The microstructure of SA508-3CL steel forging for reactor pressure vessel was studied.
对210mm壁厚的反应堆压力容器模拟锻件的树枝状偏析和显微组织进行了研究。
The properties of SA508-3CL steel forgings for the reactor pressure vessel was studied.
对壁厚为210 mm的反应堆压力容器模拟锻件用SA508-3CL钢的性能进行了研究。
Based on the requirements of western codes and rules and the research achievements, the analysis procedures for structure integrity of reactor pressure vessel (RPV) under pressurized thermal shock (PTS) were presented in this paper.
依据法规要求和国外的研究成果 ,对压水堆核电厂反应堆压力容器承压热冲击 (PTS)的研究方法进行阐述。
Comparison of Elastic-Plastic FE Method and Engineering Method for RPV Fracture Mechanics Analysis
反应堆压力容器断裂力学分析中弹塑性有限元方法与工程方法的比较
Analysis of Effect of Design Transients and Fatigue Damage on RPV Design Life
设计瞬态和疲劳损伤对反应堆压力容器设计寿命的影响分析
Design of Reactor Pressure Vessel for Qinshan Phase II NPP Project
秦山核电二期工程反应堆压力容器设计
3-D Transient Coupled Sealing Analysis for the Model of Reactor Pressure Vessel;
反应堆压力容器模拟体三维瞬态耦合密封分析
Sealing Analysis under Cooling and Heating Cycle for Reactor Pressure Vessel in Nuclear Power Station;
核电站反应堆压力容器冷热态密封分析
The Large Item Transport Program Design of the Pressure Container for the Nuclear Reactor Pile;
核反应堆压力容器的大件运输方案设计
Quality Control of Hot-working Process for Large-sized Forging Reactor Pressure Vessel
反应堆压力容器大型锻件热加工质量控制研究
Technical improvement for installation of the insulating layer of CPR1000 reactor pressure vessel
CPR1000核反应堆压力容器保温层安装技术改进
Fracture Mechanics Analysis of Flaw in Outlet Nozzle of RPV
反应堆压力容器出口接管管嘴缺陷断裂力学分析
The Application of UT Simulation Technique in the Ultrasonic Testing of Reactor Pressure Vessel
超声仿真技术在反应堆压力容器超声检查中的应用
Analysis of Corrosion on Flange Surface of RPV for NPP
核电站反应堆压力容器法兰密封面腐蚀机理的分析
The Development of 3-D Transient Sealing Analysis Program System for the New Type Reactor Pressure Vessel;
新型反应堆压力容器三维瞬态密封分析程序系统研制
Research on the Defect Evaluation of Tianwan Nuclear Power Plant Reactor Pressure Vessel
关于田湾核电站反应堆压力容器缺陷评价的研究
Numerical Simulation on Forging Process for Integrated Head of RPV
反应堆压力容器整体法兰封头锻造工艺数值模拟
Prediction Model on Irradiation Embitterment of Low Copper Alloy Reactor Pressure Vessel Steels
低铜合金反应堆压力容器钢辐照脆化预测评估模型
Liquid collapse level monitoring for nuclear reactors during loss of coolant accident
核反应堆压力容器小破口事故中坍塌液位的测量
Analysis of Effect of Design Transients and Fatigue Damage on RPV Design Life
设计瞬态和疲劳损伤对反应堆压力容器设计寿命的影响分析
Probability Analysis for External Reactor Vessel Cooling Effectiveness under Severe Accident
严重事故下反应堆压力容器外水冷有效性概率分析
Study of the Effect of Stress on phase TransformationKinetics and phase Transformation Plasticity with RPV Steel
应力对核反应堆压力容器大型锻件用钢相变动力学和相变塑性影响的研究
Comparison of Elastic-Plastic FE Method and Engineering Method for RPV Fracture Mechanics Analysis
反应堆压力容器断裂力学分析中弹塑性有限元方法与工程方法的比较