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Fuel Cycle Program. A Boiling Water Reactor Research and Development Program. Eighth Quarterly Progress Report, April-June 1962
A frequency analysis was made of the VBWR stability test data. Interpretation of the steady-state noise observed in the stability tests involved consideration of several possible sources of excitation. One of these, a theory of water surface waves, is summarized. Visual and destructive examinations were made of selected fuel rods. Fretting corrosion of the Zircaloy-clad fuel rods against stainless steel spacers was observed. Evidence that UO/sub 2/ thermal conductivity increases with time was obtained. Hot gas isotatic pressed fuel rods failed after 316 Mwd/T irradiation and 5 months storage under water. Shakedown operation of a 7-rod test section for measuring burnout heat flux was conducted. A comparison of measured and calculated isotopic composition for uranium and plutonium isotopes after 400 Mwd/T irradiation indicated that the calculations underestimate capture in U/sup 238/ and overestimate capture in Pu/ sup 239/. Flux wire irradiations provided axial and radial flux profiles and the ratio of thermal to fast flux as a function of axial position. (M.C.G.)
Date:
July 10, 1962
Creator:
Hodde, J.A. comp.
System:
The UNT Digital Library
Fuel Cycle Program Progress Report: Twelfth Quarter, April-June 1963
Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities
Date:
July 5, 1963
Creator:
Howard, C. L.
System:
The UNT Digital Library
Fuel Cycle Program Progress Report: Fifteenth Report, January-June 1964
Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities.
Date:
July 15, 1964
Creator:
Howard, C. L.
System:
The UNT Digital Library