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首页> 外文会议>Proceedings of the workshop on manufacturing technology and process for reactor fuels >Development of high uranium-density fuels for use in research reactors
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Development of high uranium-density fuels for use in research reactors

机译：开发用于研究堆的高铀密度燃料

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The uranium silicide U_3Si_2 possesses uranium density 11.3 gU/cm~3 with a congruent melting point of 1665℃, and is now successfully in use as a research reactor fuel. Another uranium silicide U_3Si and U_6Me-type uranium alloys (Me = Fe,Mn,Ni) have been chosen as new fuel materials because of the higher uranium densities 14.9 and 17.0 gU/cm~3, respectively.rnExperiments were carried out to fabricate miniature aluminum-dispersion plate-type and aluminum-clad disk-type fuels by using the conventional picture-frame method and a hot-pressing technique, respectively.rnThese included the above-mentioned new fuel materials as well as U_3Si_2. Totally 14 miniplates with uranium densities from 4.0 to 6.3 gU/cm~3 of fuel meat were prepared together with 28 disk-type fuel containing structurally-modified U_3Si , and subjected to the neutron irradiation in JMTR (Japan Materials Testing Reactor). Some results of postirradiation examinations are presen ted.
机译：硅化铀U_3Si_2的铀密度为11.3 gU / cm〜3，全熔点为1665℃，现已成功用作研究堆燃料。由于铀密度较高，分别选择了另一种硅化铀U_3Si和U_6Me型铀合金（Me = Fe，Mn，Ni）作为新的燃料材料。进行了实验以制造小型化铝分散板型燃料和覆铝圆盘型燃料分别采用传统的画框方法和热压技术。这包括上述新型燃料材料以及U_3Si_2。总共制备了14块铀密度为4.0至6.3 gU / cm〜3燃料肉的微孔板，与28种含有结构改性U_3Si的盘状燃料一起，在JMTR（日本材料试验反应堆）中进行了中子辐照。提出了一些放射后检查的结果。

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