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• W4240043800 abstract "core materials are discussed, and fuels for future PRTR and PCTR loadings are being studied. Preliminary results of Zircaloy-2 clad fuel elemert magnetic force butt welding were evaluated, and results are encouraging. Sintered and compacted powders produced by a vibration system were found to be ertirely acceptable. Effects of swaging on various types of cladding are being evaluated, and a method of testing Zircaloy-2 tubes prior to swaging was developed. In fuel evaluation a 3 ft long UO/sub 2/ rod and tube element which ruptured after reinsertion in ETR was examined. Results indicate that the failure may be due to restriction of the outer cladding coolant annulus by one or more thermocouples. Observations on an irradiated cored and sintered U0/sub 2/ fuel element after failure are listed. Test results of two 18 in. long 7-rod UO/sub 2/ cluster elements indicate that no ruptures occurred in a KER loop test. Corrosion studics include those for allowable Zr concentrations in HNO/sub 3/--HF PRTR fuel element etch bath and a dynamic bath for etching and autoclaving PRTR rod clusters. Rupture testing of simulated Al-Pu fuel elements is reported in a 30-hr, 300 test. No swelling or deposit buildup was noted. All PRTR Zircaloy tacket tubing was examined by use of a fluorescert penetrant dye. Heat transfer experiments are reported in which the heat flux at which boiling burnout in PRTR is expected are reported. Progress in mechanical equipment developmert is summarized. Included are data on a 405-hr test of a PRTR primary process pump, results of calandria mock-up tests, seal testing results, and results of Inconel X loop tests. Compilation of data and charts of input reactivity for the various transient cases to be studied on the analog computer were completed. The various cases are described. Hazard studies for various PRTR mechanical failures are summarized. Included are consideration of the effects of 14-in. header failure, maximum pressure of a shroud tube following a process tube rupture, and flow decay and equilibrium conditions following complete loss of a single primary coolant pump. A summary of the PRTR construction phase status is given along with discussion of other design progress related to PRTR and the Pu fabrication plant. Activities in PRTR planning included work on a PRTR technical manual, an operations handbook, and design of a data processing system. Tests indicate that loss of Pu to the NH/sub 4/F--NH/sub 4/NO/sub 3/ decladding solution can be reduced by treatment of the Pu core with HNO/sub 3/ before it is encased. Reduction of UO/sub 2/Cl/sub 2/ resulting from exposure of UO/sub 2/ and U/sub 3/O/sub 8/ to molten chloride salt is being studied. Reduction is complete; the UO/sub 2/ appears as a crystalline particle in the 30 to 300 mesh range. Other developments include preliminary Hg isotope separation, fabrication of an automatic ball mill feed controller, fluid bed ion exchange studies, and investigation of certain boiling metal characteristics. Simulated swelling experiments by measuring the diffusion of rare gases in uranium are in progress along with experiments to determine U pore size distribution Results of graphite oxidation experiments using CC2 are" @default.
• W4240043800 created "2022-05-12" @default.
• W4240043800 creator A5038881587 @default.
• W4240043800 date "1969-05-31" @default.
• W4240043800 modified "2023-09-28" @default.
• W4240043800 title "FFTF FUELS DEVELOPMENT CURRENT PRELIMINARY DATA REPORT FOR MAY 1969" @default.
• W4240043800 doi "https://doi.org/10.2172/1089653" @default.
• W4240043800 hasPublicationYear "1969" @default.
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