;Nathanael MOZZANI;Laureline BARBIE
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
19.RADIATION-INDUCED FERRITE FORMATION AS A POTENTIAL ISSUE IN PWR AUSTENITIC INTERNALS FOLLOWING PLANT LIFE EXTENSION

机译：辐射诱导的铁氧体形成作为植物寿命延伸后PWR奥氏体内部的潜在问题
- 作者：D. A. Merezhko;M. S. Merezhko;O. P. Maksimkin;M. N. Gussev;F. A. Garner
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
20.TRIBOCORROSION PHENOMENA IN CO- AND FE-BASED HARDFACING ALLOYS EVALUATED USING PIN-IN-ON-DISC WEAR TESTS IN A SIMULATED PWR ENVIRONMENT

机译：在模拟PWW环境中使用引脚盘式磨损试验评估了二氧化碳的硬裂合金中的Tribocolion现象
- 作者：V L Ratia;M J Carrington;D Zhang;J L Daure;D G McCartney;P H Shipway;D A Stewart
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
21.Combined approach to Medium Voltage Cable and Accessories Aging Management Technique at Nuclear Power Plants

机译：中电缆和配件核电站造工衰老管理技术的组合方法
- 作者：Raihan Khondker;Sarajit Banerjee;David Rouison;Rick Easterling
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
22.An Investigation into the Corrosion Behaviors of Stainless Steel and Ni-based Alloy in Simulated PWR Primary Water Environments

机译：模拟PWR初级水环境中不锈钢和Ni基合金腐蚀行为的研究
- 作者：Che Jung Chang;Mei Ya Wang;Tsung Kuang Yeh
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
23.Effect of Residual δ-Ferrite on SCC Behavior of 321 Stainless Steel

机译：残余δ-铁氧体对321不锈钢SCC行为的影响
- 作者：Jiamei Wang;Kai Chen;Haozhan Su;Donghai Du;Xianglong Guo;Lefu Zhang;Zhao Shen
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
24.INTERFACE CHARACTERIZATION OF CANDIDATE DUAL-PURPOSE BARRIER COATINGS FOR SIC/SIC ACCIDENT TOLERANT FUEL CLADDING

机译：SiC / SIC事故耐燃料包层的候选二元屏障涂层的界面表征
- 作者：Joey Kabel;Takaaki Koyanagi;Yutai Katoh;Ryan Schoell;Djamel Kaoumi;Caen Ang;Peter Hosemanna
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
25.SPECIMEN SIZE EFFECTS ON THE CRACK GROWTH RATE RESPONSE OF HIGHLY IRRADIATED TYPE 304 STAINLESS STEEL

机译：试样尺寸对高度照射型304不锈钢的裂纹增长率响应的影响
- 作者：A. Jenssen;J. Stj?rns?ter;C. Topbasi;P. Chou
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
26.UNDERSTANDING THE EFFECT OF STRAIN LOCALIZATION ON CORROSION FATIGUE OF TYPE 304 AUSTENITIC STAINLESS STEELS IN HIGH TEMPERATURE WATER

机译：了解应变定位对高温水304型奥氏体不锈钢腐蚀疲劳的影响
- 作者：Hanxiao Wang;Fabio Scenini;Jo?o Quinta da Fonseca;M. Grace Burke;Jill Meadows;Norman Platts;David Tice
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
27.THE MECHANISTIC UNDERSTANDING ON THE STRESS CORROSION CRACKING GROWTH RATE IN SIMULATED PWR PRIMARY WATER FOR COLD WORKED TT ALLOY 690

机译：机械理解对冷轧TT合金模拟PWWR初级水中的应力腐蚀裂解速率690
- 作者：Toshio Yonezawa;Masashi Watanabe;Atsushi Hashimoto
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
28.Comparison of selective oxidation in Ni-based alloys exposed to PWR primary water and Rhines Pack environments

机译：暴露于PWR初级水和莱茵包装环境的Ni基合金中选择性氧化的比较
- 作者：Karen Kruska;Daniel K Schreiber;Matthew J Olszta;Brian J Riley;Stephen M Bruemmer
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
29.INVESTIGATING Pb-INDUCED STRESS CORROSION CRACKING OF ALLOY 800 VIA IN-SITU XPS

机译：通过原位XPS研究了合金800的PB诱导的应力腐蚀开裂
- 作者：B. Payne;S.Y. Persaud;J.M. Smith
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
30.USING A MULTI-SCALE APPROACH TO ASSESS THE MECHANICAL PROPERTIES AND DEFORMATION MECHANISMS OF HIGH DOSE INCONEL X-750

机译：使用多尺度方法来评估高剂量Inconel X-750的机械性能和变形机制
- 作者：C. Howard;C.D. Judge;V. Bhakhri;Q. Wang;M.R. Daymond;D. Murray;F. Teng;T. Skippon;M. Mattucci;H. Rajakumar;C. Mayhew;C. Dixon;D. Poff;G.A. Bickel
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
31.MORPHOLOGY OF CAVITIES FORMED ON GRAIN BOUNDARY OF CRACKED ALLOY TT690

机译：裂纹合金TT690晶界形成的腔形态学
- 作者：Takumi Terachi;Makie Okamoto;Takuyo Yamada;Koji Arioka
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
32.IRRADIATION-ASSISTED STRESS CORROSION CRACKING OF TI-STABILIZED AUSTENITIC STAINLESS STEEL

机译：Ti稳定的奥氏体不锈钢辐照辅助应力腐蚀裂纹
- 作者：Miroslava Ernestova
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
33.MITIGATION OF PRIMARY WATER STRESS CORROSION CRACKING INITIATION OF ALLOY 600

机译：初级水应激腐蚀裂解结合合金600的减缓
- 作者：Sonya Pemberton;Jack Beswick;Mark Chatterton;Jill Meadows;Stuart Medway
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
34.Nuclear concrete microstructure generation for simulating creep

机译：模拟蠕变的核混凝土微观结构
- 作者：Christa E. Torrence;Aishwarya Baranikumar;Zachary Grasley
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
35.3D CREEP RESPONSE OF NUCLEAR CONCRETE

机译：3D核混凝土蠕变反应
- 作者：Aishwarya Baranikumar;Christa E. Torrence;Zachary Grasley
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
36.3D Characterization of Corrosion Fatigue Cracks and Crack Tips Generated in Type 304/304L Stainless Steel during Enhanced and Retarded Fatigue Crack Growth

机译：3D表征在增强和延迟疲劳裂纹裂纹增长期间304 / 304L不锈钢中产生的腐蚀疲劳裂缝和裂纹提示
- 作者：B.S. Anglin;B.D. Miller;K.B. Fisher;T.W. Webb
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
37.Non-Destructively Detecting LWR Structural Material Embrittlement using Transient Grating Spectroscopy

机译：使用瞬态光栅光谱法未破坏性检测LWR结构材料脆化
- 作者：Saleem A. Al Dajani;Benjamin R. Dacus;Cody A. Dennett;M. Grace Burke;Kudzanai Mukahiwa;Kuba Anglin;James J. Wall;Thak Sang Byun;Michael P. Short
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
38.INTER-DIGITAL CAPACITIVE SENSOR FOR EVALUATING CABLE INSULATION THROUGH JACKET

机译：用于通过夹克进行评估电缆绝缘的数字电容传感器
- 作者：S. W. Glass;L. S. Fifield;A. Sriraman;N. Bowler
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
39.Microstructural Characterization of Proton Irradiated 304L SS at 100°C and 360°C

机译：质子辐照304LS在100℃和360°C下的微观结构表征
- 作者：C.D. Judge;B. Langelier;M.A. Mattucci;Q. Wang;M. Daymond;G.S. Was;J. Smith
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
40.EFFECTS OF DRY, WET-DRY CYCLING AND AQUEOUS IMMERSION ON POLYPROPYLENE AND POLYETHYLENE CABLE INSULATION MECHANICAL PROPERTIES

机译：干燥，干燥循环和水性浸渍对聚丙烯和聚乙烯电缆绝缘机械性能的影响
- 作者：Isaiah Salinas;Adam Finke;Brian Hinderliter;Keith B. Lodge;Melissa A. Maurer-Jones;Robert Duckworth
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
41.FORMULATION OF THE IRRADIATION ASSISTED STRESS CORROSION CRACK GROWTH RATES FOR NEUTRON-IRRADIATED STAINLESS STEELS IN HIGH-TEMPERATURE WATER OF A BOILING WATER REACTOR

机译：在沸水反应器的高温水中制定中子照射不锈钢的辐照辅助应力腐蚀裂纹速率
- 作者：Masato Koshiishi;Kazuhiro Chatani;Shigeaki Tanaka;Hiroyuki Nakano;Takayuki Kaminaga
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
42.HIGH TEMPERATURE CYCLIC DEFORMATION BEHAVIOR OF AN ADVANCED AUSTENITIC STAINLESS STEEL (ALLOY 709)

机译：先进奥氏体不锈钢的高温环状变形行为（合金709）
- 作者：Zeinab Y. Alsmadi;Abdullah S. Alomari;N. Kumar;K.L. Murty
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
43.SCC Behavior at Alloy 52M-182 Weld Overlay Interfaces in a PWR Environment

机译：合金的SCC行为52M-182 PWR环境中的焊接覆盖界面
- 作者：Bogdan Alexandreanu;Yiren Chen
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
44.CHARACTERIZING AND QUANTIFYING THE AGING OF POLYETHYLENE THIN FILMS USING NOVEL DOPED-FILMS AND GOLD NANOPARTICLE LABELING STRATEGIES TOWARD UNDERSTANDING FAILURE OF CABLING INSULATION

机译：用新型掺杂膜和金纳米粒子标记策略对布线绝缘失效的表征和量化聚乙烯薄膜老化
- 作者：Daniel Zoltek;Tana O’Keefe;Faith Murphy;Magdalene B. Jones;Robert C. Duckworth;Brian Hinderliter;Melissa A. Maurer-Jones
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
45.DIFFUSING HYDROGEN EFFECT ON THE OXIDE FILM ON 316L SS IN HIGH TEMPERATURE WATER

机译：在高温水中延伸对氧化物膜上的氧化膜
- 作者：Jiarong Ma;Tongming Cui;Hao Peng;Zhanpeng Lu;Junjie Chen;Yibo Jiap
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
46.REVEALING HOW ALKALI CATIONS AFFECT THE ELECTRICAL DOUBLE LAYER STRUCTURE OF STAINLESS STEEL IN ALKALINE AQUEOUS ENVIRONMENTS

机译：揭示碱阳离子如何影响碱性环境中不锈钢的电双层结构
- 作者：Rachel Guia P. Giron;Xin Chen;Erika Callagon La Plante;Maxim N. Gussev;Keith J. Leonard;Gaurav N.Sant
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
47.Effect of thermal aging on microstructure and hardness of industrial heats of Alloy 690

机译：热老化对合金工业热组织和硬度的影响690
- 作者：Caitlin Huotilainen;Ulla Ehrnstén;Matias Ahonen;Hannu H?nninen
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
48.COUPLING EFFECT OF CHARGED-HYDROGEN AND COLD WORK ON OXIDATION BEHAVIOR OF 316L STAINLESS STEEL IN DEAERATED HIGH TEMPERATURE WATER

机译：带电荷 - 氢气和冷工程对316L不锈钢在脱气高温水中氧化行为的耦合作用
- 作者：Tongming Cui;Jiarong Ma;Fei Ning;Zhanpeng Lu;Kun Zhang;Yibo Jia;Tetsuo Shoji
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
49.INSIGHTS INTO PROSPECTIVE FUSION REACTOR COOLING SYSTEMS FROM FISSION REACTOR COOLING CIRCUITS

机译：从裂变反应器冷却电路中洞察预期融合反应器冷却系统
- 作者：T.L. Martin;A.D. Warren;D. Kumar;A. Siberry;R. Springell;R. Holmes;R. Clark;L. Platts;R. Burrows;C. Harrington;M. Gorley;E. Surrey;S. Rowthu;P. Grundler;S. Ritter
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
50.EVALUATION OF THE CORROSION KINETICS OF SIC WITH AND WITHOUT MITIGATION COATINGS IN LWR CHEMISTRIES

机译：LWR化学中具有缓解涂层的SIC腐蚀动力学的评价
- 作者：Peter Doyle;Stephen Raiman;Caen Ang;Yutai Katoh;Steven Zinkle
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
51.MICROSTRUCTURAL CHARACTERIZATION OF ALLOY 690TT EXPOSED TO Pb- CONTAINING CAUSTIC SOLUTIONS

机译：含Pb-含苛性碱溶液暴露于PB的合金690TT的微观组织特征
- 作者：G. B. Mazzei;J. Duff;M. G. Burke;F. Scenini;G Meredith;T. Horner
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
52.MICROSTRUCTURAL CHARACTERIZATION OF STEAM GENERATOR TUBE FLAKES FROM AN OPERATING PWR AND ITS GALVANIC CORROSION BEHAVIOR

机译：操作PWR与其电致腐蚀行为的蒸汽发生器管剥落的微观结构
- 作者：Soon-Hyeok Jeon;Geun Dong Song;Do Haeng Hur
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
53.Development of a gaseous iodine testing system to determine the I-SCC properties of zirconium alloys

机译：发育气态碘试验系统以确定锆合金的I-SCC性能
- 作者：Sean M. Hanlon;Andrew Phillion;Conor Gillen;Mark R. Daymond
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
54.REVIEW OF RADIATION INDUCED DEGRADATION OF CONCRETE STRUCTURE IN COMMERCIAL NUCLEAR POWER PLANTS AROUND REACTOR VESSEL

机译：辐射辐射诱导反应堆船舶商用核电站混凝土结构降解
- 作者：Bruce Biwer;David Ma;Yunping Xi;Yuxiang Jing;Madhumita Sircar;Jinsuo Nie
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
55.POST-IRRADIATION EXAMINATION OF HIGH FLUENCE BAFFLE-FORMER BOLTS RETRIEVED FROM A WESTINGHOUSE TWO-LOOP DOWNFLOW TYPE PWR

机译：从西部房屋双环下流型PWR检索的高分机械挡板后螺栓的照射后检查
- 作者：Xiang Chen;Tianyi Chen;Chad M. Parish;Mikhail A. Sokolov;Keith J. Leonard
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
56.CABLE AGING AND CM APPROACHES BEYOND THE SHORTCOMINGS OF IAEA NUCLEAR ENERGY SERIES NO. NP-T-3.6

机译：电缆老化和超越国际原子能机构核能系列缺点的方法近似。 NP-T-3.6
- 作者：Kenneth T. Gillen
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
57.WEIBULL AND BOOTSTRAP BASED PROBABILISTIC FATIGUE LIFE MODELING OF STAINLESS STEEL UNDER PWR COOLANT WATER ENVIRONMENT CONDITION

机译：PWR冷却剂水环境条件下不锈钢的威布尔和自举概率疲劳寿命建模
- 作者：Jae Phil Park;Subhasish Mohanty;Chi Bum Bahn
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
58.EFFECT OF WELDING DILUTION AND DENDRITE ORIENTATION ON SCC BEHAVIOR OF ALLOY 52M WELDING METAL IN SIMULATED PWR PRIMARY WATER

机译：焊接稀释与枝晶取向对模拟PWW初级水中合金52M焊金属SCC行为的影响
- 作者：Jiarong Ma;Kun Zhang;Tongming Cui;Zhanpeng Lu;Xue Liang;Wenqing Liu;Zhimin Zhong;Guangdong Han
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
59.EFFECT OF FOLLOW-UP POST WELD HEAT TREATMENT ON MICROSTRUCTURE AND PWSCC OF ALLOY 52M WELD METAL IN DISSIMILAR METAL WELD JOINT

机译：随后焊接热处理对不同金属焊接接头中的合金52M焊缝金属微结构和PWSCC的影响
- 作者：Jiarong Ma;Kun Zhang;Tongming Cui;Qi Xiong;Zhanpeng Lu;Junjie Chen;Chengdong Yang;Maolong Zhang;Weibao Tang
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
60.Stress assessment of baffle former bolt of PWR reactor for IASCC

机译：对IASCC的PWR反应器挡板前螺栓的应力评估
- 作者：A.M. Pandit;F.J. Blom;P.J. Baas
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
61.ELECTRICAL BREAKDOWN STRENGTH AND AC WITHSTAND IN HARVESTED EPR INSULATIONS FOR NUCLEAR POWER PLANTS

机译：核电站收获EPR绝缘的电击穿强度和AC耐用
- 作者：Robert Duckworth;Alvin Ellis;Tam Ha
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
62.'Mind the Gap' between old and new nuclear qualified cable: Lessons learned from aging, historical adverse events and other nuclear cable issues

机译：“思想旧的核限定电缆之间的差距：从老龄化，历史不良事件和其他核电有关的经验教训
- 作者：Larry Cunningham
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
63.EFFECT OF LOCAL STRAIN AND GND DENSITY ON CRACK INITIATION IN ALLOY 600

机译：局部应变和GND密度对合金600裂纹起始的影响
- 作者：Naganand Saravanan;Phani S Karamched;Morgane Le Faucheur;Emilien Burger;Fabio Scenini;Sergio Lozano-Perez
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
64.Effect of UV irradiation on Corrosion Behavior of Zirconium Alloy in High Temperature Water Conditions

机译：紫外线辐射对高温水条件下锆合金腐蚀行为的影响
- 作者：Taeho Kim;Yalong He;Zefeng Yu;Mohamed Elbakshwan;Li He;Adrien Couet
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
65.OXIDATION CHARACTERISTICS OF Ni-Cr-Fe ALLOY SYSTEMS IN SIMULATED PWR PRIMARY WATER: EFFECT OF Cr CONTENT

机译：模拟PWR初级水中Ni-Cr-Fe合金系统的氧化特性：Cr含量的影响
- 作者：Hee-Sang Shim;Do Haeng Hur
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
66.CORROSION ISSUES IN FUTURE YEARS: A TSO PERSPECTIVE

机译：未来几年的腐蚀问题：TSO透视
- 作者：Ian de CURIERES
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
67.SCC INITIATION AND GROWTH IN PWR PRIMARY WATER CONTAINING KOH VS. LIOH

机译：SCC含有KOH与koh初级水的启动和生长。 lioh.
- 作者：Peter Andresen;Peter Chou
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
68.IASCC SUSCEPTIBILITY OF HIGHLY IRRADIATED 316 STAINLESS STEEL IN SIMULATED PWR PRIMARY WATER

机译：IASCC在模拟PWR初级水中高度辐照的316不锈钢的易感性
- 作者：Donghai Du;Gary S. Was
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
69.Effects of gamma ray irradiation on corrosion of carbon steel at water line

机译：γ射线辐射对水线碳钢腐蚀的影响
- 作者：Tomomichi Ariga;Hiroshi Abe;Yutaka Watanabe
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
70.Influence of Long-Term Thermal Aging on SCC Initiation Susceptibility of L-grade Austenitic Stainless Steel

机译：长期热老化对L级奥氏体不锈钢SCC引发易感性的影响
- 作者：K. Kondo;S. Aoki;Y. Fujimura;T. Hirade;Y. Kaji;S. Yamashita
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
71.THE EFFECT OF IRRADIATION-INDUCED MATRIX BARRIER HARDENING ON IRRADIATION-ASSISTED STRESS CORROSION CRACKING (IASCC) IN AUSTENITIC STEELS AND NICKEL BASED ALLOYS

机译：辐照诱导的基质屏障硬化对奥氏体钢和镍基合金辐照辅助应力腐蚀裂纹（IASCC）的影响
- 作者：R.G. Faulkner
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
72.EFFECT OF MARTENSITE ON SCC INITIATION IN AUSTENTITC STAINLESS STEELS IN SIMULATED PWR PRIMARY WATER ENVIRONMENT

机译：马氏体对模拟PWL初级水环境中Austentitc不锈钢SCC发育的影响
- 作者：Litao Chang;M. Grace Burke;Jonathan Duff;Fabio Scenini
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
73.STRESS CORROSION CRACKING OF STAINLESS STEEL CLADDING LAYERS IN SIMULATED PWR PRIMARY WATER

机译：模拟PWR初级水中不锈钢覆层层的应力腐蚀开裂
- 作者：Qi Xiong;Tongming Cui;Jiarong Ma;Zhanpeng Lu;Fei Ning;Junjie Chen;Kun Zhang;Zhiming Zhong;Guangdong Han
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
74.CHRACTERISTICS OF WORK HARDENED SURFACE LAYER ON AUSTENITIC STAINLESS STEELS AND ITS RELATION TO SCC SUSCEPTIBILITY IN HIGH TEMPERATURE WATER

机译：奥氏体不锈钢工作层表面层的特性及其与高温水中SCC易感性的关系
- 作者：Hiroshi Abe;Yutaka Watanabe;Takamichi Miyazaki
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
75.CHARACTERIZATION OF MICROSTRUCTURE OF ALLOY 52M WELD METAL NEAR THE FUSION BOUNDARY AND OXIDE FILMS FORMED IN SIMULATED PWR PRIMARY WATER

机译：模拟PWR初级水中形成融合边界和氧化膜附近合金52M焊接金属微观结构的表征
- 作者：Kun Zhang;Jiarong Ma;Tonging Cui;Zhanpeng Lu;Fei Ning;Yibo Jia;Xue Liang
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
76.FRACTURE BEHAVIOR OF OXIDIZED GRAIN BOUNDARY IN NEUTRON-IRRADIATED STAINLESS STEEL

机译：中子照射不锈钢氧化晶界的断裂行为
- 作者：Terumitsu Miura;Katsuhiko Fujii;Koji Fukuya;Yuji Kitsunai
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
77.Effect of Cold Work on Hydrogen Diffusion in Zr-2.5Nb Alloys at Reactor Temperatures

机译：冷工变对反应器温度Zr-2.5％Nb合金中氢气扩散的影响
- 作者：Heidi Nordin;Jaganathan Ulaganathan;Sean Hanlon;Dylan Broad
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
78.THE DETERMINATION OF THE REACTION RATES, WATER VAPOR PERMEABILITY, AND ACTIVATION ENERGY FOR THERMAL OXIDATION OF LDPE FILMS

机译：用于热氧化LDPE薄膜的反应速率，水蒸气渗透性和活化能的测定
- 作者：Noumon Munir;Keith B. Lodge;Brian Hinderliter;Melissa A. Maurer-Jones;Robert Duckworth
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
79.Oxide Dispersion Type 304L Stainless Steel by Additive Manufacturing Process

机译：通过添加制造工艺氧化物分散体304L不锈钢
- 作者：Takahiro Ishizaki;Kinya Aota;Yingjuan Yang;Yusaku Maruno;Atuhiko Onuma
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
80.UNDERSTANDING THE EVOLUTION OF DEFORMATION STRUCTURES AT FATIGUE CRACK TIPS AND IMPLICATIONS FOR ENVIRONMENTALLY ENHANCED AND RETARDED FATIGUE CRACK GROWTH

机译：了解疲劳裂纹尖端变形结构的演变及对环境增强和延迟疲劳裂纹生长的影响
- 作者：B. D. Miller;D. J. Paraventi;B. S. Anglin;T. W. Webb
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
81.SIMULATING THE SUSCEPTIBILITY TO IGSCC OF COLD WORK 316 AUSTENITIC STAINLESS STEEL EXPOSED TO PRIMARY WATER

机译：模拟冷轧机216奥氏体不锈钢的IGSCC易感性暴露于初级水
- 作者：Thierry COUVANT;Emilien BURGER;Claire THAURY;Claire RAINASSE
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
82.IRRADIATION ASSISTED STRESS CORROSION CRACKING (IASCC) OF LOW STRENGTH AND HIGH STRENGTH ALLOYS IN LIGHTWATER REACTOR ENVIRONMENTS

机译：闪水反应器环境中低强度和高强度合金的辐照辅助应力腐蚀裂纹（IASCC）
- 作者：M. Wang;M. Song;L. Nelson;R. Pathania;G. S. Was
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
83.Understanding the mechanisms of surface and crack tip oxidation with valence mapping

机译：了解与价映射的表面和裂纹尖端氧化机制
- 作者：Sergio Lozano-Perez;Zhao Shen;Donghai Du;Lefu Zhang
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
84.DEVELOPMENT OF RESIDUAL STRESS DRIVEN STRESS CORROSION CRACK INITIATION AND GROWTH SPECIMENS

机译：剩余应力驱动应力腐蚀裂纹引发和生长标本的发展
- 作者：Tyler Moss;John Brockenbrough
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
85.Development of Mo-free Low Alloy Steels for Mitigation of Flow-Accelerated Corrosion in Secondary Side of PWRs

机译：无阀低合金钢的开发，用于减轻PWR次级侧的流动加速腐蚀
- 作者：Seunghyun Kim;Gi Dong Kim;Ji Hyun Kim
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
86.NANO-MECHANICAL TESTING OF PROTON IRRADIATED 304L SS AT 100°C AND 360°C TO SUPPORT IASCC

机译：质子辐照304LS在100℃和360℃下的纳米机械测试以支持IASCC
- 作者：M.A. Mattucci;Q. Wang;T. Skippon;M.R. Daymond;G.S. Was;J. Smith;C.D. Judge
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
87.ENVIRONMENTAL DEGRADATION RESISTANCE OF ATF FeCrAl CLADDING TUBE SPECIMENS DURING THE FUEL CYCLE

机译：燃料循环期间ATF Fecral包层标本的环境降解抗性
- 作者：Michael Schuster;Evan J. Dolley;Timothy B. Jurewicz;Raul B. Rebak
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
88.CHARACTERIZATION OF IN-SERVICE THERMAL AGING EFFECTS IN BASE METALS AND WELDS OF THE PRESSURE VESSEL OF A DECOMMISSIONED PWR PRESSURIZER, AFTER 27 YEARS OF OPERATION

机译：在27年的操作后，在退役的PWW加压器压力容器的基础金属和焊缝中表征在贱金属和焊缝中
- 作者：Pierre JOLY;Lingtao SUN;P?l EFSING;Jean PaulMASSOUD;Frédéric SOMVILLE;Robert GERARD;Ying Hui AN;Jonathan BAILEY
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
89.Tests on Mock-ups Representative of Rolling Zones of Steam Generator tubes in High Temperature Hydrogenated Water

机译：高温氢化水中蒸汽发生器管滚动区代表的模拟试验
- 作者：Daniel Brimbal;Steve Fyfitch;Olivier Calonne;Nicolas Huin
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
90.STRESS CORROSION CRACK INITIATION OF COLD-WORKED ALLOY 800 IN Pb-CONTAINING, ALKALINE ENVIRONMENTS

机译：含PB碱性环境中冷加工合金800的应力腐蚀裂纹启动
- 作者：Jaganathan Ulaganathan;Jared Smith
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
91.On the Potential Synergies of Helium and Hydrogen on the Nucleation and Stability of Cavity Clusters in Inconel X-750? Irradiated in a High Thermal Neutron Flux Spectra

机译：关于氦气纤维核和氢气的潜在协同作用X-750中腔簇的成核和稳定性？在高热中子通量光谱中辐照
- 作者：C.D. Judge;H. Rajakumar;A. Korinek;G.A. Bickel
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
92.MODELING THE EVOLUTION OF INTERGRANULAR HELIUM BUBBLES IN NICKEL USING THE INCLUDED PHASE MODEL

机译：用函数模型建模镍中晶间氦气泡沫的演变
- 作者：Andrew A. Prudil;Michael J. Welland;Colin D. Judge
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
93.IRRADIATION-INDUCED CRACKING OF DUAL-PURPOSE COATINGS ON SiC

机译：辐照诱导的SiC双用涂料破裂
- 作者：Stephen S. Raiman;Peter J. Doyle;Caen Ang;Takaaki Koyanagi;David Carpenter;Kurt A. Terrani;Yutai Katoh
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
94.ASSESSMENT OF THE SCC MITIGATION CAPABILITIES OF THE NOBLE METAL CHEMICAL APPLICATION TECHNOLOGY IN A SIMULATED BWR ENVIRONMENT

机译：评估贵金属化学应用技术在模拟BWR环境中的SCC缓解能力
- 作者：Pascal V. Grundler;Stefan Ritter;Sriharitha Rowthu;Hans-Peter Seifert
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
95.SPATIAL RESOLUTION OF A CABLE FAULT LOCATION ATTEMPT BY FREQUENCY DOMAIN REFLECTOMETRY

机译：电缆故障定位的空间分辨率通过频域反射测量仪尝试
- 作者：Yoshimichi Ohki;Naoshi Hirai
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
96.STEAM OXIDATION, BURST AND CRITICAL HEAT FLUX TESTING OF COMMERCIAL FECRAL CLADDING

机译：商业群体包层的蒸汽氧化，突发和临界热通量测试
- 作者：B. A. Pint;L. A. Baldesberger;K. A. Kane
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
97.INFLUENCE OF THE COMBINATION OF MICROSTRUCTURE AND MECHANICAL FIELDS ON STRESS CORROSION CRACKING INITIATION OF COLD-WORKED AUSTENITIC STAINLESS STEELS

机译：微观结构和机械领域的影响对冷工奥氏体不锈钢应力腐蚀开裂起始的影响
- 作者：Qi Huang;Yann Charles;Cécilie Duhamel;Monique Gaspérini;Jér?me Crépin
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
98.Parameter Sensitivity of Interdigital Sensors for their Design for Cable Insulation Aging Detection

机译：用于其电缆绝缘老化检测设计的叉指式传感器的参数灵敏度
- 作者：Md. Nazmul Al-Imran;S.W. Glass;Leonard S. Fifield;Mohammod Ali
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
99.LOW TEMPERATURE CRACK PROPAGATION MECHANISM OF ALLOY 182 WELD

机译：合金182焊缝的低温裂纹传播机理
- 作者：Young Suk Kim;Sung Soo Kim
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年
100.EFFECT OF SPECIMEN SIZE AND PERCENT ENGAGEMENT ON SCC BEHAVIOR OF ALLOY 82 IN BWR ENVIRONMENTS

机译：标本尺寸和百分比接合对BWR环境合金82的SCC行为的影响
- 作者：Katsuhiko Kumagai;Hiroyuki Nakano;Takayuki Kaminaga
- 会议名称：《International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors》 | 2019年