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process for the purification of uranium in irradiated and device for carrying out the process

机译:辐照中铀的纯化方法和实施该方法的装置

摘要

Uranium is purified (e.g. from fission products) by melting it under a heat stable slag which is molten at the melting point of uranium, the whole molten mass being cooled to freeze the uranium which is then removed from the still liquid slag which now contains the impurities. The slag is preferably a near eutectic composition of beryllium oxide up to 50% with at least one of Ba, Ca, Sr, Li, or La oxides with a possible addition of 4% of UO2. The uranium may form the electrode in a consumable arc furnace and a tungsten electrode may be provided for melting the slag. Other methods of melting are also referred to. Examples of slags used comprise: BeO 10%, BaO 83%, La2O3 7%; and BeO 9.36%, BaO 80.64%, CaO 10%.
机译:铀通过在热稳定的炉渣中熔融而纯化(例如从裂变产物中),该炉渣在铀的熔点下熔融,整个熔融物料被冷却以冻结铀,然后将铀从仍然含有铀的静止液态炉渣中除去。杂质。炉渣优选地是高达50%的氧化铍的近共晶组成,其中Ba,Ca,Sr,Li或La的氧化物中的至少一种以及可能添加4%的UO 2。铀可以在可消耗的电弧炉中形成电极,并且可以提供钨电极以熔化炉渣。还涉及其他熔化方法。所用炉渣的实例包括:BeO 10%,BaO 83%,La 2 O 3 7%;和和BeO 9.36%,BaO 80.64%,CaO 10%。

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