反应堆冷却剂系统

建模与仿真的范围是：反应堆冷却剂系统（RCP）、与安全分析相关的一回路辅助系统。

The range of modeling and simulation are : the reactor coolant system ( RCP ) and the auxiliary systems relative to security analysis .

冷却系统中没有冷却剂。上充／补给水流量〔反应堆冷却剂系统〕

No refrigerant in the refrigerant system . charging / make-up flow [ reactor coolant system ]

主循环泵机组是CARR反应堆冷却剂系统中的主要设备。

The Main circulating pumps are the most important equipments of Reactor Cooling System ( RCS ) of China Advanced Research Reactor ( CARR ) .

AC&600反应堆冷却剂系统及其主要辅助系统的设计特点

Design Features of RCS and Major Auxiliary Systems for AC-600

反应堆冷却剂系统剂量当量

Reactor coolant system dose equivalent

还有反应堆冷却剂系统焊接问题，它们使用了并且得到原生水，应力腐蚀裂痕。

There are reactor coolant system weld issues , they 're used and they 're getting primary water stress corrosion cracking .

接着，建立了反应堆冷却剂系统的实时仿真模型，包括了完整的热工水力模型完成对冷却剂系统物理过程的模拟。

Then the numerical models of the coolant system are established . The procedure contains integrated the thermal-hydraulic models , pump model and some special models .

压水堆核电厂反应堆冷却剂系统自然循环能力是这种类型核电厂固有的安全性之一。

The natural circulation ability of PWR ( pressurized water reactor ) coolant system is one of inherent safeties of this kind NPP ( nuclear power plant ) .

对安装有密度锁的反应堆冷却剂系统进行了流动分析，根据流体运动方程和系统的循环流动特性，说明了密度锁的作用和具有的特性。

Based on the motion equation and flow circulation in the system , the flow analysis to reactor coolant system with density locks is given ; the action and characteristics of density locks are explained .

压水堆核电厂在更换燃料和对反应堆冷却剂系统进行维修和检查的冷态停堆期间需要降低反应堆冷却剂系统的水位，并在某一段时间内降低到迥路管道内。

In a PWR nuclea γ power plant , refueling or various maintenance and inspection activities being performed on the reactor coolant system ( RCS ), it requires the coolant level in the RCS to be lowered into the loop piping ( midloop ) .

在实时仿真支撑平台ASCA下对反应堆主冷却剂系统进行了建模、编程和计算。

Under the real-time simulation support system ASCA , a reactor coolant system is modeled , programmed and computed .

对反应堆主冷却剂系统实时仿真进行了研究。

The real-time simulation of reactor coolant system is studied in the paper .

反应堆主冷却剂系统实时仿真计算

Real-Time Simulation Calculation of Reactor Coolant System

本文简要介绍了核动力反应堆冷却剂循环系统电机的结构、性能及在开发过程中的技术问题。

Structure and performance of a motor used in refrigerant circulating system of nuclear-powered reactor , and technical question in its studying is briefly introduced in this paper .

中国先进研究堆二次冷却水系统的功能是将反应堆冷却剂等系统中的热量传输给最终热阱。

The function of the secondary cooling water system of China Advanced Research Reactor is to transmit the heat of systems , such as coolant system , to the final heat sink .

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 .

在对核反应堆堆芯冷却剂系统分析的基础上，建立了海洋条件下冷却剂系统自然循环运行状态仿真模拟的数学模型。

Mathematical simulation model of nuclear reactor coolant system under ocean conditios is constructed in system analysis .

本文总结了秦山核电二期工程反应堆及反应堆冷却剂系统仪表和控制的设计、重要仪表控制设备的研制。

This paper summaries the I & C designs and the development of the key instrumentation for the reactor and coolant system of Qinshan Phase II NPP .

本文依据不同的防护准则，对核电站反应堆主冷却剂环路系统抗破裂设计问题进行了分析。

According to the different criteria for the protection against postulated pipe break effects , + the problems concerning the design of the primary reactor coolant loop systems of the PWR plants are analyzed in this paper .

反应堆冷却剂泵转速测量系统改进设计及实践

Improvement and practice of speed measurement system for reactor coolant pump

秦山核电二期工程与大亚湾核电站相比，反应堆功率下降，冷却剂系统三环路变为两环路。

Compared with that of Daya Bay Nuclear Power Plant , the reactor power of QS-II Nuclear Power Plant is decreased and the primary coolant system is changed from three loops to two loops .

重水慢化气冷反应堆上充／补给水流量〔反应堆冷却剂系统〕

Heavy-water-moderated gas-cooled reactor charging / make-up flow [ reactor coolant system ]