反应堆压力容器

反应堆压力容器出口接管管嘴缺陷断裂力学分析

Fracture Mechanics Analysis of Flaw in Outlet Nozzle of RPV

受压热冲击下反应堆压力容器内流动和传热研究综述

Summary of Flow and Heat Transfer in RPV under PTS

W型试样在核反应堆压力容器用材料的断裂韧度测试中具有良好的应用前景。

The W-type specimen has a well prospective application in the measurement of fracture toughness of the materials which are used in the nuclear reactor .

HTR-10反应堆压力容器筒体纵缝成形性能试验

Property Test for Shell Longitudinal Weld Shaping of HTR-10 Reactor Pressure Vessel

10MW高温气冷堆反应堆压力容器的出厂水压试验

Hydraulic Pressure Test of Pressure Vessel of 10 MW High Temperature Gas-cooled Reactor

10MW高温气冷实验堆反应堆压力容器热电偶贯穿件

Thermocouple Penetration Assemblies for Pressure Vessel of 10MW High Temperature Gas - Cooled Reactor

AC-600反应堆压力容器设计探讨

An Approach to the Reactor Pressure Vessel Design for AC-600

简要叙述了中国核动力研究设计院进行的核岛专用检修设备的研制工作，描述了反应堆压力容器（RPV）螺栓孔与螺栓连接件的检修工艺流程。

This paper briefly introduces the design and manufacture of nuclear island special servicing equipment of Nuclear Power Institute of China .

介绍了10MW高温气冷实验堆反应堆压力容器的结构特征和主要技术参数。

This paper introduces the structure characteristics and main designing technical parameters of the pressure vessel of Tsinghua University 10MW high temperature gas cooling reactor .

并以HTR-10反应堆压力容器为例，根据设计和制造中的具体情况，分析了可接受的形状偏差限值。

As an example of HTR - 10 's reactor pressure vessel , acceptable criteria of the shape error are discussed by the actual conditions during the design and manufacture .

Marc软件，对反应堆压力容器双道金属O形密封环进行弹塑性大应变接触分析，给出在不同压紧量下的回弹量，并与试验结果进行比较。

In this paper the elastoplastic contact analysis for O-ring of reactor pressure vessel was carried out using MSC . Marc software . The different spring-backs under the different tightening conditions were obtained and compared with the previous tests .

反应堆压力容器（RPV）是核电站中的重要构件，由于制造工艺的限制以及运行工况的影响，核电站的整个服役周期内RPV上可能会存在裂纹类缺陷。

Reactor pressure vessel ( RPV ) is an important component in nuclear power plants , the crack-like defects may exist in RPV during the whole operation life of nuclear power plants as a result of the manufacturing process or the operation condition .

承压热冲击下反应堆压力容器中流体的瞬态混合特性

Transient Mixing Characteristic of Reactor Pressure Vessel under Pressurized Thermal Shock

反应堆压力容器定位键安装技术研究

Technical Research about Assembly of Positioning key on Reactor Pressure Vessels

反应堆压力容器密封螺栓，超声检测。

Reactor Pressure Vessel , Closure Studs , Ultrasonic Examination Method .

反应堆压力容器下封头三维流场计算

Three Dimensional Numerical Simulation in Lower Header of Reactor Pressure Vessel

严重事故下反应堆压力容器外水冷有效性概率分析

Probability Analysis for External Reactor Vessel Cooling Effectiveness under Severe Accident

反应堆压力容器大型锻件热加工质量控制研究

Quality Control of Hot-working Process for Large-sized Forging Reactor Pressure Vessel

先进压水堆反应堆压力容器面临的脆化问题

The embrittlement encountered in the reactor pressure vessel of the advanced PWR

反应堆压力容器金属O形环密封性能研究

Sealing Behaviour Research on Metal O-ring of Reactor Pressure Vessel

反应堆压力容器中子辐照损伤的分析和评价

The Analyses and Evaluation of Neutron Irradiation Damage for Reactor Pressure Vessel

反应堆压力容器螺栓孔与螺栓连接件专用检修设备

Special Servicing Equipment for Reactor Pressurized Vessel Stud Hole and Stud Accessories

核电站反应堆压力容器法兰密封面腐蚀机理的分析

Analysis of Corrosion on Flange Surface of RPV for NPP

带拐角裂纹的反应堆压力容器接管的安全分析

Fracture Safety Analysis of RPV Nozzle with a Corner Crack in PWR

核反应堆压力容器小破口事故中坍塌液位的测量

Liquid collapse level monitoring for nuclear reactors during loss of coolant accident

反应堆压力容器整体法兰封头锻造工艺数值模拟

Numerical Simulation on Forging Process for Integrated Head of RPV

反应堆压力容器的变形和应力分析

The Analysis of Deformations and Stresses in Pressurized Vessel for a Nuclear Reactor

核反应堆压力容器的应力分析和评定

Stress analysis and evaluation of nuclear reactor pressure vessels

反应堆压力容器堆芯支承块镶块钴基合金堆焊试验研究

Test Investigation of Overlaying Pressure Vessel Component on Nuclear Reactor by Cobalt-Based Alloy

反应堆压力容器螺栓孔螺纹润滑设备的设计

Design of Lubricating Equipment of Stud Hole ′ sThreads of Reactor Pressure Vessel