HIGH PERFORMANCE UO$sub 2$ PROGRAM. Quarterly Progress Report No. 5, April- June 1962

Technical Report · Fri Jun 01 04:00:00 EDT 1962

OSTI ID:4703205

Weidenbaum, B

Three fuel rods containing UO/sub 2/ pellets, all equipped with pressure sensing transducers, are being irradiated in the VBWR. The pellets for each rod have a density of 98% and an enrichment of 3.9%; 98% and 7.0%; and 93% and 3.8%, respectively. The pressure build-up in the pellet rods with low enrichment UO/ sub 2/ still remains fairly constant at a low value. The pressure build-up in the pellet rod with high enrichment UO/sub 2/ is now 180 psig at an estimated burnup of 2200 MWD/T with reactor power at 26 MW. Pre-irradiation shakedown of the pressurized water loop was completed with non-fueied assemblies. The loop water chemistry specifications were modified to reduce the likelihood of crud deposition on the fuel rods; alterations necessary to effect these new coolant specifications were completed. Installation of the underground tank system for high level liquid waste was completed and the system is operational. The PWL operated with fueled assemblies during GETR Cycles 33 and 34 without incident. The peak surface heat flux during the irradiation of pellet fuel assembly EPT-6 for one cycle in the PWL was 645,000 Btu/hr-ft/sup 2/. Some axial warpage and swelling in the peak heat flux region hampered the removal of the fuel rods from the shroud tubes in the assembly. The peak surface heat flux during the irradiation of pellet fuel assembly EPT-8 for one cycle in the PWL was 900,000 Btu/hr-ft/sup 2/. The irradiation of pellet fuel assembly EPT-10 was begun with a peak surface heat flux of 1,050,000 Btu/hr-ft/sup 2/ at start-up. Positive evidence of UO/sub 2/ melting was found in Trail Cable Capsule No. 6. Analysis of the results from the three Trail Cable capsules is continuing in an effort to derive the pelletcladding interface conductivity, the variation of the interface conductivity with surface heat flux, the thermal conductivity of UO/sub 2/ at 3,000 to 5,000 deg F, and the surface heat flux required to induce UO/sub 2/ melting in the capsule. (auth)

• Research Organization: General Electric Co. Atomic Power Equipment Dept., San Jose, Calif.
• NSA Number: NSA-17-028429
• OSTI ID: 4703205
• Report Number(s): GEAP-3771-5; EURAEC-489
• Country of Publication: United States
• Language: English

Related Subjects

BURNUP
CHEMICAL REACTIONS
DEFORMATION
DENSITY
DEPOSITS
ENRICHMENT
FUEL CANS
FUEL ELEMENTS
HEAT TRANSFER
IRRADIATION
MELTING
PELLETS
PERFORMANCE
POWER
PRESSURE
REACTOR TECHNOLOGY
RESEARCH REACTORS
SURFACES
THERMAL CONDUCTIVITY
TRANSDUCERS
TUBES
URANIUM DIOXIDE
VBWR
WASTE PROCESSING
WATER COOLANT