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U.S. Department of Energy
Office of Scientific and Technical Information

HIGH PERFORMANCE UO$sub 2$ PROGRAM QUARTERLY PROGRESS REPORT NO. 6, JULY- SEPTEMBER 1962

Technical Report ·
OSTI ID:4693330
The experiment for direct measurement of fission-gas pressure was terminated at the VBWR shutdown on September 12, 1962. Evidence indicated that practically 100% of the fission gas is released in that volume fraction of the fuel rod calculated to be operating at a temperature above 1700 un. Concent 85% C. Four irradiations were carried out in the GETR pressurized-water loop. All fuel rods in two assemblies irradiated showed marked swelling of the cladding. The extent of the swelling was directly related to the fuel rod thermal performance. A fuel assembly was fabricated with UO/sub 2/ pellets containing a small central hole in an effort to eliminate clad swelling. When UO/sub 2/ was heated in a tungsten crucible above 2800 un. Concent 85% C migration of tungsten into UO/sub 2/ and UO/sub 2/ into tungsten occurred. (M.C.G.)
Research Organization:
General Electric Co. Atomic Power Equipment Dept., Cincinnati
NSA Number:
NSA-17-022219
OSTI ID:
4693330
Report Number(s):
GEAP-3771-6; EURAEC-503
Country of Publication:
United States
Language:
English