Technology of Non-Production Reactor Fuels Reprocessing Budget Activity 2790. Quarterly Report

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Sawing studies were made using a dry function blade for cutting Zircaloy taking. An off-gas filtration system including a rotoclone and a filter assembly was installed to permit studying of the particulate material generated during the friction cutting operations. Studies of mechanical techniques for safety processing the Na or NaK alloy reservoirs present in some non-production fuels have continued. Stainless steel-clad swaged U0/sub 2/ rods and stainless steel- clad U- 10 wt.% Mo alloy rods were sheared under water to investigate the mechanical and particulate handling problems associated with these two major components of the power reactor fuels reprocessing program. … continued below

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20 pages

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Cooper, V. R. July 1, 1959.

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  • Hanford Atomic Products Operation
    Publisher Info: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
    Place of Publication: Richland, Washington

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Sawing studies were made using a dry function blade for cutting Zircaloy taking. An off-gas filtration system including a rotoclone and a filter assembly was installed to permit studying of the particulate material generated during the friction cutting operations. Studies of mechanical techniques for safety processing the Na or NaK alloy reservoirs present in some non-production fuels have continued. Stainless steel-clad swaged U0/sub 2/ rods and stainless steel- clad U- 10 wt.% Mo alloy rods were sheared under water to investigate the mechanical and particulate handling problems associated with these two major components of the power reactor fuels reprocessing program. The behavior of explosive U- Zr residues in the Zirflex Process was studied. In dissolution of stainless steel cladding from U0/sub 2/ it was found that a more rapid initial U0/ sub 2/ dissolution by H/sub 2/SO/sub 4/ occurred if the U0/sub 2/ was exposed to the atmosphere. Farther studies on the dissolution of ingot U and sintered U0/ sub 2/ in HNO/sub 3/ and HNO/sub 3/- ferric nitrate are reported. The dissolation of U-Mo alloys is being studied. The corrosion of 304-L stainless steel and Hastelloy-F in nitric acid-ferric nitrate systems was studied. Exploratory experiments were done attempting to define the effect of Al(NO/sub 3/ )/sub 3/ and HF on the formation of explosion sensitive surfaces during the dissolution of U - low Zr alloys. Studies of metallic U dissolution in dilute aqua regia were made. Niflex (HNO/sub 3/- HF) dissolution studies of 304 stainless steel were continued. (W.L.H.)

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20 pages

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  • Other Information: Decl. Aug. 5, 1959. Orig. Receipt Date: 31-DEC-60

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  • July 1, 1959

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  • Oct. 15, 2017, 10:09 p.m.

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  • Jan. 27, 2021, 2:15 p.m.

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Cooper, V. R. Technology of Non-Production Reactor Fuels Reprocessing Budget Activity 2790. Quarterly Report, report, July 1, 1959; Richland, Washington. (https://digital.library.unt.edu/ark:/67531/metadc1020723/: accessed July 7, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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