CARBIDE FUEL DEVELOPMENT. Progress Report, Period of September 15, 1960 to January 31, 1960

Technical Report · Tue Feb 28 04:00:00 EST 1961

DOI:https://doi.org/10.2172/4009358· OSTI ID:4009358

Strasser, A; Taylor, K

Several UC batches were synthesized in a graphite resistance furnace in a plutonium glove box. Use of Ni as additive was found to lower the sintering temperature but not the ultimate density of UC. In the fuel-clad compatibility tests, UC was held in contact with various cladding materials at 820 deg C in helium; the cladding materials included Inconel X, type 304 stalnless steel, 2 1/ 4 Cr --Mo, Be, and Zircaloy 2. The results of microprobe analysis of the compatibility samples after testing for 1000 to 4000 hr are described. UC samples clad by Nb and type 316 stainless s-teel were irradiated and the helium gap thermal conductivities given for burnups of 3000 and 5000 Mwd/t. (D. L.C.)

• Research Organization: Nuclear Development Corp. of America, White Plains, N.Y.; Carborundum Co., Niagara Falls, N.Y.
• NSA Number: NSA-15-018495
• OSTI ID: 4009358
• Report Number(s): NDA-2162-1
• Country of Publication: United States
• Language: English

Related Subjects

ALUMINUM ALLOYS
BERYLLIUM
CHROMIUM ALLOYS
COATING
DENSITY
FURNACES
GRAPHITE
HELIUM
HIGH TEMPERATURE
INCONEL ALLOYS
MATERIALS TESTING
METALS, CERAMICS, AND OTHER MATERIALS
MICROSCOPY
MOLYBDENUM ALLOYS
NICKEL
NICKEL ALLOYS
NIOBIUM ALLOYS
PLUTONIUM
RADIATION PROTECTION
REMOTE HANDLING
SINTERING
STAINLESS STEELS
TITANIUM ALLOYS
URANIUM CARBIDES