中国核动力研究设计院

中国核动力研究设计院

The Studies of the New Type Steam-box Nuclear Power Institute of China

SCAS是中国核动力研究设计院编制的反应堆二回路蒸汽活化产物源项程序。

SCAS is the source term code to calculate steam activation products in secondary loop of reactor , which is developed by Nuclear Power Institute of China .

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 .

中国核动力研究设计院（NPIC）承担了反应堆及反应堆冷却剂系统及相关的控制、保护、仪控系统的设计与技术服务任务，并承担有关的设计验证工作。

Nuclear Power Institute of China is responsible for the design and technical service of the reactor and reactor coolant system , and relative control , protection , and instrumentation systems , as well as the design qualifications .

中国核动力研究设计院研究堆燃料元件的发展现状

Development of Fuel Element for Research Reactor in Nuclear Power Institute of China

目前，中国核动力研究设计院承担的核电机组的堆芯换料设计均引进法国先进的软件包。

At present , the code package used for nuclear power unit reload design by Nuclear Power Institute of China is from France .

在先进压水堆预研项目中，中国核动力研究设计院研制出了数字化反应堆控制系统原理样机。该产品样机研成后经运行试验表明设计是成功的。

The Prototype Digital Control System for Advanced Reactor is produced by NPIC . A performance test of the advanced development shows the design is successful .