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International symposium on zirconium in the nuclear industry

召开年：2013
召开地：Hyderabad(IN)
出版时间：-

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1.Reflections on the Development of the 'f' Texture Factors for Zirconium Components and the Establishment of Properties of the Zirconium-Hydrogen System

机译：关于锆组分“ f”质构因子发展及锆氢体系性质建立的思考
- 作者：J. J. Kearns
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- zirconium;
- texture;
- anisotropy;
- hydrogen;
- embrittlement;
- solubility;
- diffusion coefficients;
- thermal-diffusion;
2.Displacive and Diffusional Transformations of the Beta Phase in Zirconium Alloys

机译：锆合金中β相的位移和扩散转变
- 作者：S. Banerjee
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- Zirconium;
- martensite;
- phase transformation;
3.Effect of Hydrogen on Dimensional Changes of Zirconium and the Influence of Alloying Elements: First-Principles and Classical Simulations of Point Defects, Dislocation Loops, and Hydrides

机译：氢对锆尺寸变化和合金元素的影响：点缺陷，位错环和氢化物的第一性原理和经典模拟
- 作者：M. Christensen;W. Wolf;C. Freeman;E. Wimmer;R. B. Adamson;L. Hallstadius;P. Cantonwine;E. V. Mader
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- Zircaloy;
- computer modeling;
- zirconium;
- hydrogen effects;
- zirconium hydrides;
- solubility;
- defects;
- diffusion;
- dislocation loops;
- atomistic simulation;
4.Phase Field Modeling of Microstructure Evolution in Zirconium Base Alloys

机译：锆基合金组织演变的相场建模
- 作者：Gargi Choudhuri;Sibasis Chakraborty;B. K. Shah;D. Srivastava;G. K. Dey
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- phase field method;
- lath;
- interface;
- supersaturation;
- allotriomorph;
- Zirconium;
5.Thermodynamics of Zr Alloys: Application to Heterogeneous Materials

机译：Zr合金的热力学：在非均质材料中的应用
- 作者：P. Barberis;C. Vauglin;P. Fremiot;P. Guerin
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- thermodynamics;
- chemical potential;
- hydrogen;
- iron;
- weld;
- liner;
- Laves phase;
- miscibility gap;
- up-hill diffusion;
6.Influence of Sn on Deformation Mechanisms During Room Temperature Compression of Binary Zr-Sn Alloys

机译：Sn对二元Zr-Sn合金室温压缩过程中形变机理的影响
- 作者：K. V. Mani Krishna;D. G. Leo Prakash;D. Srivastava;N. Saibaba;J. Quinta da Fonseca;G. K. Dey;M. Preuss
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- Zr-Sn alloys;
- deformation mechanisms;
- intergranular strains;
- twinning;
- in situ compression;
- neutron diffraction;
7.Impact of Iron in M5TM6

机译：铁对M5TM6的影响
- 作者：D. Kaczorowski;J. P. Mardon;P. Barberis;P. B. Hoffmann;J. Stevens
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- alloy composition;
- corrosion;
- dimensional properties;
- second-phase precipitates;
- iron;
- M5™;
- creep;
- mechanical properties;
- cladding;
8.Microstructure and Properties of a Three-Layer Nuclear Fuel Cladding Prototype Containing Erbium as a Neutronic Burnable Poison

机译：含b作为中子可燃性毒物的三层核燃料熔覆原型的微观结构和性能
- 作者：J. C. Brachet;P. Olier;V. Vandenberghe;S. Doriot;S. Urvoy;D. Hamon;T. Guilbert;A. Mascaro;J. Jourdan;C. Toffolon-Masclet;M. Tupin;B. Bourdiliau;C. Raepsaet;J. M. Joubert;J. L. Aubin
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- erbium;
- neutronic burnable poison;
- zirconium-erbium-hydrogen-oxygen phase diagrams;
- CALPHAD;
- Thermocalc;
- Zircobase;
- hydrogen trapping;
- three-layer-clad;
- μ-ERDA;
9.Characterizing Quenched Microstructures in Relation to Processing

机译：表征与加工有关的淬火微结构
- 作者：P. Barberis;M. T. Tran;F. Montheillet;D. Piot;A. Gaillac
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- quenching;
- variant selection;
- image analysis;
- modeling;
- EBSD;
- cooling rate;
- microstructure;
- platelets;
- basketweave;
10.Identification of Safe Hot-Working Conditions in Cast Zr-2.5Nb

机译：Zr-2.5Nb铸件安全热加工条件的确定
- 作者：J. K. Chakravartty;R. Kapoor;A. Sarkar;V. Kumar;S. K. Jha;N. Saibaba;S. Banerjee
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- hot deformation;
- Zr alloys;
- ingot breakdown;
11.A Numerical Study of the Effect of Extrusion Parameters on the Temperature Distribution in Zr-2.5Nb

机译：挤压参数对Zr-2.5Nb温度分布影响的数值研究
- 作者：N. Saibaba;N. Keskar;K. V. Mani Krishna;V. Raizada;K. Vaibhaw;S. K. Jha;D. Srivastava;G. K. Dey
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- pressure tube;
- hot extrusion;
- simulation;
- FEM;
- Zr-2.5;
- wt. Nb;
12.Study on Effect of Processing on Texture Development in Zirconium-2.5 Niobium Alloy Tubes

机译：工艺对2.5％锆铌合金管织构发展的影响研究
- 作者：N. Saibaba;K. Kapoor;S. V. Ramana Rao;Kalpana Itisri;S. K. Jha;C. Phani Babu;G. N. Ganesha;B. Prahlad;R. K. Mistry
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- Zr-2.5Nb;
- crystallographic texture;
- thermo-mechanical-treatment;
- pilgering;
13.Numerical Modeling of Fuel Rod Resistance Butt Welding

机译：燃料棒电阻对接焊的数值模拟
- 作者：A. Gaillac;D. Duthoo;C. Vauglin;D. Carcey-Collet;F. Bay;K. Mocellin
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- zirconium alloys;
- fuel rods;
- welding;
- numerical modeling;
- finite element;
14.Application of Coating Technology on Zirconium-Based Alloy to Decrease High-Temperature Oxidation

机译：锆基合金涂层技术在降低高温氧化中的应用
- 作者：Hyun-Gil Kim;Il-Hyun Kim;Jeong-Yong Park;Yang-Hyun Koo
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- zirconium;
- high-temperature oxidation;
- coating;
15.Oxidation Mechanism in Zircaloy-2-The Effect of SPP Size Distribution

机译：Zircaloy-2-的氧化机理SPP尺寸分布的影响
- 作者：Pia Tejland;Hans-Olof Andren;Gustav Sundell;Mattias Thuvander;Bertil Josefsson;Lars Hallstadius;Maria Ivermark;Mats Dahlbaeck
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- Zircaloy-2;
- oxidation;
- SPP;
- TEM;
- APT;
16.Effect of Sn on Corrosion Mechanisms in Advanced Zr-Cladding for Pressurised Water Reactors

机译：锡对压水反应堆高级Zr熔覆层腐蚀机理的影响
- 作者：P. G. Frankel;J. Wei;E. M. Francis;A. Forsey;N. Ni;S. Lozano-Perez;A. Ambard;M. Blat-Yrieix;R. J. Comstock;L. Hallstadius;R. Moat;C. R. M. Grovenor;S. Lyon;R. A. Cottis;M. Preuss
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- Zirconium alloys;
- ZrO_2;
- corrosion mechanisms;
- synchrotron X-ray diffraction;
- In-situ oxidation;
- phase transformation;
17.Understanding of Corrosion Mechanisms of Zirconium Alloys after Irradiation: Effect of Ion Irradiation of the Oxide Layers on the Corrosion Rate

机译：了解锆合金辐照后的腐蚀机理：氧化物层的离子辐照对腐蚀速率的影响
- 作者：Marc Tupin;Joel Hamann;Damien Cuisinier;Philippe Bossis;Martine Blat;Antoine Ambard;Alain Miquet;Damien Kaczorowski;Francois Jomard
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- irradiation;
- corrosion;
- diffusion;
18.Effect of Alloying Elements on Hydrogen Pickup in Zirconium Alloys

机译：合金元素对锆合金中氢吸收的影响
- 作者：Adrien Couet;Arthur T. Motta;Robert J. Comstock
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- hydrogen pick-up;
- zirconium alloys;
- CNPGAA;
- XANES;
- alloying elements;
- electronic conductivity;
19.Toward a Comprehensive Mechanistic Understanding of Hydrogen Uptake in Zirconium Alloys by Combining Atom Probe Analysis With Electronic Structure Calculations

机译：通过将原子探针分析与电子结构计算相结合来全面了解锆合金中的氢吸收机理
- 作者：Mikaela Lindgren;Gustav Sundell;Itai Panas;Lars Hallstadius;Mattias Thuvander;Hans-Olof Andren
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- corrosion;
- hydrogen pickup;
- density functional theory;
- atom probe tomography;
- zirconium;
- alloys;
- suboxide;
- hydride;
- HPU;
- HPUF;
20.Corrosion and Hydrogen Uptake in Zirconium Claddings Irradiated in Light Water Reactors

机译：轻水反应堆中辐照的锆熔覆层的腐蚀和氢吸收
- 作者：Sousan Abolhassani;Gerhard Bart;Johannes Bertsch;Mirco Grosse;Lars Hallstadius;Armin Hermann;Goutam Kuri;Guido Ledergerber;Clement Lemaignan;Matthias Martin;Stephane Portier;Christian Proff;Renato Restani;Stephane Valance;Sima Valizadeh;Holger Wiese
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- hydrogen content;
- oxidation;
- irradiation effects;
- high burnup;
- TEM;
- EPMA;
- SIMS;
21.Oxidation and Hydrogen Uptake of ZIRLO Structural Components Irradiated to High Burn-Up

机译：ZIRLO结构组分被高燃耗后的氧化和氢吸收
- 作者：J. M. Garcia-Infanta;M. Aullo;D. Schrire;F. Culebras;A. M. Garde
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- ZIRLO;
- oxidation;
- guide tube;
- grid;
- hydrogen induced growth;
- irradiation growth;
- grid growth;
22.Performance and Property Evaluation of High-Burnup Optimized ZIRLO™ Cladding

机译：高爆裂优化ZIRLO™覆层的性能和性能评估
- 作者：G. Pan;A. M. Garde;A. R. Atwood
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
23.Corrosion, Dimensional Stability and Microstructure of VVER-1000 E635 Alloy FA Components at Burnups up to 72 MWday/kgU

机译：VVER-1000 E635合金FA组件在燃耗高达72 MWday / kgU时的腐蚀，尺寸稳定性和显微组织
- 作者：V. N. Shishov;V. A. Markelov;A. V. Nikulina;V. V. Novikov;M. M. Peregud;A. Yu. Shevyakov;I. N. Volkova;G. P. Kobylyansky;A. E. Novoselov;A. V. Obukhov
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- neutron irradiation;
- E635 alloy;
- fuel rod cladding;
- fuel assemblies;
- oxide film thickness;
- hydrogen;
- microstructure;
- precipitates;
- dislocations;
- electron microscopy;
- growth;
- examination;
24.Corrosion and Hydriding Model for Zircaloy-2 Pressure Tubes of Indian Pressurised Heavy Water Reactors

机译：印度加压重水反应堆Zircaloy-2压力管的腐蚀和氢化模型
- 作者：S. K. Sinha;R. K. Sinha
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- PHWR;
- Zircaloy-2;
- corrosion;
- pressure tube;
25.Oxide Surface Peeling of Advanced Zirconium Alloy Cladding after High Burnup Irradiation in Pressurized Water Reactors

机译：高压水反应堆中高燃耗辐射后高级锆合金熔覆的氧化物表面剥落
- 作者：A. M. Garde;G. Pan;A. J. Mueller;L. Hallstadius
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- zirconium alloys;
- high corrosion resistance;
- oxide delamination;
- peeling;
- spalling;
- hydride localization;
- ductility;
- wear resistance;
26.The Effects of Microstructure and Operating Conditions on Irradiation Creep of Zr-2.5Nb Pressure Tubing

机译：Zr-2.5Nb压力管微观组织和工作条件对辐照蠕变的影响
- 作者：L. Walters;G. A. Bickel;M. Griffiths
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- Zr-2.5Nb alloy;
- pressure tube;
- neutron irradiation;
- irradiation creep;
- microstruc-ture;
- in-reactor deformation;
27.Breakthrough in Understanding Radiation Growth of Zirconium

机译：理解锆的辐射生长方面的突破
- 作者：Stanislav I. Golubov;Alexander V. Barashev;Roger E. Stoller;Bachu N. Singh
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- neutron irradiation;
- zirconium;
- radiation growth;
- theory;
28.Microstructural Evolution of M5™ Alloy Irradiated in PWRs up to High Fluences-Comparison With Other Zr-Based Alloys

机译：与其他Zr基合金相比，在PWR中高通量辐照的M5™合金的微观结构演变
- 作者：S. Doriot;B. Verhaeghe;J.-L. Bechade;D. Menut;D. Gilbon;J.-P. Mardon;J.-M. Cloue;A. Miquet;L. Legras
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- irradiation;
- dislocation loops;
- microstructure;
- Zr1Nb alloys;
- precipitation;
- growth;
29.Modeling Irradiation Damage in Zr-2.5Nb and Its Effects on Delayed Hydride Cracking Growth Rate

机译：Zr-2.5Nb辐照损伤的建模及其对延迟氢化物裂解生长速率的影响
- 作者：G. A. Bickel;M. Griffiths;H. Chaput;A. Buyers;C. E. Coleman
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- Zr-2.5Nb;
- neutron irradiation;
- delayed hydride cracking;
- pressure tubes;
- micro-structure;
- X-ray diffraction;
- line broadening;
- beta-phase;
30.Understanding the Drivers of In-Reactor Growth of β-Quenched Zircaloy-2 BWR Channels

机译：了解β淬灭Zircaloy-2 BWR通道在反应器中生长的驱动因素
- 作者：Javier Romero;Mats Dahlbaeck;Lars Hallstadius;Maria Ivermark;Guido Ledergerber
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- beta-quenching;
- irradiation growth;
- hydrogen pickup;
31.Impact of Hydrogen Pick-Up and Applied Stress on C-Component Loops: Toward a Better Understanding of the Radiation Induced Growth of Recrystallized Zirconium Alloys

机译：氢吸收和施加应力对C成分回路的影响：更好地理解辐射诱导的重结晶锆合金的生长
- 作者：L. Tournadre;F. Onimus;J.-L. Bechade;D. Gilbon;J.-M. Cloue;J.-P. Mardon;X. Feaugas
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- zirconium;
- growth;
- c-loops;
- hydrogen;
- stress;
- ion irradiation;
32.Contribution to the Study of the Pseudobinary Zr1Nb-O Phase Diagram and Its Application to Numerical Modeling of the High-Temperature Steam Oxidation of Zr1Nb Fuel Cladding

机译：准二元Zr1Nb-O相图研究及其在Zr1Nb燃料熔覆层高温蒸汽氧化数值模拟中的应用
- 作者：M. Negyesi;J. Krejci;S. Linhart;L. Novotny;A. Pribyl;J. Burda;V. Kloucek;J. Lorincik;J. Sopousek;J. Adamek;J. Siegl;V. Vrtilkova
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- fuel cladding;
- oxidation;
- Zr1Nb-O;
- modeling;
- microstructure;
33.Experimental Comparison of the Behavior of E110 and E110G Claddings at High Temperature

机译：E110和E110G熔覆层高温行为的实验比较
- 作者：Zoltan Hozer;Erzsebet Perez-Fero;Tamas Novotny;Imre Nagy;Marta Horvath;Anna Pinter-Csordas;Andras Vimi;Mihaly Kunstar;Tamas Kemeny
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- Zirconium oxidation;
- cladding embrittlement;
- ballooning and burst;
34.Effect of Pre-Oxide on Zircaloy-4 High-Temperature Steam Oxidation and Post- Quench Mechanical Properties

机译：预氧化物对Zircaloy-4高温蒸汽氧化和淬火后力学性能的影响
- 作者：S. Guilbert;P. Lacote;G. Montigny;C. Duriez;J. Desquines;C. Grandjean
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- LOCA;
- oxygen diffusion;
- corrosion layer;
- steam oxidation;
- high temperature;
35.Deviations From Parabolic Kinetics During Oxidation of Zirconium Alloys

机译：锆合金氧化过程中抛物线动力学的偏差
- 作者：Martin Steinbrueck;Mirco Grosse
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- zirconium alloy;
- oxidation;
- kinetics;
- nuclear safety research;
36.Influence of Steam Pressure on the High Temperature Oxidation and Post-Cooling Mechanical Properties of Zircaloy-4 and M5 Cladding (LOCA Conditions)

机译：蒸汽压力对Zircaloy-4和M5熔覆层的高温氧化和冷却后力学性能的影响（LOCA条件）
- 作者：M. Le Saux;V. Vandenberghe;P. Crebier;J. C. Brachet;D. Gilbon;J. P. Mardon;P. Jacques;A. Cabrera
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
37.Analysis of the Secondary Cladding Hydrogenation During the Quench-LOCA Bundle Tests With Zircaloy-4 Claddings and its Influence on the Cladding Embrittlement

机译：Zircaloy-4覆层淬火-LOCA捆绑试验中二次覆层氢化的分析及其对覆层脆化的影响
- 作者：M. Grosse;J. Stuckert;C. Roessger;M. Steinbrueck;M. Walter;A. Kaestner
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- loss of coolant accidents;
- secondary hydrogenation;
- neutron imaging;
- hydrogen embrittlement;
38.Effect of Hydride Distribution on the Mechanical Properties of Zirconium-Alloy Fuel Cladding and Guide Tubes

机译：氢化物分布对锆合金燃料熔覆和导管力学性能的影响
- 作者：Suresh K. Yagnik;Jen-Hung Chen;Roang-Ching Kuo
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- zirconium alloys;
- hydrides;
- mechanical properties;
39.Mechanisms of Hydride Reorientation in Zircaloy-4 Studied in Situ

机译：Zircaloy-4原位研究氢化物重定向的机理
- 作者：Kimberly Colas;Arthur Motta;Mark R. Daymond;Jonathan Almer
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- zirconium hydrides;
- reorientation;
- synchrotron x-ray diffraction;
40.Hydriding Induced Corrosion Failures in BWR Fuel

机译：氢化诱导的BWR燃料腐蚀失效
- 作者：Dan Lutz;Yang-Pi Lin;Randy Dunavant;Rob Schneider;Hartney Yeager;Aylin Kucuk;Bo Cheng;Jim Lemons
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
- BWR;
- Zircaloy-2;
- corrosion;
- hydriding;
- failure mechanism;
- secondary ion mass spectrometry;
- hydrogen diffusion;
- finite element modeling;
41.Foreword

机译：前言
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年
42.Overview

机译：总览
- 作者：Robert J. Comstock;Pierre Barberis
- 会议名称：《International symposium on zirconium in the nuclear industry》 | 2015年