QUARTERLY PROGRESS REPORT FOR CHEMICAL DEVELOPMENT SECTION B, JULY- SEPTEMBER 1962
UC dissolves in HNO/sub 3/ to give mixtures of soluble organic polycarboxylic acids. A tentative analysis is given for the acids resulting from the dissolution of UC in boiling 4 N HNO/sub 3/. The reactions of as-cast uranium carbides containing 2 to 10 wt% C with water were studied. The continuous dissolution of 2% U--Zr alloy fuel in a Ti dissolver was demonstrated using as dissolvent refluxing ted from Th/sup 228/ and its daughters by extracting from an acid feed and scrubbing with acid-deficient Al(NO/sub 3/)/sub 3/. The effects of nltrates on the dissolution of UO/sub 2/ pellets in HNO/sub 3/ were studied. No boron was leached from glass raschig rings containing 3.8 wt% B by solutions containing U, Th, and HNO/sub 3/. The Pa concentration of solutions containing Th, Pa/sup 231/ HNO/sub 3/ Al, and F- was stable over one month and remained unaffected by contact with stainless steel for 1 week. Removal of Pa from solutions by Vycor glass and silica gel was studied. Tests were run on the size distribution of UO/sub 2/ fines produced by a miniature hydraulic shear in the cutting unirradiated and irradiated clad UO/sub 2/. Corrosion studies were carried out for A'' nickel, Haynes 25, and INOR-8 in N/ sub 2/-CCl/sub 4/ and cyciic O/sub 2//Cl/sub 2/CCl/sub 4/ and for welded stainless steel and Corronel 230 in HNO/sub 3/- HF. Thermal stability of simulated high-sulfate Purex waste and glass fixations of simulated TBP-25 waste, and the corrosion of stainless steel by Purex waste and a salt mine were studied. The effects of phosphates and Na/sub 2/CO/sub 3/ in a synthetic low-level waste solution on the hardness of the effluent from a laboratory clarifier were studied. The precipitation of Ca and Mg from ORNL lowlevel waste and the removal of foaming agent from solutions were studied. The vapor pressures of TBP over its periments were made on the head-end precipitation in the laboratory-scale flowsheet for the precipitation-ion exchange method for the recovery of Sr from 1 WW Purex waste. The effects of gamma irradiation to a dose of 4.2 x 10/sup 8/ r on the hydroxyl form of Dowex 1 X-10 were studied under dynamic flow conditions. The partial reduction of BaSO/sub 4/, SrSO/sub 4/, CaSO/sub 4/, and MgSO/sub 4/ by H/sub 2/ was s tudied. (D.L.C.)
- Research Organization:
- Oak Ridge National Lab., Tenn.
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-17-010246
- OSTI ID:
- 4724125
- Report Number(s):
- ORNL-TM-403
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-63
- Country of Publication:
- United States
- Language:
- English
Similar Records
CHEMICAL TECHNOLOGY DIVISION, CHEMICAL DEVELOPMENT SECTION B MONTHLY PROGRESS REPORT, JANUARY 1960
CHEMICAL TECHNOLOGY DIVISION, CHEMICAL DEVELOPMENT SECTION B MONTHLY PROGRESS REPORT, MARCH 1960