重水堆

结果表明，重水堆用锆管超声波探伤试块中，用U形人工缺陷取代V形人工缺陷是可行的。

The result showed it was reasonable to use U shape notch to replace V shape notch in test blocks for ultrasonic testing of zirconium tube applied in Candu reactor .

重水堆~3H排放量控制值的建议

Control level recommendations for ~ 3H discharge of PHWR

重水堆核电站~（14）C的产生、释放和控制措施

Production , release and control measures of ~ ( 14 ) c in heavy water reactor

Krylov子空间方法及先进重水堆在线通量拟构方法初步研究

Study on Krylov Subspace Method and the Flux Mapping for Advanced Candu Reactor

MOX燃料在CANDU重水堆中应用可行性的研究

Feasibility Study on Application of MOX Fuel in a CANDU Reactor

CANDU型重水堆核电站综述

Survey of CANDU Nuclear Power Station

综述了CANDU型重水堆核电站的运行业绩、结构和安全性分析。

This paper summarizes the performance of CANDU nuclear power station , its structure and safety analysis .

CANDU重水堆燃料管理

Fuel Management of CANDU Reactor

重水堆核电站用CANDU-6型燃料棒束的制造工艺

Manufacturing process of CANDU-6 fuel Bundle for HWR nuclear power station

介绍重水堆停堆系统上可编程数字比较器（PDC）的软硬件的组成，PDC对停堆参数的运算、逻辑控制、自检和PDC调试经验等，及其PDC故障诊断系统的具体应用。

This article introduce Programmer Digital Comparator ( PDC ) hardware and software , PDC calculation and logic control for shutdown system , software self - check , PDC commissioning experience , Maintenance and Diagnosis ( MAD ) System application .

加拿大根据其基本国情在特殊的历史条件下开发了压力管式重水堆（PHWR）核电技术。

Canada , in accordance with its basic national conditions in the history is developing nuclear power technology of heavy water pressure tubular reactor ( PHWR ) .

重水堆大修期间的核安全要求及管理

Nuclear Safety Requirements during Planned Outage of Heavy Water NPP

CANDU6型重水堆机组的最大的两个特点就是：一是重水作为中子慢化剂和一回路的冷却剂；

It has two characteristic : 1 . heavy water & as moderator and coolant ;

重水堆停堆系统中数据采集系统的设计与应用

The Design and Application of Data Acquisitioning System in Reactor Shutdown System of Heavy Water Reactor

碳正离子的稳定性和反应性热态反应性实时监测及重水堆光激中子本底源的确定

Hot-state reactivity real-time monitoring and the determination of photoneutron background source in heavy water research reactor

此外，我们还从对正常运行状态下的实时反应性值的统计分析得到了光激中子源本底的大小，为确定重水堆光激中子源大小提供了一个新的方法。

A new method is provided for the determination of the photoneutron background source in Heavy Water Reactor .

轻/重水堆中子辐照氢区熔硅退火特性的比较

Annealing Characteristic Comparison of NTD FZ ( H ) Si Irradiated in Light water reactor and Heavy water reactor

重水堆核电站核反应堆筒体滑模施工技术

Technology for Construction of Tube shape Wall of Nuclear Reactor Container of Nuclear Power Plant with Heavy water moderated Reactor with Slipforms

并对如何使用此再制的核燃料提出两种方案，分别适用于压水堆和以天然铀为燃料的坎杜重水堆。

Scheme B in the article , i.e. a method of using the rebuilt used fuel from PWR to replace the natural uranium fuel for HWR , was discussed .

秦山三期重水堆工程厂区土石方开挖为两座与秦山相连的山体，华湘公司承担该项工程任务。

The earth and rock excavation of the plant area of the3rd heavy water reactor project of Qinshan nuclear power plant was of two hill-bodies linked up with Qinshan hill and Huaxiang Co.

比较了核电机组与火电机组再热系统的不同特性，阐述了重水堆核电机组汽水分离再热器系统的流程和控制。

In this paper , the reheater difference between nuclear power plant and coal-firing power plant was given , and the MSR system 's craft and control for nuclear power plant was also discussed .

说明了重水堆核电站氚生成的途径，核电站设计中控制氚向环境释放的措施以及排放到环境中的氚对居民所致的剂量等公众关注的问题。

The issues drawing people 's attention , such as ways of CANDU plant tritium generation , measures to control tritium release to environment in the design of nuclear power plants as well as public dose due to tritium released to the environment are presented .

重水零功率堆上的初始转换比测量

Determination of initial conversion ratio on heavy water zero power reactor

高浓铀重水零功率堆中子温度和超热指标的测定

Measurements of neutron temperature and epithermal index in high enriched uranium heavy water zero power reactor

脉冲中子源方法及其在低浓铀重水零功率堆上的应用

The pulsed neutron technique and its application in heavy-water zero power reactor with low enriched uranium fuel