CHEMICAL TECHNOLOGY DIVISION, CHEMICAL DEVELOPMENT SECTION B MONTHLY PROGRESS REPORT, JUNE-JULY 1960

The effect of two neutron poisons, baron and cadmium, on the rate of dissolution of high-density 95% ThO/sub 2/-5% UO/sub 2/ pellets in the Zirflex Process was determined. Dissolution of U-10% Mo alloy in boiling HNO/sub 3/ resulted in a precipitation of uranyl molybdates. Air caused greater uranium and thorium losses during decladding of ThO/sub 2/-UO/sub 2/ fuel than irradiation. Processing of U-Mo fuel by a Zircex type process is discussed. Two leaches of graphitized fuel with 90% HNO/sub 3/ recovered more than 99% of the uranium. Irradiation of synthetic ThO/sub 2/-UO/sub 2/ fuel solution to 5 and 10 watt-hr/l in a Co/sup 60/ source resulted in about a 50% decrease in decontamination factor using the acid-Thorex flowsheet. Corrosion of titanium, tantalum, and Ni-o-nel in Thorex solution and titanium corrosion in various molybdenum core alloy solutions were investigated. The solubilities of ferric mono- and dibutyl phosphates in HNO/sub 3/ and 30% TBP-Amsco-HNO/sub 3/ solutions were determined. Fission product concentrations expected in Purex waste from processing Yankee Atomic Reactor fuel were calculated. Chemical applications of nuclear explosions to H/sup 3/ exchange, reduction of CaSO/sub 4/, and Gnome sampling are discussed. (For preceding period see CF-60-6-108.) (M.C.G.