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Processing and microstructural characterisation of UO2-based simulated spent nuclear fuel ceramics for the UK`s advanced gas-cooled reactors

机译:用于英国先进气冷反应堆的UO2基模拟废核燃料陶瓷的加工和微观结构表征

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摘要

Processing and characterisation of depleted UO2-based Simulated Spent Nuclear Fuel (SIMFuel), which aims to replicate both chemistry and microstructure of Spent Nuclear Fuel (SNF) discharged from a UK Advanced Gas-cooled Reactor (AGR) after a prolonged cooling time is described in this thesis.udThirteen fission product surrogates were blended with depleted UO2 and sintered to simulate the composition of fuel pellets after burn-ups of 25 and 43 GWd/t U. Pure depleted UO2 pellets were also investigated as a reference. The fission product (FP) inventory was calculated using the FISPIN code provided by the UK National Nuclear Laboratory.udExperiments were conducted in two phases, during which SIMFuel pellets were sintered for 5 and 12 h at 1730 °C in reducing atmosphere. Some pellets were also heat-treated to simulate microstructural changes in SNF while in the reactor. SIMFuel pellets were up to 92% dense, with grain sizes between 1.5 μm and 5 μm and porosity 4% and 10%. Undoped reference pellet density was ~96.5%, with grain size of 10.3±3.0 μm and ~4.5 area% porosity. Heat treatment of the UO2 samples increased grain size by ~50%, while little change occurred in the doped samples.udThe chemistry of the various FPs was reproduced with limitations. Notably, during the sintering process oxide precipitates ((Ba,Sr)ZrO3 perovskite phase) and Pd-Ru-Rh-Mo metallic precipitates formed within the UO2 matrix, as originally sought. Spherical oxide precipitates measured up to 30 μm in diameter, while the metallic precipitates were 0.8±0.7 μm. FPs with high solubility in UO2, such as La, Nd and Y, dissolved into the UO2 matrix. ICP-MS analysis showed that some dopants, e.g. Cs and Te, evaporated from the pellets, while the concentration of other elements had also changed during sample fabrication.udVery scarce information on real PWR and AGR SNF are reviewed and compared to AGR SIMFuel fabricated in this project. Thorough analysis reveal the severe limitations of the SIMFuel technique in general and call for more experimental work and accessible publications on SNF.
机译:描述了耗尽的基于UO2的模拟乏核燃料(SIMFuel)的处理和特性,该方法旨在复制从英国先进气冷堆(AGR)排放的冷却时间延长后的乏核燃料(SNF)的化学和微观结构。 ud将十三种裂变产物替代物与贫化的UO2混合并烧结以模拟燃尽25和43 GWd / t U的燃料颗粒的组成。还研究了纯耗竭的UO2颗粒作为参考。使用英国国家核实验室提供的FISPIN代码计算裂变产物(FP)存量。 ud实验分两个阶段进行,在此阶段中,SIMFuel颗粒在还原性气氛中于1730°C烧结5和12 h。还对一些颗粒进行了热处理,以模拟反应堆中SNF的微观结构变化。 SIMFuel颗粒的密度高达92%,粒度在1.5μm和5μm之间,孔隙率在4%和10%之间。未掺杂的参考颗粒密度为〜96.5%,晶粒尺寸为10.3±3.0μm,孔隙率为〜4.5面积%。 UO2样品的热处理将晶粒尺寸增加了约50%,而掺杂样品中几乎没有发生变化。 ud各种FP的化学成分均受到限制地复制。值得注意的是,在烧结过程中,氧化物沉淀((Ba,Sr)ZrO3钙钛矿相)和在UO2基体内形成的Pd-Ru-Rh-Mo金属沉淀,如最初所寻求的。球形氧化物沉淀物的直径最大为30μm,而金属沉淀物的直径为0.8±0.7μm。在UO2中具有高溶解度的FP(例如La,Nd和Y)溶解在UO2基质中。 ICP-MS分析显示一些掺杂剂,例如掺杂剂。 Cs和Te从颗粒中蒸发,而其他元素的浓度在样品制造过程中也发生了变化。 ud对实际PWR和AGR SNF的非常稀少的信息进行了审查,并与该项目中制造的AGR SIMFuel进行了比较。全面的分析揭示了SIMFuel技术的严重局限性,并呼吁开展更多的实验工作和有关SNF的可访问出版物。

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    Hiezl Zoltan;

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  • 年度 2015
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