换料

介绍了NHR-10组件内钆可燃毒物配置、堆芯燃料组件布置和换料方案的改进设计。

This paper introduces the improved NHR 10 core design which includes the arrangement of the gadolinium burnable poison ( BP ), the fuel assembly arrangement and the fuel assembly reloading scheme .

核供热堆换料优化设计研究

Study of reloading optimization design for nuclear heating reactors

用于CANDU堆换料方案快速评价的线性敏感矩阵方法

Development of linear sensitivity matrix method for fast evaluation of CANDU refuelling schemes

利用中子学计算程序对换料堆芯正常运行工况（一类工况或工况I）和中等频率事故工况（二类工况或工况II）中可能的堆芯功率分布进行模拟。

The radial and axial power distributions of normal operation ( category I or condition I ) and abnormal operation ( category II or condition II ) are simulated by using neutronics calculation code .

而且现在的凹板印刷又要求具有高速、全自动换料的特点，这又增加了张力控制的难度，传统的PI控制满足不了控制的要求，必须对其进行改造。

Tension control becomes more difficult because modern gravure press machine possessing high speed and auto material-exchanging . The traditional PI control can not satisfy the requirements of control precision and system stability .

实例分析验证了该方法的有效性；4分析研究了粗糙集理论在CANDU反应堆换料管理工作的应用。

The experiment showed that the algorithm was valid . 4 The application of Rough Set Theory in fuel management of CANDU reactor was analyzed and researched .

自某电站投入运行以来，当使用PO管从换料水池向BA管传水时，D2泵下游出口管线振动和噪声相当高，导致该泵和相关管线损坏。

Since some power station has been putting into operation , so high the pipeline vibration and noise of the pump backward position exist when the spreading water from the changing pond to BA with PO , then this pump and relevant pipeline are damaged .

对一个典型压水堆堆芯在IBM-4341计算机上进行了计算，得到预期效果，计算所用机时较省（对1/8堆芯布置，计算3个换料周期约用9分钟CPU时间）。

Some calculations were done for a typical PWR core on an IBM-4341 computer , The satisfactory results were obtained at reasonable low computational costs . It spent nearly 9 mins CPU time for 3 fuel cycles with a 1 / 8 core configuration .

HTR-10-MW高温气冷实验堆换料方式的研究

The study on the shuffling scheme in HTR-10 MW test module

大亚湾核电站18个月换料对流体系统的影响分析和论证

Fluid Systems Analysis and Verification for GNPS 18-Months Fuel Cycles

追求技术创新创世界一流水平&记大亚湾核电运营管理有限公司18个月换料项目工作

Pursues the technique innovation , create top-grade level in world

换料报告审评方法及效果

Method and Effects of the Review on Refuelling Outage Report

快堆过渡循环换料方案的优化设计

Optimization Design of Refueling Strategy for Fast Reactor Transition Cycles

遗传算法在压水堆核电厂低泄漏换料堆芯装载方案优化中的应用

Low-leakage Loading Pattern Optimization for PWR NPP Reload Core Using Genetic Algorithms

大亚湾核电站堆芯换料设计

In-Core Reload Design for Daya Bay Nuclear Power Station

其工作量大大延长了换料设计的周期。

Thus it delayed the cycle of reload design .

混合遗传算法在压水堆换料优化中的应用

New Hybrid Optimization Method and Its Application to Pressurized Water Reactors Reloading Optimization

在压水堆核电站换料的过程中存在燃料棒破损的可能。

There exists probability of fuel assembly damage in PWR during refueling period .

大亚湾核电站18个月换料非失水事故分析

GNPS 18-Months Fuel Cycles Non - LOCA Accident Analyses

换料操作必须遥控进行，并且不需要人为的直接干预。

Refuelling must be done remotely without direct intervention .

最后比较了由该系统生成的换料程序和人工编写的程序。

Finally , a comparison of computerized and manned-programmed refueling plans is given .

在核电站堆芯换料管理系统上的应用，验证了该方法的有效性。

The proposed methods were validated by the applications in nuclear station MIS .

外层燃料内移换料方式供者细胞脾内移植诱导小鼠气管移植耐受

Induction of Tolerance to Murine Tracheal Allograft by Intrasplenic Transplantation of Donor Cells

松开螺丝，将燃料换料的存储空间补充制动液。

Loosen the screw , will fuel refueling storage space added the brake fluid .

遗传算法及其应用于堆芯换料优化问题的特性研究

Study on Characteristics of Genetic Algorithms and Its Application to Optimize Reloading Pattern Problem

两台机组的首次装料设计和首次换料设计由法马通承担。第3循环大亚湾核电站与国内换料设计单位一起致力于换料设计自主化，井开始与法马通背靠背的换料堆芯设计。

The two initial core design and first reload design were done by Framatome .

压水堆多循环换料设计优化方法研究

Algorithm research on PWR multi-cycle refueling design optimization

大亚湾核电站18个月换料堆芯热工水力设计

GNPS 18-Months Fuel Cycles Core Thermal Hydraulic Design

大亚湾核电站18个月换料工程及其项目管理

18-Months Fuel Cycle Engineering and Its Project Management of the Daya Bay Nuclear Power Station

岭澳核电站二期18个月换料燃料管理研究

Fuel Management Study on 18-Months Fuel Cycle for Ling ' ao Phase-II Nuclear Power Station