candu

candu

1. Installation Modes for Major Equipment of CANDU 6 Nuclear Power Plant Reactor Buildings

6核电站反应堆厂房主设备安装模式

2. CANDU 6 Nuclear Power Plant Reactor Physical Startup

6核电站反应堆物理启动

3. CANDU 6 Nuclear Power Plant Tritium Control and Release

6核电站氚的控制和排放

4. Heavy Water Management for CANDU 6 Units

CANDU 6机组重水管理

5. The Canada Deuterium Uranium (CANDU) is one of the very few reactor types which have successfully reached full maturity in the world.

CANDU 堆是世界上达到充分成熟且成功发展的少数几种堆型之一。

6. CANDU fuel management has both design and operations aspects.

CANDU 堆燃料管理有设计和运行两方面的内容。

7. Thereare many differences between CANDU and a pressurized water reactor instructure.

CANDU 堆相比一般的压水堆在设计上有显著的区别。

8. Physical startup and physical commissioning test of CANDU 6 during commissioning are primarily performed at Phases B and C, and critical monitoring after fuel loading at PHASE A is also included.

CANDU6堆调试期间的物理启动和物理调试试验主要在B阶段和C阶段进行，同时也包括A阶段的堆芯装料后的临界监督。

9. Study of Delayed Hydride Cracking In CANDU and RBMK Pressure Tubes

CANDU及RBMK压力管锆合金的氢致延迟断裂研究

10. Physics Codes and Methods for CANDU Reactor

CANDU反应堆物理程序和方法

11. Survey of CANDU Nuclear Power Station

CANDU型重水堆核电站综述

12. CANDU reactor

CANDU堆

13. Analysis of the precise control mechanism of CANDU reactor power

CANDU堆功率的精细控制机理分析

14. Development of CANDU

CANDU堆发展的回溯与展望

15. Study of RU Utilization in CANDU Reactor- an Advanced Nuclear Fuel Cycle of PWR/CANDU Synergism

CANDU堆应用RU的PWR/CANDU联合核燃料循环的研究

16. Analysis and Study of Severe Accidents in CANDU Nuclear Power Plant

CANDU堆核电厂严重事故分析研究

17. Thermalhydraulic Design Methods and Computer Codesfor CANDU Reactor

CANDU堆热工水力设计方法和计算机软件

18. Coupling of Neutronics and Thermal-Hydraulic of CANDU Fuel Management Program and Modification of Time-averaged Model

CANDU堆燃料管理程序的物理热工水力耦合和时均计算模型的改进

19. Application of Fuel Management Calculation Codes for CANDU Reactor

CANDU堆燃料管理计算软件的应用研究

20. CANDU NPP

CANDU核电厂

21. Characteristics and development of CANDU NPP unit

CANDU核电机组的特点与发展

22. Fuel Management of CANDU Reactor

CANDU重水堆燃料管理

23. Feasibility Study on Application of MOX Fuel in a CANDU Reactor

MOX燃料在CANDU重水堆中应用可行性的研究

24. TACR (Thorium Based Advanced CANDU Reactor)

TACR

25. XIE Zhongsheng.Study of advanced in core fuel management strategy for PWR and CANDU nuclear power plants[J].Nucl Power Eng,2000,21(1):56-62(in Chinese).

[2]谢仲生.关于PWR及CANDU堆先进燃料管理策略的研究[J].核动力工程,2000,21(1):56-62.

26. In this article it is discussed the nuclear safety requirements and the basis of the requirements,and the background of making these nuclear safety requirements from the point of view of CANDU planned outage nuclear safety management.

主要是从CANDU堆停堆大修期间的核安全管理方面论述CANDU大修期间的核安全要求及依据以及制定这些核安全要求的背景。

27. In this paper the natural uranium fuel Cycle and currently developed advanced CANDU fuel cycles in the near future are described.

介绍CANDU 堆的天然铀燃料循环以及最近开发的适合未来近期的先进燃料循环。

28. The process of CANDU NPP severe accident is introduced, and then CANDU NPP severe accident and Qinshan Phase Three NPP level one PSA made by AECL are analyzed.

介绍了CANDU堆核电厂的严重事故过程、AECL对CANDU严重事故进行的分析研究和对秦山三期核电厂进行的较为详细的核电厂一级PSA分析。

29. Numerical Study of Advanced CANDU Reactor Moderator Fluid Field and Temperature Field

先进CANDU型反应堆慢化剂流场和温度场的数值研究

30. Advanced CANDU reactor

先进CANDU堆

31. The content includes the introduction of the program of"nuclear safety requirements during planned outage (of TQNPP)",the existed nuclear safety risk of planned outage of CANDU units and the measures of treatments,etc.

其内容包括对停堆大修核安全要求这个管理程序的介绍,CANDU堆大修期间存在的核安全风险及应对措施等。

32. The results show that the CANDU NPP is with good capability to withstand severe accident, and that the core damage frequency of Qinshan Phase Three NPP meets the objective limit used in the world and China.

分析结果表明,在对抗严重事故方面CANDU堆有着优良的特性,秦山三期堆芯严重损坏概率满足我国和国际通常的目标限值。

33. Candu pressurized heavy water cooled

加拿大重水慢化加压重水冷却反应堆

34. Under normal circumstances a dead end about a week, Candu will lose money in cash or bank accounts forms to the respective agents Exchange, gambling winners through agents pay money in the same way.

各级代理均组织参赌者通过互联网进行赌球，每场赌资几百元至数万元不等。

35. The fuel cycle model is one of the most important problem in the concept design of Thorium Advanced CANDU Reactor(TACR).

在钍基先进CANDU堆的概念设计中,钍燃料的循环利用方式是一重要问题。

36. Earthing System Design of CANDU Type Nuclear Generating Station

坎杜型核电站接地系统设计

37. This paper describes main type of CANDU steam generators,including Pickering A,Pickering B,Bruce A,Bruce B ,Gentillg 2,Darlington steam generators.

坎杜堆蒸汽发生器的主要型号有：皮克灵A、皮克灵B、布鲁斯A、布鲁斯B、根蒂莱2和达灵顿核电站的蒸汽发生器。

38. Summarization of CANDU Steam Generator Design

坎杜堆蒸汽发生器设计综述

39. Current safety issues of CANDU licensing

坎杜审批的通行安全问题

40. Support analysis for safety analysis development for CANDU nuclear power plant

坎杜核电厂安全分析发展的支持分析

41. An analytical assessment of the longitudinal ridging of CANDU type fuel element CANDU

型燃料元件纵向隆脊的分析评价

42. Integrity of spent CANDU fuel during and following dry storage CANDU

堆乏燃料在干法贮存期间的完整性

43. Multi-group lattice code WIMS-AECL has strong modeling capability for clustergeometry and isotopic composition, so it has been used for the design and analysis ofthe advanced CANDU reactors (ACR).

多群栅元程序WIMS-AECL对棒束几何结构和材料成分具有很强的建模能力,被指定用于先进CANDU堆(ACR)的设计和分析。

44. It can be used in the fuel management calculation of CANDU reactors.

它完全可以用于CANDU堆燃料管理计算。

45. Its CANDU reactors were once thought superior because they could be refuelled without shutting down.

它的重水铀反应堆可以在不关闭的情况下进行燃料补给，一度被认为世界领先。

46. The feasibility and economy of the application of reprocessed uranium(RU) from spent PWR fuel in CANDU reactor of Qinshan Phase III NPP were studied.

对压水堆乏燃料后处理回收铀(RU)在秦山三期CANDU堆中应用的可行性和经济性进行分析。

47. The feasibility of application of slightly enriched uranium (SEU) in CANDU reactor of Qinshan Phase III NPP under the time-averaged equilibrium refueling was studied in this paper using the code system DRAGON/DONJON.

对秦山三期CANDU堆应用稍浓铀的可行性用DRAGON/DONJON程序做了时均堆芯研究分析。

48. In this paper, the moderator fluid field and temperature field of three moderator circulation designs for advanced CANDU reactors (ACR,TANES) has been numerically simulated by applicable nu merical procedure.

应用数值方法对先进CANDU型反应堆(ACR、TANES等)慢化剂冷却系统的3个慢化剂回路方案的流场和温度场进行了数值模拟。

49. In this paper, the moderator fluid field and temperature field of three moderator circulation designs for advanced CANDU reactors( ACR, TANES) has been numerically simulated by applicable nu merical procedure.

应用数值方法对先进CANDU型反应堆(CR、ANES等)化剂冷却系统的3个慢化剂回路方案的流场和温度场进行了数值模拟。

50. The paper presents a design of passive heat-switch between pressure tube and calandria tube of Thorium-based Advanced CANDU Reactor(TACR).

提出了一种可应用于钍基先进CANDU型反应堆(TACR:Thorium-based Advanced CANDU Reactor)压力管与排管间的非能动热开关设计方案。

51. Based on the existing pressurized water reactors(PWR) and Canada deuterium uranium (CANDU) reactors in China, one advanced nuclear fuel cycle strategy of PWR/CANDU synergism was proposed.

摘要根据我国已拥有压水堆(PWR)和坎杜(CANDU)堆的具体情况，提出一种PWR/CANDU联合核燃料循环的策略。

52. At last, the advanced nuclear fuel cycles used in Qinshan Phase III CANDU nuclear power plant were studied and two strategies were proposed in this paper.

最后，本文对秦山三期核电厂CANDU堆的核燃料循环进行了研究，提出二个重大的改进方案。

53. This paper describes the heat transport system to be installed in the Qinshan CANDU nuclear power plant.

本文介绍正在建设的秦山三期CANDU 核电厂的热传输系统

54. This paper describes the site conditions,configuration and operating characteristics of the CANDU 6 nuclear power plant now being built at the Qinshan site in China.

本文简单介绍正在建设的秦山三期CANDU 核电厂的厂址条件、设计和运行特征。

55. Firstly, the WIMS-D4、WIMS-AECL、DRAGON and DONJON codes for physics design and analysis of CANDU reactor are studied and validated.

本文首先对CANDU反应堆物理设计和分析计算所用的基本程序WIMS-D4、WIMS-AECL、DRAGON以及DONJON进行了计算研究和验证。

56. In this thesis, a steady-state thermalhydraulic scheme for Thorium basedAdvanced CANDU Reactor (TACR) core has been designed, and has been evaluatedusing the thermal hydraulic code CATHENA.

本论文为钍基先进CANDU反应堆(TACR)的堆芯稳态热工水力设计,并用反应堆热工水力分析程序CATHENA进行分析评价。

57. In this thesis, a new concept with passive moderator system for TACR isdesigned, and is assessed through analyzing a loss of coolant flow accident(LOFA)by CATHENA Mod3.5c/Rev1, a thermalhydraulic computer codedeveloped by AECL for CANDU.

本论文为钍基先进坎杜堆(TACR)满足非能动安全要求的慢化剂系统进行概念设计,并用热工水力分析程序 CATHENA Mod3.5c/Rev1 分析反应堆在全厂断电情况下的失流事故,以评价所设计的系统。

58. The calculation of the CANDU (CANada Deuterium Uranium) in-core fuel management is described in this thesis.

本论文对秦山三期CANDU（CANada Deuterium Uranium）型反应堆堆内燃料管理计算进行了研究，并研制了适用于秦山三期CANDU型反应堆燃料管理计算的软件包。

59. Estimation of internal exposure for exposed personnel from a Candu nuclear fuel factory CANDU

核燃料厂受照人员的体内照射评价

60. These generators which have evolved out of the years of operating experience in CANDU.

根据坎杜堆多年的运行经验，其蒸汽发生器设计经历了多次改进。

61. Thirdly, application of MOX fuel in CANDU reactor is studied and appropriate fuel composition is chosen.

然后，本文进行了MOX燃料在CANDU重水堆中应用可行性研究，并优选出燃料的成分。

62. This work,using WIMS-AECL,MCNP-4B and MCBurn codes,has calculated the criticality and burnup problems of a series of benchmarks and advanced CANDU lattices,including all-uranium and thorium-based fuels.

用WIMS-AECL程序和MCNP-4B及MCBurn程序对一系列基准例题和先进CANDU堆全铀、含钍组件进行临界和燃耗计算。

63. Because of the inherent flexibility of nuclear fuel cycle in CANDU reactor, the transition from the nature uranium to the recycled uranium(RU) can be completed without any changes of the structure of reactor core and operation mode.

由于CANDU堆对核燃料循环的固有灵活性 ,堆芯结构及运行方式不需作重大改变 ,即可完成从天然铀到RU的过渡。

64. The optimum enrichment of Qinshan CANDU reactor was determined to be 1.125wt%.

确定秦山三期采用稍浓铀的最优富集度为1.125wt%。

65. Improvements on Main Control Rooms of Qinshan CANDU 6 Units

秦山CANDU 6机组主控制室改进

66. CANDU 6 Units Fuel Handling System

秦山三期CANDU 6机组的燃料操作系统

67. The first of the CANDU 6 series entered commercial service in 1983.The initial design of CANDU 6 was derived as a single unit version of the successful Pickering A station in Ontario,an integrated four unit plant operated by Ontario Hydro.

第一台CANDU?6 机组于1983 年投入商业运行。 CANDU?6 的初始设计源于很成功的皮克灵A 核电厂的单机化版本。

68. First, the establishment of a special magistrate to accept reflect the Candu and the suspect matches the authenticity of the hotline;

第一，设立一个专门接受反映裁判参赌和怀疑比赛真实性的热线；

69. Police identified one of the accounts involved in the case since January 2008 to June from a total of five sites involved in collecting funds bet Candu's 1929 yuan.

警方现已查明，其中一个涉案账户自2008年1月至6月共从五个涉案网站收取参赌人的下注资金1929万余元。

70. They believe that demand will rise not just for medical isotopes but also for Canada's CANDU reactors, which use a different technology from many elsewhere.

评论家们认为需求增加的原因并不仅仅是医用同位素，还有加拿大坎杜型反应堆，它需要利用很多其他地方的不同技术。

71. Qinshan CANDU nuclear fuel handling system is described in detail.

详述了秦山CANDU堆燃料操作系统，包括新燃料贮存和运输系统、乏燃料贮存和运输系统、燃料更换系统以及远距离观测摄像机。

72. These differences bring some advantages for CANDU in reactorsafety and security.

这些特点也给它带来了安全方面的诸多优势。

73. Application of Genetic Algorithm in CANDU Reactor In-core Fuel Management

遗传算法在CANDU堆燃料管理中应用的研究

74. CANDU nuclear power plant

重水堆核电站

75. CSDVS fail open event analysis and handling measure of CANDU nuclear power plant

重水堆核电站主蒸汽旁排阀故障分析和应对策略

76. Thorium Based Advanced CANDU Reactor

钍基先进CANDU堆

77. Research on Power Effect of Th-U Fuel on TACR (Thorium Based Advanced CANDU Reactor)

钍基先进CANDU堆(TACR)钍-铀燃料功率影响研究

78. Research on Fuel Cycle of Thorium Advanced CANDU Reactor

钍基先进CANDU堆燃料循环方式研究

79. Conceptual Design of Passive Moderator System for Thorium-based Advanced CANDU Reactor

钍基先进坎杜堆非能动慢化剂系统概念设计

80. Thorium based Advanced CANDU Reactor(TACR)

钍基先进重水堆