发明名称 REMOVING METHOD OF SOLID URANIUM COMPOUND IN URANIUM ENRICHED SEPARATION CASCADE
摘要 <p>PROBLEM TO BE SOLVED: To efficiently remove solid uranium compound in a cascade by a small amount of uranium removing processing gas (halogen gas). SOLUTION: An uranium enriched separation cascade 10 using a centrifugal separator is cold-operated, uranium removing processing gas is supplied to the cascade, reacted with solid uranium compound adhered on the cascade, and the separation ability of the centrifugal separator is utilized to be separated. Reactive production gas and non-reactive halogen gas being lightweight components discharged from the production side of the cascade are introduced to a reactive production gas collecting facility 14, the reactive production gas is separated and collected, and the non-reactive halogen gas is returned to the cascade as uranium removing processing gas. Uranium hexafluoride gas of a heavyweight component is discharged from the waste product side, and collected by an uranium hexafluoride gas collection facility 18. The reactive production gas collected in the reactive production gas collection facility is re-fluoridized by a re-fluoridizing facility 16 and preferably returned to the cascade.</p>
申请公布号 JPH11160491(A) 申请公布日期 1999.06.18
申请号 JP19970344239 申请日期 1997.11.28
申请人 JAPAN NUCLEAR CYCLE DEVELOPMENT INST STATE OF PROJECTS(JNC) 发明人 YONEKAWA SHIGERU;FUJIWARA SATOSHI;YAMAMOTO FUMIO
分类号 G21C19/44;G21F9/28;(IPC1-7):G21F9/28 主分类号 G21C19/44
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