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Title: Chemical decontamination and melt densification. [Chop-leach fuel hulls]

Conference ·
OSTI ID:7352047

Preliminary studies on the chemical decontamination and densification of Zircaloy, stainless steel, and Inconel undissolved residues remaining after dissolution of the UO/sub 2/--PuO/sub 2/ spent fuel material from sheared fuel bundles are reported. The studies were made on cold or very small samples to demonstrate the feasibility of the processes developed before proceeding to hot cell demonstrations with kg level of the sources. A promising aqueous decontamination method for Zr alloy cladding was developed in which oxidized surfaces are conditioned with HF prior to leaching with ammonium oxalate, ammonium citrate, ammonium fluoride, and hydrogen peroxide. Feasibility of molten salt decontamination of oxidized Zircaloy was demonstrated. A low melting alloy of Zircaloy, stainless steel, and Inconel was obtained in induction heated graphite crucibles. Segregated Zircaloy cladding sections were directly melted by the inductoslag process to yield a metal ingot suitable for storage. Both Zircaloy and Zircaloy--stainless steel--Inconel alloys proved to be highly satisfactory getters and sinks for recovered tritium. (JSR)

Research Organization:
Battelle Pacific Northwest Labs., Richland, Wash. (USA)
DOE Contract Number:
E(45-1)-1830
OSTI ID:
7352047
Report Number(s):
BNWL-SA-5696; CONF-760310-5; TRN: 76-014226
Resource Relation:
Conference: IAEA symposium on the management of radioactive waste, Vienna, Austria, 22 Mar 1976
Country of Publication:
United States
Language:
English