reactor pressure vessel

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

HTR-10反应堆压力容器筒体纵缝成形性能试验

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

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

反应堆压力容器中子辐照损伤的分析和评价

Aging Analysis of Reactor Pressure Vessel for Unit 2 of DAYA Bay Nuclear Power Station

大亚湾核电站2号机组反应堆压力容器老化现状的初步分析

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

Three Dimensional Numerical Simulation in Lower Header of Reactor Pressure Vessel

反应堆压力容器下封头三维流场计算

The guts of the reactor have to be hauled out of the pressure vessel.

核反应堆的核心构件必须从压力罩中取出来。

The operating limit of water reactor pressure vessel

水堆压力容器运行限制

The analyzed result shows that in interested area, both the partial pressure of incondensable gas in RPV ( reactor pressure vessel) and the diameter of injection pipe are the main factors influencing on boron-injecting velocity.

分析结果说明：在所关心的范围内，反应堆压力容器内不凝结气体的分压力和注硼管直径的影响最大。

Therefore, an increased demand for reliable sealing analysis for reactor pressure vessel is recognized.

为此需要对反应堆压力容器进行可靠的密封分析。

Research and measurement on dynamic fracture toughness for nuclear reactor pressure vessel steels

核压力容器钢辐照后动态断裂韧性测试及研究

Pressurized Thermal Shock Analysis for Reactor Pressure Vessel

反应堆压力容器承压热冲击分析

Experimental investigation of radiation embrittlement effects of low copper reactor pressure vessel steels

低铜压力容器钢辐照脆化效应实验研究

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

反应堆压力容器金属O形环密封性能研究

Transient Mixing Characteristic of Reactor Pressure Vessel under Pressurized Thermal Shock

承压热冲击下反应堆压力容器中流体的瞬态混合特性

3-D Transient Analysis for Flange Sealing System in Reactor Pressure Vessel of Power Station

某电站核容器法兰三维瞬态密封分析

NPP Site Measurement Research for Reactor Pressure Vessel

反应堆压力容器现场测试研究

Reliability Analysis of the Reactor Pressure Vessel

核反应堆压力容器可靠性分析

Transfer of technology in China for nuclear reactor pressure vessel internals manufacturing

在中国对核反应堆高压容器内部零件生产制造技术转让

Brittle Fracture of Water Reactor Pressure Vessel& Criteria, Standard and its Use

水堆压力容器的脆性断裂&准则、标准及其应用

Positioning of Moving Table for Checking Screw Holes of Nuclear Reactor Pressure Vessel

核反应堆压力壳螺栓孔检测自动小车的定位

Reactor Pressure Vessel, Closure Studs, Ultrasonic Examination Method.

反应堆压力容器密封螺栓，超声检测。

Operating Limitary Pressure and Calculative Method of Water Reactor Pressure Vessel

水堆压力容器运行限制压力的计算方法

Numerical Sealing Analysis for Sealing System in Reactor Pressure Vessel Flanges

核容器法兰密封系统密封性能数值分析

The Microstructure of Reactor Pressure Vessel Steel for Nuclear Power Plant and its Effect on Properties

核电站反应堆压力容器用钢的显微组织及其对性能的影响

Research and application of the first nuclear reactor pressure vessel inspection machine of China

我国首台核反应堆压力容器检查机研制及应用

The reactor vessel constitutes the main part of pressure boundary of primary coolant.

反应堆压力壳构成了主冷却剂压力边界的主体。

Based on the code, the code system for streaming calculation was constituted and was used for calculating neutron streaming through the thermal insulator annular gap of actual reactor pressure vessel.

以它为主体，建立了辐射泄漏计算程序系统，并运用该系统进行了反应堆压力容器绝热层缝中子泄漏计算研究。

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

AC-600反应堆压力容器设计探讨

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

10MW高温气冷堆反应堆压力容器的出厂水压试验