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- This paper discribles the fabrication technology by semi/fullCIP for HTGR spherical fuel element. 本文介绍了高温气冷堆(HTGR)球形燃料元件的半/全冷等静压制造工艺。
- Natural flake graphite of laminated structure is aeolotropic, and it is difficult to press spherical fuel element because of low bulk density and tap density of graphite micro-powder. 天然鳞片石墨为层状结构呈各向异性,且天然鳞片石墨微粉的松装密度和振实密度太低,不利于球形燃料元件的压制。
- spheric fuel element 球形燃料元件
- Chemical analysis of coated particles in spherical fuel element 球形燃料元件中包覆燃料颗粒的化学分析
- An Investigation of the Heat Transfer Coefficient Distribution over a Spherical Fuel Element for a Pebble Bed Reactor 球床堆燃料元件球放热分布研究
- It demonstrates that the fuel element is still safe under this level of burnup. 在该燃耗下,元件仍具有一定的安全裕度。
- 1.Natural flake graphite of laminated structure is aeolotropic, and it is difficult to press spherical fuel element because of low bulk density and tap density of graphite micro-powder. 天然鳞片石墨为层状结构呈各向异性,且天然鳞片石墨微粉的松装密度和振实密度太低,不利于球形燃料元件的压制。
- The coated fuel particle is the key fuel element in the high temperature gas cooled reactor (HTGR). 包覆燃料颗粒是高温气冷堆燃料元件的关键组成部分。
- Decay heat power in nuclear fuels of high-temperature reactors with spherical fuel elements 带球形燃烧元件的高温反应堆的核燃料再裂变功率的计算
- Decay heat power in nuclear fuels of high-temperature reactors with spherical fuel elements; documentation and illustration 带球状燃烧元件的高温反应堆的核燃料再裂变功率的计算。文件和说明
- SiC coatings were fabricated by chemical vapor reaction (CVR) on HTR fuel element matrix graphite, and the structure characteristics of SiC coatings were analyzed with XRD, Raman spectra and SEM. 本文对利用化学气相反应法(CVR)在高温气冷堆燃料元件基体石墨上制备SiC涂层的工艺进行了探讨,利用XRD、Raman谱及SEM对制备的SiC涂层进行了分析。
- In order to carry out power transient tests for PWR fuel element in China Advanced Research Reactor (CARR), the research and conceptual design of 3He pressure control loop were completed. 摘要为使中国先进研究堆(CARR)具备开展压水堆燃料瞬态试验的能力，本工作对氦-3回路进行研究与初步设计。
- The paper also gives results of transporting 32boxes of HFETR discharged fuel elements first loaded in the5MW LPR. 给出了5MW LPR 首炉装料的32盒 HFETR 卸料元件的运输实践结果。
- This paper analyses the reprocessing method and direct final disposal method of HTR spent fuel elements on basis of the characterization of HTR fuel element. 根据高温气冷堆乏燃料元件的特点，分析了对乏燃料元件进行后处理和直接最终处置的处理办法。
- The irradiation and whole-core demonstration indicate that the fuel elements were dimensionally sta-ble. 辐照和全堆芯试用表明:元件外形尺寸稳定;
- Safe and economic disposal of HTR spent fuel elements is an important topic for HTR development. 用既安全又经济的办法处理高温气冷堆乏燃料元件是高温气冷堆发展的重要课题。
- Once irradiated, the uranium fuel elements tend to lose strength and become wrinkled. 经辐射，铀燃料的强度往往减弱并且会出现皱曲现象。
- Spent fuel elements in HTR-10 are discharged into seal and shield casks.Each cask can hold approximately 2 000 fuel elements. HTR-10乏燃料元件卸在密封和屏蔽的乏燃料罐内，每罐可容纳2 000个乏燃料元件。
- A chain reaction can be initiated by inserting more and more fuel elements into the reactor core until the critical mass is attained. 只要在反应堆中加入越来越多的燃料并且一直加到临界质量为止，就可以发生连锁反应。
- In a printer, the removable type element. 印刷机上可拆卸的打印部件。
