Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

PROCESS OF DISSOLVING FUEL ELEMENTS OF NUCLEAR REACTORS

Patent ·
OSTI ID:4637372
; ;

A process is described for dissolving stainless-steelor zirconium-clad uranium dioxide fuel elements by immersing the elements in molten lead chloride, adding copper, cuprous chloride, or cupric chloride as a catalyst and passing chlorine through the salt mixture. (AEC)

Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-17-035951
Assignee:
U.S. Atomic Energy Commission
Patent Number(s):
US 3102849
OSTI ID:
4637372
Country of Publication:
United States
Language:
English

Similar Records

SALT PHASE CHLORINATION OF REACTOR FUELS. III. CATALYZED DISSOLUTION OF URANIUM DIOXIDE IN LEAD CHLORIDE-CHLORIDE SYSTEMS
Technical Report · Wed Jan 31 23:00:00 EST 1962 · OSTI ID:4808131
SALT-PHASE CHLORINATION OF REACTOR FUELS. II. ARCO PROCESS DEFINITION AND SCOPING STUDIES
Technical Report · Thu Oct 20 00:00:00 EDT 1960 · OSTI ID:4108919
METHOD OF FORMING A FUEL ELEMENT FOR A NUCLEAR REACTOR
Patent · Mon Jan 22 23:00:00 EST 1962 · OSTI ID:4815809

Related Subjects

CATALYSIS
CHEMISTRY
CHLORINE
COPPER
COPPER CHLORIDES
FUEL CANS
FUSED SALTS
GAS FLOW
LEAD CHLORIDES
SEPARATION PROCESSES
SOLUTIONS
STAINLESS STEELS
URANIUM DIOXIDE
ZIRCONIUM