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RECYCLE METHOD FOR PELLET SCRAP OF OXIDE NUCLEAR FUEL
RECYCLE METHOD FOR PELLET SCRAP OF OXIDE NUCLEAR FUEL
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机译:氧化物核燃料切粒的循环法
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摘要
PROBLEM TO BE SOLVED: To provide a method for recycling a large amount of pellet scrap without using a fluidized fed reaction furnace. SOLUTION: Pellet scrap containing exclusively UO2 or UO2 containing oxides of plutonium, gadolinium and erbium is oxidized under oxidizing gas atmosphere of 300 to 800 deg.C in a thermal processing furnace to produce regenerated particles of U3 O8 . Material powder containing regenerated particles U3 O8 to about 10 to 100 wt.% and the remainder consisting exclusively of UO2 or UO2 powder containing oxides of plutonium, gadolinium and erbium is constituted. After adding a sintering assistant, oxide or compound of niobium(Nb), titanium(Ti), lithium(Li), vanadium(V), tin(Sn), aluminum(Al), magnesium(Mg) and silicon(Si) to the stuff powder by 0.02 to 2 wt.% of the element weight, mixing and molding, the material is sintered for 1 to 20 hours under reducing atmosphere of 1500 to 1800 deg.C to produce new nuclear fuel pellets.
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机译:解决的问题:提供一种无需使用流化进料反应炉就可回收大量颗粒废料的方法。解决方案:仅在300至800℃的氧化性气体气氛中,将仅包含UO2或含U,g和的氧化物的UO2的粒料废料在热处理炉中氧化,以生成再生的U3 O8颗粒。构成包含约10至100wt。%的再生颗粒U 3 O 8的材料粉末,其余部分仅由包含O 、,和and的氧化物的UO 2或UO 2粉末组成。在添加烧结助剂,氧化物或铌(Nb),钛(Ti),锂(Li),钒(V),锡(Sn),铝(Al),镁(Mg)和硅(Si)的化合物将原料粉末按元素重量的0.02至2 wt。%进行混合和模制,然后在1500至1800℃的还原气氛下将该材料烧结1至20小时,以生产新的核燃料芯块。
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