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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Hauptverfasser: HANUS, DIETMAR, KOENIGS, WIHELM, LOEB, RAINER, FUNKE, PETER
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creator HANUS
DIETMAR
KOENIGS
WIHELM
LOEB
RAINER
FUNKE
PETER
description 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.
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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). 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subjects 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
title Method of producing mixed-oxide nuclear fuel pellets soluble in nitric acid
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