非能动安全系统

非能动安全系统和减少核电厂建造初投资是AC-600设计的重点。本文介绍了有关非能动安全系统的设计特点和安全功能，同时对AC-60C的经济性能也做了初步分析。

The passive safety systems and nuclear power plant capital cost reduction are planned to be two major design emphases for AC-600.This paper introduces the design characteristics and safety functions of passive safety systems and discusses the economic benefit of AC-600 as well .

AC-600非能动安全系统设计

Passive Safety System Design for AC-600

实验研究表明：三大非能动安全系统的设计是合理、可行的，基本能满足其赋与的功能要求。

These experiments proved the design of these passive systems are feasible and reliable and can meet basically the required safety functions .

以核电厂事故为例叙述了核电厂安全运行对策研究的重要性；介绍了代表新一代先进反应堆的非能动安全系统设计原则和针对人因差错应采取的管理和培训对策。

The passive safety system design principles for new generation advanced reactor are suggested , The management for administration and training is suggested to be adopted for preventing human error .

含有不凝性气体的蒸汽冷凝是先进反应堆非能动安全壳冷却系统（PCCS）中重要的换热方式，是当前核反应堆热工水力学研究的一个热点。

Condensation of steam in the presence of noncondensable gases is an important heat transfer mode in the passive containment cooling system ( PCCS ) .

本文对安全壳进行长期效应的分析结果表明，AC600非能动安全壳冷却系统能够保证安全壳的完整性。

This paper gets the conclusion that the PCCS can ensure the integrality of the AC600 containment in the long-term .

非能动安全壳冷却系统水分配装置设计

Design of Water Distribution Device for Passive Containment Cooling System

用人工神经网络方法进行非能动安全壳冷却系统可靠性分析

Reliability quantification of PCCS through artificial neural network algorithm

本文介绍在模拟实际非能动安全壳冷却系统及接近实际安全壳分隔区域尺寸的条件下，大型矩形腔体中由强迫射流所造成的速度场和热分层现象。

This paper introduces the investigation of velocity field induced by forced jets and thermal stratification in a large rectangular enclosure , at conditions simulating those of actual passive containment cooling systems and scales approaching those of actual containment buildings or compartments .

非能动余热排出换热器是非能动安全系统中的一个重要设备，担负着事故工况下导出堆芯余热，保证反应堆安全的重任。

The passive residual heat removal heat exchanger is an important device in the passive safety system , which charged with the important task of removing core decay heat during the accident operating conditions to ensure the safety of reactor .

AC600二次侧非能动应急堆芯余热排出系统实验装置是一座大型非能动安全系统实验研究装置。

The secondary side passive emergency Core residual heat removal system ( ECRHR System ) test facility is a large scale passive safety system experimental test rig , which is designed base on the thermal hydraulic simulating theory and criteria .