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METALLURGICAL EVALUATION OF AN INCONEL 690 INSERT FROM A RADIOACTIVE WASTE GLASS MELTER POUR SPOUT

机译:从放射性废物玻璃熔化器倒出来的Inconel 690插入的冶金评估

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A metallurgical evaluation was conducted to assess the performance of an Inconel 690 insert that was removed from the pour spout of a radioactive waste glass melter. The insert was in service for approximately three months during which time 64 canisters, 114,300 kg (252,000 lbs), of glass had been poured. The insert was exposed to molten borosilicate glass and corrosive vapors at temperatures in excess of 1000 deg C. The most severe degradation occurred in the upper portion of the insert in the glass contact region. Degradation was attributed to the synergistic effects of oxidation and molten glass corrosion. Oxidation was the primary degradation mechanism in the vapor space. Results of the metallurgical evaluation including degradation rates will be presented.
机译:进行冶金评估以评估从放射性废物玻璃熔化的倒入喷口中除去的690插入物的性能。该插入件在倾倒了64个罐,114,300公斤(252,000磅),玻璃的时间约为三个月。将插入件暴露于熔融硼硅酸盐玻璃和腐蚀性蒸汽超过1000℃的温度下。在玻璃接触区域的插入件的上部发生最严重的降解。降解归因于氧化和熔融玻璃腐蚀的协同作用。氧化是蒸汽空间中的初级降解机制。将介绍包括退化率的冶金评估结果。

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