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- A safety check-up method for decommissioned reactor fuel element cladding 一种用于退役核燃料元件包壳的破裂检测技术
- Heat transfer and pressure drop of a reactor fuel element model with polyzonal spiral finning 具有多区螺旋肋的反应堆燃料元件模型的传热和压降
- reactor fuel element 反应堆燃料元件
- Research reactor fuel transport in the U.K. 英国研究堆燃料运输。
- 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。
- 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。
- 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。
- For most countries, uranium enrichment makes no economic sense either, since reactor fuel can be bought from suppliers in Europe, America and Russia. 对大多数国家来说,铀浓缩也同样无经济效益,因为反应堆燃料可由欧洲、美国和俄罗斯买到。
- 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。
- Its comprehensive coverage focuses on corrosion of all metal/nonmetal alloy reactor components, including claddings, coatings, pressure vessels, piping, and fuel elements, etc. 它的广泛报导集中在所有金属/有色金属反应堆部件,包括包层,涂层,压力容器,管道系统和燃料元素等腐蚀;
- 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。
- MW high temperature gas cooled reactor(HTR 10) is a helium cooled and graphite moderated nuclear reactor. Spherical graphite fuel elements are piled loosely in the core. 10MW高温气冷堆为氦气冷却、石墨慢化的核反应堆,球形石墨燃料元件松散堆积在堆芯中。
- Local mean velocity and turbulence intensity measurements were obtained with DANTEC 55 X two-dimensional Laser Dopper Anemometry (LDA) for rod bundle of reactor fuel assembly test model whick was a 4x4 rod bundle. 采用DANTEC 55X两维激光多普勒测速仪对反应堆燃料组件棒束流场进行了测试,获得了其不同断面处的紊流速度分布及湍流特性,并进行了理论模型计算分析,试验结果与理论计算及他人实验结果符合较好。
- The UO3 that Bulande produces in river establishment carries Huo Pu in harbor changeover establishment, can change UO3 into over use as the UO2 of domestic reactor fuel and the UF6 that offer outlet. 布兰德河设施中生产的 UO3 运送到霍普港转换设施中 ,在那里可将 UO3 转换成用作国内反应堆燃料的 UO2 和供出口的 UF6。
- 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。
- 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。
- Reactor fuel charging and discharging machines; 反应堆燃料装卸机;
- 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 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。
- 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;