燃料棒

核燃料棒~（235）U富集度均匀性扫描装置中的中子慢化系统计算

Neutron Moderation Calculation for Nuclear Fuel Rod Scanner

新一代核燃料棒UO2芯块间隙检测设备研制

New inspecting equipment for intet-pellet gaps in the fuel rod

GB/T11851-1996压水堆燃料棒焊缝X射线照相检验方法

Radiographic inspection of welds for PWR fuel rods

核电站燃料棒焊缝X射线检测质量监督

Quality supervision of X-ray testing of the welds in nuclear power plant fuel rods

AFA3G含钆燃料棒上端塞环缝TIG焊接研究

AFA 3G Gd Rod Top End Plug Girth TIG Wilding

燃料棒芯块中Kr、Xe的低温释放机理

Low-Temperature Release Mechanism of Kr and Xe in Fuel Pellet

在实践的基础上，较全面地介绍了核电站燃料棒焊缝X射线检测质量监督的必要性、监督依据和内容以及监督的实施情况。

The quality supervision of X ray testing of the welds in nuclear power plant fuel rods was introduced including its necessity , basis , contents and implementation .

用质谱计测定燃料棒中释放的气体组份和当量水份。比较了如下三种棒中的当量水份：（1）充氦无UO2芯块的空棒；

The gaseous compositions and equivalent water released from the fuel rod are measured by mass spectrometry .

本文测量了不同直径的PMMA燃料棒在逆风和静止环境中的火焰传播速度、裂解长度和火焰形状。

In this paper the flame spreading rate ( Vf ), pyrolysis length ( lp ) and flame structure of PMMA fuel rod in an opposed air flow and quiescent environment were investigated .

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

本文介绍了水-水零功率堆均匀栅格中，利用周期法和脉冲中子源法测量Gd2O3&UO2毒物燃料棒反应性效应的几个实验结果。

Some experimental results on the reactivity effects produced by Gd_2o_3-UO_2 Poison rods measured in a light water zero power experiment with homogeneous lattice distribution by using periodic method as well as pulsed source method are given .

运营福岛第一核电站（FukushimaDaiichi）的东京电力公司（Tepco）猜测，有两座反应堆里的放射性燃料棒可能已部分熔化。

Tokyo Electric Power ( Tepco ), the company that operates the Fukushima Daiichi nuclear plant , suspects that radioactive fuel rods may have partly melted in two reactors .

初步的研究结果表明：如果在自然循环长度和延伸燃耗运行期内发生落棒事故，对于基负荷运行和基负荷一次调频运行，均有PCI的应力裕量，不会造成燃料棒破损。

The results show there are enough stress margins for the base load operation and primary frequency control operation if rod drop accident occurs in the natural cycle and stretch out operation , therefore no risk of PCI failure has been found .

M5合金是一种适用于高燃耗组件的新型锆合金，主要用作燃料棒包壳、端塞、导向管和定位格架材料。

M5 alloy was a new zirconium alloy used in high burn up assembly such as fuel cladding , end plug , guide tube and grid spring and so on .

研究结果表明，氦-3回路能够快速、均匀、灵活地调节试验燃料棒的功率，是CARR实现压水堆燃料功率瞬态变化的优选方案。

It is seen that the3He loop can adjust the power of the tested PWR fuel element rapidly , evenly and flexibly and it is an optimal path to realize the power transient regulation for tested PWR fuel .

其中M4和M5合金包壳在燃料棒燃耗达到55GW·d·t-1的辐照考验结果表明，它们在堆内的腐蚀、蠕变和辐照伸长等性能优于改进型Zr4合金包壳。

The results obtained from irradiation test show that the corrosion resistance , creep resistance and irradiation growth for M4 and M5 are superior to the optimized Zircaloy 4 , especially the performances of M5 in and out of pile are much better .

对于核燃料棒235U富集度均匀性扫描装置，为了合理有效地利用252Cf中子源，提高检测灵敏度，需要合理选择中子慢化材料，优化中子慢化过程。

In order to use ~ ( 252 ) Cf source effectively and improve testing sensitivity of the nuclear fuel scanner , appropriate moderation material should be selected carefully , and the process of neutron moderation should be optimized .

未辐照燃料棒内氢来源的研究

A study on internal sources of hydrogen in unirradiated fuel rod

AFA3G核燃料棒表面陶瓷化处理技术研究

Study on Ceramic Surface Coating Process of AFA 3G Fuel Rod

先进重水反应堆燃料棒束物理研究与设计

Research and Design on Fuel Bundle of Advanced Heavy Water Reactor

压水堆燃料棒堆内瞬态试验功率调节装置设计

Design of Power Adjusting Device for PWR Fuel Rod Ramp Test

压水堆燃料棒设计参数不确定性研究

Research on Uncertainty of Design Parameters for PWR Fuel Rod

燃料棒束对称近壁子通道内湍流结构的模拟实验研究

An experimental investigation on turbulent flow through symmetric wall-subchannels of rod bundles

核电站燃料棒制造中的电子束焊接

Electron beam welding in manufacture of fuel rods for nuclear power plants

GB/T13368-1992微型中子源反应堆核燃料棒技术条件

Specification of nuclear fuel rods for miniature neutron source reactor

GB/T11809-1998压水堆核燃料棒焊缝金相检验

Metallographic examination for weld seam of nuclear fuel rod used in PWR

关于核电站燃料棒束临界热流密度研究中一些问题的讨论

Some Problems about the Investigation of Critical Heat Flux for PWR Fuel Assemblies

燃料棒组件生产线自动化控制网络系统

The Control System & Network System Design of Nuclear Fuel Element Production Line

快堆组件套管及燃料棒测量系统设计

Measuring System for Fast Neutron Reactors and Fuel Pins

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 .