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Method for dissolving plutonium-containing nuclear fuels

Patent ·
OSTI ID:6325083
; ;
A method of accelerating and increasing the solubility in nitric acid of plutonium dioxide and uranium/plutonium oxide fuels and insoluble residues from such nitric acid dissolution, includes the steps of arranging metal loadings to be at least 200 G (Pu) or (U+Pu) per liter of dissolving solution so that the plutonium in solution acts as an autocatalyst.
Assignee:
United Kingdom Atomic Energy Auth (United Kingdom)
Patent Number(s):
US 4333912
OSTI ID:
6325083
Country of Publication:
United States
Language:
English

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Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACTINIDE COMPOUNDS
CHALCOGENIDES
DISSOLUTION
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FUELS
HYDROGEN COMPOUNDS
INORGANIC ACIDS
MATERIALS
NITRATES
NITRIC ACID
NITROGEN COMPOUNDS
NUCLEAR FUELS
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM NITRATES
PLUTONIUM OXIDES
REACTOR MATERIALS
REACTORS
RECYCLING
SEPARATION PROCESSES
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES