Document Details
PURL
Title:
PRELIMINARY ZIRFLEX FLOWSHEET FOR THE DISSOLUTION OF ZIRCALOY CLAD FUELS
Author(s):
Document Type:
REPORT
Publication Date:
1958 Jul 10
Declassification Date:
1959 Feb 02
Declassification Status:
Declassified
Document Pages:
pages 7
Accession Number:
RL-1-367614
Document Number(s):
HW-56752(Del.)
Originating Research Org.:
General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
OpenNet Entry Date:
1959 Dec 31
OpenNet Modified Date:
2022 Jun 28
Description/Abstract:
A preliminary flowsheet for processing Zircaloyclad uranium dioxide fuels is presented. The process (Zirflex) employs a mixture of boiling ammonium fluoride and ammonium nitrate for the selective dissolution of the fuel cladding. Most of the uranium dissolved during coating removal is precipitated as UF/sub 4/ by cooling. Centrifugation recovers the precipitate which is later dissolved in nitric acid and aluminum nitrate. After decladding the remaining cores of metallic uranium or uranium dioxide are dissolved in a conventional manner with nitric acid. Likewise, the customary stainless steel equipment may be used. Typical corrosion rates for cladding removal followed by nitric acid dissolution are 2.5 mils per month. (auth)