Method of producing mixed-oxide nuclear fuel pellets soluble in nitric acid

Production of mixed-oxide nuclear fuel pellets of uranium dioxide (UO2+x) and plutonium dioxide (PuO2) which are soluble in nitric acid. The powder mixture of oxides is added to a halogen-free milling aid, such as propane diol, then is milled and subsequently granulated, pressed and sintered. The mi...

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Bibliographische Detailangaben
Hauptverfasser:	HANUS, DIETMAR, KOENIGS, WIHELM, LOEB, RAINER, FUNKE, PETER
Format:	Patent
Sprache:	eng
Schlagworte:	CHEMICAL OR PHYSICAL PROCESSES, e.g. CATALYSIS OR COLLOIDCHEMISTRY CRUSHING, PULVERISING, OR DISINTEGRATING CRUSHING, PULVERISING, OR DISINTEGRATING IN GENERAL GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS MILLING GRAIN NUCLEAR ENGINEERING NUCLEAR PHYSICS NUCLEAR REACTORS PERFORMING OPERATIONS PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL PHYSICS PREPARATORY TREATMENT OF GRAIN FOR MILLING REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGYGENERATION, TRANSMISSION OR DISTRIBUTION TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINSTCLIMATE CHANGE THEIR RELEVANT APPARATUS TRANSPORTING
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Beschreibung
Zusammenfassung:	Production of mixed-oxide nuclear fuel pellets of uranium dioxide (UO2+x) and plutonium dioxide (PuO2) which are soluble in nitric acid. The powder mixture of oxides is added to a halogen-free milling aid, such as propane diol, then is milled and subsequently granulated, pressed and sintered. The milling aid is expelled by subsequent drying processes or heat treatments (sintering). The milling process is controlled to obtain a primary grain size of less than two micrometers.