PROCESS OF DISSOLVING ZIRCONIUM ALLOYS
Patent
·
OSTI ID:4304923
A process is described for dissolving binary zirconium-uranium alloys where the uranium content is about 2%. In prior dissolution procedures for these alloys, an oxidizing agent was added to prevent the precipitation of uranium tetrafluoride. In the present method complete dissolution is accomplished without the use of the oxidizing agent by using only the stoichiometric amount or slight excess of HF required by the zirconium. The concentration of the acid may range from 2M to 10M and the dissolution is advatageously carried out at a temperature of 80 deg C.
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-12-007004
- Assignee:
- U.S. Atomic Energy Commission
- Patent Number(s):
- US 2820692
- OSTI ID:
- 4304923
- Country of Publication:
- United States
- Language:
- English
Similar Records
THE ANALYSIS OF URANIUM-ZIRCONIUM ALLOYS
AN IMPROVED AQUEOUS PROCESS FOR ZIRCONIUM ALLOY NUCLEAR REACTOR FUELS. PART II. CONTINUOUS DISSOLUTION WITH 5M HYDROFLUORIC ACID
METHOD OF DISSOLVING ZIRCONIUM CONTAINING FUEL ELEMENTS
Technical Report
·
Sat Feb 28 23:00:00 EST 1953
·
OSTI ID:4386423
AN IMPROVED AQUEOUS PROCESS FOR ZIRCONIUM ALLOY NUCLEAR REACTOR FUELS. PART II. CONTINUOUS DISSOLUTION WITH 5M HYDROFLUORIC ACID
Technical Report
·
Wed Sep 25 00:00:00 EDT 1963
·
OSTI ID:4084192
METHOD OF DISSOLVING ZIRCONIUM CONTAINING FUEL ELEMENTS
Patent
·
Sun Dec 11 23:00:00 EST 1960
·
OSTI ID:4838032