QUARTERLY PROGRESS REPORT TO JOINT U.S.-EURATOM RESEARCH AND DEVELOPMENT BOARD ON BATTELLE ASSISTANCE TO AEC-EURATOM PROGRAM FOR THE PERIOD ENDING MARCH 31, 1961

Technical Report · Tue Oct 31 04:00:00 EST 1961

OSTI ID:4008423

Epstein, H M; Keller, D L

Void Distribution and Heat Transfer Studies. Steam distribution studies were made in 50- and 100-mil thick rectangular channels at pressures of 700 to 1300 psi snd Reynolds numbers of 4 x 10/sup 4/ to 10/sup 5/. Correlations of slip ratio at constant void fraction indicates that the slip ratio has a maximum at a Reynolds number of approximately 75,000 and decreases monotonically with pressure. Development of Uranium Mononitride. It was found that UN specimens of 95 to 96% theoretical density can be prepared by hot pressing coarse UN powders at approximately 1480 deg C. A small amount of an extraneous phase was discovered in this dense UN by etching. Preliminary corrosion data are presented for UN. In arc melting studies, it was found that arc current and potential are important in the formation of UN by arc melting. Cap sules were designed for irradiation studies of UN, and estimated rates of U burnup and H/sub 2/ production are given. Pellets of UN containing natural U were immersed in NaK in an Al container in a He atmosphere; after 1000 hr at 500 deg F, some discoloration of the UN specimen resulted (D.L.C.)

• Research Organization: Battelle Memorial Inst., Columbus, Ohio
• DOE Contract Number: W-7405-ENG-92
• NSA Number: NSA-15-018987
• OSTI ID: 4008423
• Report Number(s): TID-12551; EURAEC-76
• Country of Publication: United States
• Language: English

Related Subjects

BUBBLES
BURNUP
COMPACTING
CORROSION
DECOMPOSITION
DENSITY
DISTRIBUTION
ELECTRIC ARCS
FABRICATION
HEAT TRANSFER
HELIUM
HIGH TEMPERATURE
HYDROGEN
IRRADIATION
MELTING
NATURAL URANIUM FUEL
NITRIDES
POTASSIUM ALLOYS
POWDERS
PRESSURE
REACTOR TECHNOLOGY
SODIUM ALLOYS
STEAM
TESTING
TUBES
URANIUM COMPOUNDS
ZONES