FUEL CYCLE DEVELOPMENT PROGRAM. Quarterly Progress Report, July 1 to September 30, 1962
Under Task I, irradiation testing of Capsule UNC-3-1 was resumed in the ETR and is scheduled for completion in January 1983. Under Task II, thermal expansion determinations of uranium carbide were delayed after the apparatus was found defective. The equipment was repnired and tests are being resumed. Thermal conductivity tests are awaiting the release by the AEC of a subcontract to another laboratory. The apparatus for determining hot hardness of uranium carbide is being checked out. Irradiation test specimens of uranium carbide are still being irradiated in MTR. Capsules UNC-1-2 and UNC-1-3 will be removed by the end of October after receiving 15,000 Mwd/ton U. Capsule UNC-1-1 will remain in MTR until a burnup of 30,000 Mwd plus or minus ton is achieved. This is currently estimated to occur in July 1963. Examination of cast uranium carbide, exposed for a year under varied conditions, indicated satisfactory resistance of 4.5 and 4.7 wt.% carbon material to corrosion by laboratory air. Laboratory air caused transverse cracking of 5.3 wt.% carbon specimens after five months. Uranium carbide specimens stored in vacuo showed some surface attack and slight pitting but no cracking. Carbon content of these specimens did not appear to have any effect on corrosion behavior. (auth)
- Research Organization:
- United Nuclear Corp. Development Div., White Plains, N.Y.
- NSA Number:
- NSA-17-011106
- OSTI ID:
- 4718329
- Report Number(s):
- UNC-5040
- Country of Publication:
- United States
- Language:
- English
Similar Records
FUEL CYCLE DEVELOPMENT PROGRAM. Quarterly Progress Report, January 1 to March 31, 1962
THE EFFECT OF HIGH-BURNUP IRRADIATION ON MASSIVE URANIUM MONOCARBIDE
Related Subjects
BURNUP
CAPSULES
CARBON
CASTING
CORROSION
CRACKS
DEFECTS
EXPANSION
FUEL CANS
FUELS
HARDNESS
IRRADIATION
LABORATORY EQUIPMENT
MATERIALS TESTING
METALS, CERAMICS, AND OTHER MATERIALS
MTR
QUANTITATIVE ANALYSIS
QUANTITY RATIO
REACTORS
STABILITY
SURFACES
TESTING
THERMAL CONDUCTIVITY
URANIUM CARBIDES
VACUUM