STUDIES OF FAST REACTOR FUEL ELEMENT BEHAVIOR UNDER TRANSIENT HEATING TO FAILURE. I. INITIAL EXPERIMENTS ON METALLIC SAMPLES IN THE ABSENCE OF COOLANT

Technical Report · Tue Aug 01 00:00:00 EDT 1961

DOI:https://doi.org/10.2172/4823898· OSTI ID:4823898

Dickerman, C. E.; Sowa, E. S.; Okrent, D.; Monaweck, J.; Miller, L. B.

Meltdown tests on single metallic unirradiated fuel elements in TREAT are described. The fuel elements (EBRII Mark I fuel pins, EBR-II fuel pins with retractory Nb or Ta cladding, and Fermi-I fuel pins) are tested in an inert atmosphere, with no coolant. The fuel elements are exposed to reactor power bursts of 200 msec to 25 sec duration, under conditions simulating fast reactor operations. For these tests, the type of power burst, the integrated power, the fuel enrichment, the maximum cladding temperature, and the effects of the test on the fuel element are recorded. ( T.F.H.)

• Research Organization: Argonne National Lab., Ill.
• DOE Contract Number: W-31-109-ENG-38
• NSA Number: NSA-15-032911
• OSTI ID: 4823898
• Report Number(s): ANL-6334
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-61
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
EBR-1
ENRICHMENT
EXCURSIONS
FAST NEUTRONS
FUEL CANS
FUEL ELEMENTS
HEAT TREATMENTS
HEATING
MELTING
NIOBIUM
POWER
REACTORS
REFRACTORIES
TANTALUM
TEMPERATURE
TESTING
TRANSIENTS
TREAT