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International Conference on Nuclear Engineering: Abstracts

召开年：2005
召开地：Beijing(CN)
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1.THE ONLINE SIMULATION OF CORE PHYSICSIN NUCLEAR POWER PLANT

机译：核电站核心物理的在线模拟。
- 作者：Zhao Qiang; Zhang Zhijian; Cao Xinrong
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- online simulation;
- core physics;
- NPP;
2.Beam Steering Technique of Ultrasonic Waveguide Sensorfor Under-Sodium Inspection of Sodium Fast Reactor

机译：钠快检查反应堆钠检查用超声波波导传感器的光束转向技术
- 作者：Young-Sang Joo; Jae-Han Lee
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Ultrasonic;
- Waveguide;
- Under-Sodium Inspection;
- Sodium Fast Reactor;
3.IMPROVEMENTS TO THE RELAP5-3D NEARLY-IMPLICIT NUMERICAL SCHEME

机译：RELAP5-3D近似隐式数字方案的改进
- 作者：Richard A. Riemke; Walter L. Weaver; Richard R. Schultz
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
4.Solubility Study of Tc(IV) Oxides

机译：Tc（IV）氧化物的溶解度研究
- 作者：LIU De-jun; FAN Xian-hua
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Tc(IV) oxide;
- solubility;
- rate of oxidation;
5.ANALYSIS OF PUMPING PERFORMANCES IN ONE-STAGETURBOMOLECULAR PUMP BY 3D DIRECT SIMULATIONMONTE CARLO CALCULATION

机译：3D直接模拟蒙特卡罗计算法分析单核糖皮质激素泵的泵性能
- 作者：Sheng Wang; Hisashi Ninokata
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Turbomolecular Pump;
- DSMC;
- Pumping Performances;
- Transmission Probability;
6.TURBULENCE MODEL STUDY FOR THE SIMULATION OF HIGHDENSITY LIQUID METAL FLOW IN WINDOW TARGET

机译：窗口目标中高密度液态金属流动模拟的湍流模型研究
- 作者：T. K. Das; P. Satyamurthy
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
7.AXIAL DEVELOPMENT OF SUBCOOLED BOILING FLOW IN AVERTICAL CONCENTRIC ANNULUS

机译：垂直集中环过冷沸腾流动的轴向发展
- 作者：Taeho Lee; Rong Situ; Takashi Hibiki; Tomoji Takamasa; Mamoru Ishii
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
8.ACR?* MODULARIZATION AND CONSTRUCTABILITY:ACHIEVING THE CONSTRUCTION SCHEDULE

机译：ACR？*模块化和可构造性：实现施工时间表
- 作者：J.W. Love; R. Ricciuti; M. Elgohary; E. Choy; L.Hiebert
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- AECL;
- CANDU?;
- ACR;
- schedule;
- constructability;
- module;
- parallel;
- construction;
- sequence;
9.FEATURES AND VALIDATION OF DISCRETE ELEMENT METHODFOR SIMULATING PEBBLE FLOW IN REACTOR CORE

机译：反应堆核中模拟卵石流的离散元方法的特点与验证
- 作者：Yong Xu; Yanjie Li
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Discrete Element Method;
- reactor core;
- fuel pebble;
10.A STABLE OPERATING PROCEDURE AND THE START-UP ISSUES INA NATURAL CIRCULATION PRESSURE TUBE BOILING WATERREACTOR

机译：自然循环压力管沸腾水反应器的稳定运行过程和启动问题
- 作者：P.K. Vijayan; R. K. Bagul; G.S.S.P. Rao; D.S.Pilkhwal; A.K. Nayak; D.Saha; R.K. Sinha
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- natural circulation;
- instability;
- boilingwater reactors;
- start-up;
11.AP1000 BEST ESTIMATE LARGE BREAK LOCA ANALYSIS PERFORMEDWITH THE WESTINGHOUSE AUTOMATED STATISTICAL TREATMENT OFUNCERTAINTY METHOD (ASTRUM)

机译：AP1000最佳估计的大型突破口分析，通过西屋自动不确定性统计处理方法（ASTRUM）执行
- 作者：Cesare Frepoli; Stéphanie Y. Antoine; Xiaoping Li; Robert M. Kemper; Katsuhiro Ohkawa
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
12.MAJOR COMPONENT REPLACEMENT PROJECTSPLANNING AND INSTALLATION EXPERIENCE

机译：主要零件更换项目的规划和安装经验
- 作者：Philippe Denimal; Gary M. Mignogna; Daniel M. Schlader
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Alloy 600;
- Pressurizer;
- Steam Generator;
- Reactor Vessel Head;
- Integrated Head Assembly;
13.DEVELOPMENT AND DEMONSTRATION OF ATR-MOX FUEL

机译：ATR-MOX燃料的开发与示范
- 作者：Tomoyuki Abe; Seiichiro Maeda; Hiroaki Nakazawa
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- ATR;
- MOX fuel;
- FUGEN;
- nuclear fuel cycle;
14.A NOVEL NON-DESTRUCTIVE METHOD FOR DISTINGUISHINGBETWEEN FATIGUE AND STRESS CORROSION CRACKS USINGELECTROMAGNETIC INDUCTION

机译：电磁感应识别疲劳裂纹与应力腐蚀裂纹的新型非破坏性方法
- 作者：Ladislav Janousek; Zhenmao Chen; Noritaka Yusa; Kenzo Miya
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- fatigue crack;
- stress corrosion crack;
- distinguish;
- non-destructive evaluation;
- electromagneticinduction;
- eddy currents;
15.AN ESTIMATION OF REACTOR THERMAL POWER UNCERTAINTYUSING UFM-BASED FEEDWATER FLOW RATE IN NUCLEARPOWER PLANTS

机译：基于UFM的核电站锅炉反应器热力不确定度的估算。
- 作者：Byung Ryul Jung; Ho Cheol Jang; Byung Jin Lee; Se Jin Baik; Woo Hyun Jang
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Venturi Meter;
- Ultrasonic Flow Meter;
- Feedwater Flow Rate;
- OPR1000;
- Reactor Thermal PowerUncertainty;
16.BEACON-COLSS CORE MONITORING SYSTEMAPPLICATION AND BENEFITS

机译：BEACON-COLSS核心监控系统的应用和优势
- 作者：Tae Young Yoon; William A. Boyd
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- BEACON;
- COLSS;
- Core Monitoring;
17.ENHANCING HEAT TRANSFER AND CRUD MITIGATIONIN PWR FUEL

机译：加强压水堆燃料的传热和减缓结垢
- 作者：L. David Smith, Ⅲ; Michael E. Conner; Paul F. Joffre; Zeses E. Karoutas; Dmitry V. Paramonov; Bin Liu; Milorad B. Dzodzo
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- PWR Fuel;
- Heat Transfer;
- Spacer Grid;
- IFM;
- AOA;
- Crud;
18.CONDENSER PERFORMANCE IMPACT ON PLANT OPERATIONSAND COMPONENT LIFE CYCLE

机译：冷凝器性能对工厂操作和组件生命周期的影响
- 作者：Joseph W. Harpster
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
19.A Conceptual Design of Passive Containment Cooling System for Thorium-basedAdvanced Nuclear System

机译：基于Thor的先进核系统被动安全壳冷却系统的概念设计
- 作者：YU Jiyang; YOU Songbo; JIA Baoshan; Sollychin Rayman; RUAN Yangqiang
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- TACR;
- PCCS;
- PCCSAC;
- LOCA;
20.Public Opinion on Nuclear Power in China

机译：中国核电舆论
- 作者：Shi Zhengang; Liu Changxin; Zhang Zuoyi
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- nuclear power;
- public acceptance;
21.PRESSURE SURGE IN A RAPID SHUTDOWN SYSTEM:UPDATE OF CALCULATIONS BY MEASUREMENT RESULTS

机译：快速关机系统中的压力波动：通过测量结果更新计算
- 作者：Fritz-Otto Henkel; Helmut Kennerknecht; Dirk Schümann
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Boiling water reactor (BWR);
- rapid shutdown system;
- piping;
- calculation;
- measurement;
- strain gage;
- displacement;
- acceleration;
- pressure;
- pressure surge;
- non-linear effects;
- rupture;
22.RESULTS OF THE QUENCH-L1, DISCO-L1, AND COMET-L1EXPERIMENTS PERFORMED WITHIN THE LACOMERA PROJECTAT THE FORSCHUNGSZENTRUM KARLSRUHE

机译：在FORSCHUNGSZENTRUM KARLSRUHE的Lacomera项目中执行QUENCH-L1，Disco-L1和COMET-L1实验的结果
- 作者：Alexei Miassoedov; Hans Alsmeyer; Leonhard Meyer; Martin Steinbrueck; Zoltan Hozer; Ivan Ivanov; Guena Doubleva; Michel Cranga; Cataldo Caroli; Delphine Plassart
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- safety;
- severe accidents;
- quench;
- MCCI;
- DCH;
23.DUCTILE DESIGN OF STRUCTURE UNDER IMPACT LOAD

机译：冲击载荷下结构的延性设计
- 作者：James Y. Zhu
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- ductile design;
- steel structure;
- large deformation;
- impact load;
- ductility ratio;
24.THE INDUSTRIAL ORGANIZATION IS THE KEY TO A NATIONAL SELF-RELIANT PROGRAM

机译：工业组织是国家自立计划的关键
- 作者：Hervé MACHENAUD
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
25.DETECTION AND SIZING OF DEFECTS IN STRUCTURAL COMPONENTS OF A NUCLEARPOWER PLANT BY ECT

机译：ECT检测和鉴定核电厂植物结构成分的缺陷
- 作者：Zhenmao Chen; Kenzo Miya
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Eddy current testing;
- Defect detection;
- Defect sizing;
- Inservice inspection;
- Welding part;
- Stress corrosion crack;
26.ANALYSIS OF LOSS OF COOLANT ACCIDENT IN MTR POOL TYPERESEARCH REACTORS

机译：MTR池式研究反应器中冷却剂损失的分析
- 作者：Tewfik Hamidouche; El Khider Si-Ahmed; Anis Bousbia-Salah; Francesco D'Auria
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Channel codes;
- Best Estimate codes;
- Reactivity insertion accident;
- Loss of coolant accidents;
- research reactors;
- safety analysis;
27.DEVELOPMENT OF THE DMS (2)(DOUBLE MS: MODULAR SIMPLIFIED & MEDIUMSMALL REACTOR)

机译：DMS的开发（2）（双MS：模块化简化和中小型反应器）
- 作者：Shizuka Hirako; Takahiko Hida; Yuusuke Shimizu; Shigeru Yokouchi; Yoshinori Iimura; Kumiaki Moriya
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Medium & Small Reactor;
- Plant Layout;
- Construction;
- Module;
28.DEVELOPMENT OF TECHNOLOGIES ON INNOVATIVE-SIMPLIFIEDNUCLEAR POWER PLANT USING HIGH-EFFICIENCY STEAMINJECTORS(6) DIRECT CONDENSATION HEAT TRANSFER AND STABILITY OFWATER JET IN STEAM INJECTOR

机译：高效气化炉创新简化核电站技术的发展（6）蒸汽喷射管内直接凝结换热和水射流稳定性
- 作者：Yasuo Koizumi; Hiroyasu Ohtake; Naoki Yamashita; Tohru Miyashita; Michitsugu MORI
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Water jet stability;
- Steam injector;
- Next-generation reactor;
- Condensation;
29.POLCA-T ?A COUPLED 3D NEUTRON KINETIC AND THERMAL HYDRAULIC CODEFOR ANALYSIS OF BWR'S

机译：POLCA-T耦合的3D中子动力学和热工液压代码分析BWR
- 作者：Ulf Bredolt; Dobromir Panayotov
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
30.NUCLEAR CRITICALITY SAFETY AT GLOBAL NUCLEAR FUEL

机译：全球核燃料的核临界安全性
- 作者：Lon E. Paulson; Qi Ao
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Nuclear Criticality Safety;
- Double Contingency Principle;
- Criticality Safety Design Criteria;
- Monte Carlo;
31.VITRIFICATION OF HLW IN COLD CRUCIBLE MELTER

机译：高熔点熔炼机的玻璃化
- 作者：JF Hollebecque; G. Bordier; R. Do Quang; T. Flament
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
32.BIOSORPTION OF AMERICIUM-241 BY SACCHAROMYCES CEREVISAE:PRELIMINARY EVALUATION AND MECHANISM

机译：酿酒酵母对AMERICIUM-241的形态学研究：初步评估和机理
- 作者：Ning Liu; Jiali Liao; Yuanyou Yang; Qiang Luo; Jiannan Jin; Shunzhong Luo; Pengji Zhao
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Radionuclides;
- Americium-241;
- Saccharomyces cerevisiae;
- Biosorption;
33.THEORETICAL AND EXPERIMENTAL STUDIES ON TRANSIENT HEATTRANSFER FOR FORCED CONVECTION FLOW OF HELIUM GASOVER A HORIZONTAL CYLINDER

机译：水平气瓶氦气强制对流瞬态换热的理论和实验研究
- 作者：Qiusheng LIU; Katsuya FUKUDA; Zheng ZHANG
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Transient heat transfer;
- Forced convection;
- Heliumgas;
- Exponentially increasing heat input;
- Period;
- Numericalsolution;
- Turbulent flow;
- Horizontal cylinder;
- Diameter;
34.ANALYTICAL REDUNDANCY FOR CANDU NUCLEAR POWER PLANTSUSING A MODIFIED DEDICATED OBSERVER SCHEME

机译：修改后的专用观察者方案对坎杜核电站的分析冗余
- 作者：Lee Rehorn; Jin Jiang
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
35.CONCEPTUAL DESIGN OF SO3 DECOMPOSER FORTHERMO-CHEMICAL IODINE-SULFUR PROCESS PILOT PLANT

机译：SO3分解器碘化学硫制程试验厂的概念设计
- 作者：Akihiro Kanagawa; Seiji Kasahara; Atsuhiko Terada; Shinji Kubo; Ryutaro Hino; Yoshiyuki Kawahara; Masaharu Watabe; Hiroshi Fukui; Kazuo Ishino; Toshio Takahashi
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- HTGR;
- Hydrogen production;
- Iodine-Sulfur process;
- SO3 decomposer;
- SiC ceramics;
- Heat exchanger;
36.INVESTIGATION OF POLONIUM REMOVAL SYSTEMS FORLEAD-BISMUTH COOLED FAST REACTORSUSING A TELLURIUM SURROGATE – PART III

机译：含硫酸铝的无烟铋快速冷却反应器除磷系统的研究-第三部分
- 作者：Shuji Ohno; Eric P. Loewen; Laurence E. Auman
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Lead-Bismuth Eutectic;
- Polonium;
- Tellurium;
- Lead Cooled Reactor;
37.ENVIRONMENTAL FATIGUE LIFE EVALUATIONOF LWR COMPONENT MATERIALS

机译：轻水堆组件材料的环境疲劳寿命评估
- 作者：Katsumi Sakaguchi
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Fatigue;
- Environment;
- LWR Component Materials;
- Environmental Correction Factor;
38.VALIDATION OF A THERMAL HYDRAULIC COMPUTER CODE TO PERFORM TWO-PHASEMULTI-COMPONENT FORCE CALCULATIONS FOR STRUCTURALEVALUATIONS

机译：验证热液压计算机代码以进行结构评估的两阶段多分量力计算
- 作者：Joseph S. Miller; Kevin Ramsden
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
39.Fundamental Challenging Problems for Developing New NuclearSafety Standard Computer Codes

机译：开发新的核安全标准计算机代码的基本挑战性问题
- 作者：Po Kee Wong; Adam E. Wong; Anita Wong
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- TRAJECTORY SOLID ANGLE;
- GEOMETRIC SOLID ANGLE;
- WONG'S ANGLE;
40.STUDY OF VISUALIZED ANALYSIS PLATFORM FOR NUCLEAR FUELCYCLE SYSTEM BASED ON MULTILEVEL FLOW MODEL

机译：基于多级流模型的核燃料系统可视化分析平台研究
- 作者：Jingquan Liu; Hidekazu Yoshikawa; Yangping Zhou; Jun Ouyang; Ming Yang
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Multilevel Flow Model;
- Nuclear Fuel Cycle;
- Levelised Cost Assessment;
- Graphical modeling method;
41.STRESS ANALYSIS AND ASSESSMENT OF HERMETICALLY SEALEDCONTAINER FOR RADIOACTIVE MATERIAL TRANSPORTATION

机译：放射性材料气密密封容器的应力分析与评估
- 作者：Xu Jing;Sun Lei;Li Xihua
- 会议名称：《》 | 2005年
- container for radioactive material transportation;
- drop;
- stress analysis;
42.DEVELOPMENT OF UNDERWATER LASER CLADDING ANDUNDERWATER LASER SEAL WELDING TECHNIQUES FORREACTOR COMPONENTS

机译：反应堆组件的水下激光熔覆和水下激光密封焊接技术的发展
- 作者：Masataka Tamura; Shohei Kawano; Wataru Kouno; Yasushi Kanazawa
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
43.CANDU SAFETY & LICENSING FRAMEWORK & PROCESS

机译：坎杜安全与许可框架和流程
- 作者：Basma A. Shalaby; Frank Nuzzo; Simon Pang
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
44.DECONTAMINATION PERFORMANCE OFLOW–PRESSURE ARC DECONTAMINATION TECHNOLOGYUSING CARBON MONOXIDE GAS

机译：一氧化碳气体对低压电弧净化技术的净化性能
- 作者：Shizue FURUKAWA; Hiromi KANBE; Kazutoshi FUJIWARA; Tadashi AMAKAWA; Kazuo ADACHI
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- decontamination;
- Low-Pressure Arc;
- Co-60 residual ratio;
- carbon monoxide gas;
45.CURRENT STATUS OF &D AND UTILIZATION OF NUCLEA ENE GY IN JAPAN

机译：日本核能研发与利用的最新状况
- 作者：Shunsuke Kondo
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
46.Concept Design of 200kW Medical Isotope Production Reactor

机译：200kW医用同位素生产反应堆的概念设计
- 作者：Danrong SONG; Sheng YUE
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Medical Isotope;
- Homogenous solution reactor;
- Concept Design;
47.METHODOLOGY OF CHF LOOK UP TABLE DERIVATION

机译：CHF查询表格推导方法
- 作者：J. Q. Shan; D. C. Groeneveld; A. Z. Vasic'; J. Yang; A. Durmayaz; S. W. Peng; S.C. Cheng
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Critical Heat Flux;
- Look up table;
48.Recent progress of tungsten as plasma facing materials for fusion reactors

机译：钨作为聚变反应堆面向等离子体的材料的最新进展
- 作者：Xiang Liu; Lin Yang; Fu Zhang; Zengyu Xu; Yong Liu
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Pure tungsten;
- plasma sprayed tungsten coating;
- thermal shock resistancecapability;
- Thermal fatigue;
49.STUDY ON RFP AGING DEGRADATION CAUSED BY REVOLVINGFRICTION

机译：旋转摩擦引起的RFP老化退化的研究
- 作者：Koji Shiroyama; Kenji Araki; Kimihiro Kaimori; Hiroyuki Miyamoto; Makoto Terajima; Yojiro Hayashi
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- reactor feed water pump;
- aging degradation;
- revolving friction;
50.INFLUENCE OF HIGH BURNUP ON THE DECAY HEAT POWER OFSPENT FUEL AT LONG-TERM STORAGE

机译：高燃比对长期储存燃料油衰减热力的影响
- 作者：Boris Bergelson; Alexander Gerasimov; Georgy Tikhomirov
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Spent fuel;
- long-term storage;
- high burnup;
51.RCCA IN-SERVICE AUTO-INSPECTION SIGNAL ANALYSIS ANDEVALUATION

机译：RCCA服务中自动检查信号分析与评估
- 作者：Zhong Zhimin; Zheng Honglian; Li Jinsong; Xue Xincai; Ye Chen; Wang Ruizheng
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Ultrasonic testing;
- Eddy current testing;
- Fuel assembly;
- Control rod;
52.Fast neutron flux and fluence outside the fissile zone of PWR fuel assemblyCalculation methodology using MCNP Monte Carlo code and SCIENCEpackage

机译：压水堆燃料组件易裂变区域外的快速中子通量和注量使用MCNP蒙特卡洛代码和SCIENCEpackage的计算方法
- 作者：S. Zheng; N. Comte; M. Pasquet
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Neutron Flux;
- Fluence;
- PWR FuelAssembly;
- MCNP;
- SCIENCEpackage;
53.ANALYSIS OF 2D REACTOR CORES USING LINEAR PERTURBATIONTHEORY AND NODAL FINITE ELEMENT METHODS

机译：基于线性摄动理论和节点有限元方法的二维反应堆芯分析
- 作者：César Adrián Múgica Rodríguez; Edmundo del Valle Gallegos
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- codes;
- diffusion;
- nodal;
- shuffling;
- perturbation;
- eigenvalue;
54.IRIS (INTERNATIONAL REACTOR INNOVATIVE AND SECURE)SAFETY SYSTEM AND EQUIPMENT DESIGN VERIFICATION TESTPLAN

机译：IRIS（国际反应堆创新和安全）安全系统和设备设计验证测试计划
- 作者：L. E. CONWAY
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- IRIS;
- Test Plan;
- Test;
55.MIMAS, SETTING THE WORLD-WIDE STANDARDFOR PLUTONIUM RECYCLING

机译：MIMAS设定了全球范围的P回收标准
- 作者：Alain Vandergheynst; Yvon Vanderborck
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- MIMAS;
- MOX;
- Plutonium;
- MOX Fabrication;
56.A NUMERICAL ESTIMATION ON THE VELOCITY CORRECTIONFACTOR OF THE UFMFOR MAIN FEEDWATER FLOW RATE MEASUREMENTS

机译：UFMFOR主要进水流速测量速度校正因子的数值估算。
- 作者：Ho Cheol Jang; Byung Jin Lee; Byung Ryul Jung; Se Jin Baik; Jae Hong Ha; Woo Hyun Jang
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
57.HIGH TEMPERTURE NPSH AND ITS APPLICATION FORA FEEDWATER SYSTEM

机译：高温NPSH及其在给水系统中的应用。
- 作者：Jun Manabe; Kazuyoshi Miyagawa
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- NPSH;
- feedwater booster pump;
- load reduction;
- deaerator tank;
- depression boiling;
- cavitation;
- thermal effect;
58.ANALYSIS OF CRACK PROPAGATION IN MATERIALS

机译：材料的裂纹扩展分析
- 作者：Afzaal M. Malik; Ejaz. M. Qureshi; A. Shafiq; U. Ullah
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
59.ANALYSIS OF TWO DIFFERENT TYPES OF HYDROGENCOMBUSTION DURING SEVERE ACCIDENTS IN A TYPICALPRESSURIZED WATER REACTOR

机译：典型加压水反应器严重事故中两种不同类型的氢燃烧分析
- 作者：Ko Yu-Chih; Lee Min
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Severe Accident;
- Hydrogen Combustion;
- PWR;
- LOCA;
- SBO;
60.IRIS – ECONOMICS REVIEW

机译：虹膜–经济评论
- 作者：K. Miller
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Modular Reactor;
- International Group;
- Cumulative Cashflow;
- Learning in Construction;
- Learning in Operation;
61.DEVELOPMENT OF TECHNOLOGIESOF NUCLEAR CERAMIC GRADE FUEL PRODUCTION

机译：核陶瓷分级燃料生产技术的发展
- 作者：Anton Manych; Anatoliy Kuchkovskiy; Igor Korobeynikov
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
62.AN ENGINEERING DESIGN OF REACTOR WITH NPP SPENT FUELS

机译：NPP油毡反应器的工程设计
- 作者：Yuan Luzheng; Li Yulun; Shen Feng; Yang Changjiang; Dai Changnian; Jin Huajin
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- spent fuel pool reactor;
- spent fuel of NPP;
- seawater desalination;
- safety analysis;
63.EFFECTS OF SURFACE CONDITIONS ON TRANSIENT POOLBOILING CHF IN VARIOUS LIQUIDS WITH DIFFERENTMECHANISMS DEPENDING ON PRESSURE AND SUBCOOLING(DRAFT)

机译：表面条件对各种液体的瞬态沸腾CHF的影响，其机理取决于压力和沉降（草案）
- 作者：JongDoc Park; Katsuya Fukuda; QiuSheng Liu
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Transient Boiling;
- Pool Boiling;
- CHF;
- Surface Condition;
64.VOID FRACTION AND PRESSURE DROP IN TWO-PHASEEQUILIBRIUM FLOWS IN A VERTICAL 2×3 ROD BUNDLE CHANNEL

机译：垂直2×3杆束通道两相平衡流中的空隙率和压降
- 作者：Michio Sadatomi; Keiko Kano; Akimaro Kawahara; Naoki Mori
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Void fraction;
- Pressure drop;
- Two-phase flow;
- Subchannel;
- Rod bundle;
65.DEVELOPMENT OF INNOVATIVE RADIATION DETECTORUSING RADIATION INDUCED SURFACE ACTIVATION

机译：辐射诱导表面活化的新型辐射检测技术的发展
- 作者：Michiyo TAKANO; Tatsuya HAZUKU; Tomoji TAKAMASA; Koji OKAMOTO; Hiroyuki DATE; Norio TSUJIMURA; Hidemasa TOMOZAWA
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- radiation detector;
- Radiation Induced Surface Activation (RISA);
- oxidized metal;
- TiO2 film;
- high-temperature conditions;
66.EVALUATION OF STRUCTURAL INTEGRITY ANDCONTROLLABILITY OF THE MAIN FEED WATER CONTROL VALVEFOR APWRS

机译：APWRS主给水控制阀的结构完整性和可控性评价
- 作者：Koji Tachibana; Toshikazu Maeda; Hideyuki Morita; Takaharu Hiroe; Koichiro Oketani
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- main feed water control valve;
- fluid force;
- APWR;
67.IMPROVEMENT OF M310 PWR: A STUDY OF THE LOAD FOLLOWWITHOUT BORON ADJUSTMENT

机译：M310 PWR的改进：无需硼调节的负载跟踪研究
- 作者：Zirong Ma; Zenghua Yao
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- load follow;
- LFWOBA;
- daily load cycle;
- AO;
68.HTR CONFINEMENT/CONTAINMENTAND THE PROTECTION AGAINSTAIRCRAFT CRASH

机译：HTR的限制/防护和防止飞机坠毁
- 作者：Gerd Brinkmann
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Confinement;
- containment;
- accident assumptions;
- environmental impact;
- aircraft crash;
69.Laser based maintenance technology for PWR power plants

机译：压水堆电厂的基于激光的维护技术
- 作者：Itaru Chida; Masaki Yoda; Naruhiko Mukai; Yuji Sano; Makoto Ochiai; Takahiro Miura; Ryoichi Saeki
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Preventive maintenance;
- SCC;
- Laser peening;
- Laser ultrasonic testing;
- BMI;
70.Quickening Development of Nuclear Industry and Promoting Nuclear Power Construction in China

机译：加快发展核工业，促进中国核电建设
- 作者：HUANG Guoju
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
71.STUDY ON SAFETY RELIEF VALVE TESTING LOOP OF HTR-10PRIMARY LOOP PRESSURE RELIEF SYSTEM

机译：HTR-10型主泄压系统安全泄压阀测试环的研究
- 作者：DONG Jianling; Su Qingshan; Wu Xinxin
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
72.PHYSICS CHARACTERISTICS OF LONG-LIFE CORE USING TH-UWITH LEAD-BISMUTH COOLANT

机译：带铅铋冷却剂的-U型长寿命核的物理特性
- 作者：YU Ganglin; WANG Kan
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Th-U fuel;
- Lead-bismuth coolant;
- long-life core;
- nuclear design;
73.SAFE OPERATION AND LIFE EXTENSION OF THE RBMK PLANTS

机译：RBMK植物的安全操作和寿命延长
- 作者：N.M. Sorokin; B.A. Gabaraev; Yu.M. Cherkashov
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
74.Wear in nuclear power plants, environment effect,a tribocorrosion approach

机译：核电厂的磨损，环境影响，摩擦腐蚀方法
- 作者：D.KACZOROWSKI; J.Ph. VERNOT; P. COMBRADE
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- PWR;
- tribocorrosion;
- environment;
- stainless steel;
75.A PROPOSAL OF USING RISK INSIGHTS IN THE SPARE PARTSMANAGEMENT IN NUCLEAR POWER PLANT

机译：在核电厂的备件管理中使用风险意识的建议
- 作者：Ping Min; Jiejuan Tong; Xuhong He
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Spare Parts Management;
- Risk Insights;
- PSA (Probabilistic Safety Assessment);
- EquipmentsCategorization;
76.ACHIEVEMENT OF COOLANT TEMPERATURE OF 950℃ IN HTTR

机译：HTTR中950℃冷却温度的实现
- 作者：Kozo KAWASAKI; Tatsuo IYOKU; Yukio TACHIBANA; Toshio NAKAZAWA; Hideyuki HAYASHI
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- HTTR;
- HTGR;
- 950℃;
- high temperature;
- rise-to-power;
- inherent safety;
77.NUMERICAL SIMULATION OF THREE DIMENSIONAL FLOWIN THE LOWER PLENUM

机译：下增压空间三维流动的数值模拟
- 作者：Xiaojun Wang
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Turbulent flow;
- CFD;
- TRIO_U code;
- Lower plenum;
78.CONCEPT OF INNOVATIVE WATER REACTORFOR FLEXIBLE FUEL CYCLE (FLWR)

机译：柔性燃油循环水反应器（FLWR）的概念
- 作者：T. Iwamura; S. Uchikawa; T. Okubo; T. Kugo; H. Akie; T. Nakatsuka
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Water reactor;
- Fuel cycle;
- Pu multiple recycle;
- MOX fuel;
- High conversion ratio;
- Breeding;
79.ATHLET-MF: A SYSTEM ANALYSIS CODE FOR MULTI-FLUIDNUCLEAR SYSTEMS

机译：ATHLET-MF：用于多核系统的系统分析代码
- 作者：Haiyan Chen; Xu Cheng
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- ATHLET-MF;
- ADS;
- thermal-hydraulics;
- system analysis;
- LBE;
80.DETERMINING THE RESIDUAL LIFETIME FOR THE MAIN RBMKCOMPONENTS IN FRAME OF LIFE EXTENSION OF POWER UNITS

机译：确定机组寿命扩展框架中主要RBMK组件的剩余寿命
- 作者：A.A. Petrov; A.A. Potapov; V.D. Baldin
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- reactor RBMK;
- graphite;
- metal structure;
- life extention;
81.CONDENSATION INDUCED NON-CONDENSABLESACCUMULATION IN A NON-VENTED HORIZONTAL PIPECONNECTED WITH AN ELBOW AND A VERTICAL PIPE

机译：与弯头和竖管连接的无通气水平管中的凝结引起的非凝结积累
- 作者：Vladimir D. Stevanovic; Zoran V. Stosic; Uwe Stoll; Tilman Diesselhorst
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- hydrogen;
- accumulation;
- condensation;
- noncondensables;
- venting pipe;
82.CROSS-FLOW INDUCED VIBRATION ANALYSIS IN TUBE BUNDLES:A BONDGRAPH APPROACH

机译：管束中的横流引起的振动分析：粘结图法
- 作者：Muhammad Afzaal Malik; Badar Rashid; Shahab Khushnood
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Cross flow-induced vibrations;
- tube bundle;
- heatexchanger;
- steam generator;
- Bondgraph approach;
- 20-SIM;
83.RESEARCH ON THE FUSION DIAGNOSIS SYSTEM OF NUCLEARPOWER PLANTS

机译：核电厂融合诊断系统的研究
- 作者：Chun-li XIE; Hong XIA; Yong-kuo LIU
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Data fusion;
- Fault diagnosis;
- Inverted U-tube;
- Nuclear power plant;
84.3D WAVELET BASED CONTAMINANT MASS TRANSPORT MODEL

机译：基于3D小波的污染物大规模运输模型
- 作者：Hesham Nasif; Atsushi Neyama
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Wavelet;
- Contaminant Transport;
- Daubechies;
- Connection coefficients;
- High-level radioactive waste;
85.WAVE PROPAGATION PROPERTIES OF FRAME STRUCTURES

机译：框架结构的波传播特性
- 作者：Akemi Nishida
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- wave propagation;
- frame structure;
- flexural wave;
- Timoshenko beam;
- phase velocity;
86.MULTI-SCALE ANALYSIS OF NUCLEAR REACTOR THERMAL-HYDRAULICSFIRST APPLICATIONS USING THE NEPTUNE PLATFORM

机译：利用海王平台进行核反应堆热液动力学的多尺度分析首次应用
- 作者：Antoine Guelfi; Marc Boucker; Stéphane Mimouni; Dominique Bestion; Pascal Boudier
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
87.INTEGRATED DIGITAL I&C SYSTEM FOR NEW PLANTS(DRAFT)

机译：新植物集成数字化I＆C系统（草案）
- 作者：Homare Sakamoto; Masashi Kitamura
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
88.EDF AGEING MANAGEMENT PROGRAM OF NUCLEAR COMPONENTS :A SAFETY AND ECONOMICAL ISSUE

机译：EDF核成分老化管理计划：安全和经济问题
- 作者：Claude Faidy
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- ageing management program;
- degradation mechanism;
- life management;
89.DEVELOPMENT OF BUILT-IN DEBRIS-FILTER BOTTOM NOZZLEFOR PWR FUEL ASSEMBLIES

机译：压水燃料组件内置碎屑过滤器底部喷嘴的开发
- 作者：Juntaro Shimizu; Kazuki Monaka; Masaji Mori; Kazuo Ikeda
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Debris Filter;
- Bottom Nozzle;
- Nuclear Fuel Assembly;
- PWR;
90.An Optimization Method Applied inthe Development of Spacer Grid of Fuel Assembly

机译：一种优化方法在燃油总成隔板网格开发中的应用
- 作者：HU Haixiang; CHEN Ping
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Fuel;
- Spacer Grid;
- Thermal-Hydraulic;
- CFD;
- CHF;
91.Comparison of MCNP and INSREC-HEP codes for Radiation Evaluation at theMaze entrance of Treatment Room

机译：MCNP和INSREC-HEP代码在治疗室迷宫入口处的辐射评估比较
- 作者：Dong Hoon Shin; Young Wook Lee; Young Ho Cho; Hyun Seok Ko; Chang Sun Kang
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
92.FUEL EFFICIENT NUCLEAR REACTOR CONTROLS

机译：高效核反应堆控制
- 作者：Shantanu Das; Bhibhuranjan Basudeb Biswas
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
93.APPLICATION OF SEISMIC ANALYSIS ON A NEUTRON REFLECTORFOR APWR REACTOR INTERNALS

机译：地震分析在APWR反应堆内部中子反射器中的应用
- 作者：Hiroyuki Murakoso; Toshio Ichikawa; Satoshi Yonemoto; Tomomichi Nakamura; Hideyuki Morita; Minoru Murota; Toshihiko Tanaka; Masao Kimura
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- neutron reflector;
- seismic test;
- seismic analysis;
- fluid-structure interaction;
- nonlinearity;
94.FUNDAMENTAL RESEARCH ON THE COOLING CHARACTERISTICOF PCCS WITH DROPWISE CONDENSATION

机译：降凝结冷却特性PCCS的基础研究
- 作者：Masahiro KAWAKUBO; Mitsuo MATSUZAKI; Hiroshige KIKURA; Masanori ARITOMI; Toshihiro KOMENO
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
95.EXPERIMENTS ON FLOW-INDUCED VIBRATIONSIN A HEAT EXCHANGER TUBE BUNDLE

机译：换热器管束中流动引起的振动的实验
- 作者：Shahab Khushnood; Zaffar Muhammad Khan; Muhammad Afzaal Malik; Zafarullah Koreshi; Mahmood Anwar Khan; Khawaja Sajid Bashir
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- Tube bundle;
- flow-induced vibrations;
- fretting wearloss;
- thermal damping;
- thermal loading;
96.STRUCTURAL INTEGRITY ANALYSIS OF THE STEAMDISTRIBUTION DEVICE IN CASE OF LOCA

机译：LOCA情况下蒸汽分配装置的结构完整性分析
- 作者：Renatas Karalevi?ius; Gintautas Dundulis; Ronald F. Kulak; Sigitas Rimkevi?ius; Algirdas H. Marchertas
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- ALS;
- SDD;
- MDBA;
- LOCA;
- transient analysis;
- vertical vent pipe;
97.CALCULATION OF NEUTRON FLUX DENSITY OF HFETR'S PRESSUREVESSEL

机译：HFE TR压力容器中子通量密度的计算
- 作者：Shuiqing Liu
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
- life extension;
- pressure vessel;
- neutron flux;
- HFETR;
98.Supporting Study of Regulation for Interim Storage Facility for Spent Fuelin Japan

机译：日本乏燃料临时存储设施法规的辅助研究
- 作者：Satoshi Itooka; Takeshi Yokoyama; Masami Kato; Koji Shirai; Toshiari Saegusa
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
99.UNAVAILABILITY, SPURIOUS OPERATION AND COST ANALYSIS OFPERIODICALLY TESTED AND MAINTAINED STANDBY K-OUT-OF-N SYSTEMS

机译：定期测试和维护的备用K-out-of-n系统的不可用性，虚假操作和成本分析
- 作者：Lixuan Lu; Jin Jiang
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年
100.Doses and Radiation Protection: a clear step forward in comparisonwith former generation of PWRs in France and Germany

机译：剂量和辐射防护：与法国和德国的上一代压水堆相比，向前迈出了明显的一步
- 作者：E. Baumann; I. Terry
- 会议名称：《International Conference on Nuclear Engineering: Abstracts》 | 2005年