DRY METHOD OF REPROCESSING SPENT NUCLEAR FUEL

PROBLEM TO BE SOLVED: To reduce an amount of a glass solidified body for solidifying a radio- active waste generated in a spent nuclear fuel. SOLUTION: This method is provided with a step (S4) for oxidation-heating the spent nuclear fuel at 450-800 deg.C to generate fuel powder, and a step (S6) for...

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Bibliographische Detailangaben
Hauptverfasser:	AMANO OSAMU, SUDO KUNIHIKO, OWAYA HIDENARI, SHIMADA TAKASHI, KOSAKA YUJI, HARA TERUO
Format:	Patent
Sprache:	eng
Schlagworte:	CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATERTREATMENT OR WASTE MANAGEMENT GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS NUCLEAR ENGINEERING NUCLEAR PHYSICS NUCLEAR REACTORS PHYSICS TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINSTCLIMATE CHANGE
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Beschreibung
Zusammenfassung:	PROBLEM TO BE SOLVED: To reduce an amount of a glass solidified body for solidifying a radio- active waste generated in a spent nuclear fuel. SOLUTION: This method is provided with a step (S4) for oxidation-heating the spent nuclear fuel at 450-800 deg.C to generate fuel powder, and a step (S6) for heat-treating the fuel powder at 1000 deg.C or more under a reduced pressure atmosphere to separate a volatile substance volatilized and a non-volatile substance not volatilized. Cesium 137 of a radio-active nuclear species generated by combustion of the nuclear fuel is contained in the volatile substance. Radio- activity is reduced and a heating value is reduced in the radio-active waste generated by reprocessing, by conducting the separation into the volatile substance and the non-volatile substance (S4) to reprocess the non-volatile substance (S7).