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Title: NUCLEAR ENGINEERING DEPARTMENT, PROGRESS REPORT, SEPTEMBER 1-DECEMBER 31, 1960

Technical Report ·
OSTI ID:4840741

BS>H 7 : Progress is reported for various projects in reactor theory and physics. Data are given for the total neutron and activation cross sections of Dy/sup 164/ as a function of neutron energy. Chemistry and Chemical Engineering. Some radiation research projects are reported. The yields of gas and polymer from radiolysis of C/sub 6/F/sub 16/ and C/sub 8/F/sub 16/ were determined. High-temperature galvanic cells were used at 700 to 950 deg C to measure the thermodynamic properties of ThC/sub 2/. No evidence of complex formation was found in the u-v spectra of KCl-PbCl/sub 2/ mixtures. The effect of Na/sup +/ ions on the extraction of Cs polyiodides from aqueous solutions containing NaI into solutions of I/sub 2/ in nitrobenzene was studied. Breakthrough curves were determined for the adsorption of Xe and Kr on activated charcoal, and the effects of temperature and gas velocity on the adsorption were studied. The I/sub 2/ adsorption isotherm on graphite was calculated for 1000 deg C, and several experiments were performed to test the equilibration speed of the I/sub 2/-graphite system at 1000 deg C. Graphite-Re thermocouples were tested at temperatures up to 2100 deg C, and their thermoelectric characteristics are given. Studies are reported for waste disposal by incorporation in phosphate glasses. Preliminary results are given for radiolytic product yields from aqueous NH/sub 3/, ethylene, CO/sub 2/, and U -hydrocarbon gas. Studies were performed on the removal of U from inert A1/sub 2/O/sub 3/ beds. A number of experiments were conducted on the dissolution of stainless steel-clad UO/sub 2/ and ceramic BeO-U oxide fuels in NO/sub 2/-HF in the Nitrofluor process. Teflon 100 or Teflon FEP was found to be very resistant to NO/sub 2/-HF. Liquid N/sub 2/ O/sub 4/ irradiated with 5.6 x 10/sup 8/ r gamma rays over 4 months was found to have suffered only negligible decomposition. A study was made of the vapor pressurecomposition-temperature relationships of the NO/sub 2/-HF system. H/sub 2/PO/sub 3/F was found to be a good solvent for sintered ThO/sub 2/-UO/sub 2/ fuel, and the versatility of H/sub 2/PO/sub 3/F as a solvent for other fuels was studied. The diffusivity of Te in Al was determined to be approximately 3 x 10/ sup -9/ cm/sup 2//sec at 500 deg C. Meltdown experiments on U-Mo alloys indicate that I is released from the alloys independently of Te. Heat transfer rates measured on the new loop for the flow of Hg through unbaffled rod bundles and results of an analytical study of heat transfer to liquid metals flowing in concentric annuli are reported. Hot Laboratory. Progress is reported on production of Ca/sup 47/, I/sup 124/, Ar/sup 38/, Ga/sup 68/, Mg/sup 28/ , Li/sup 6/D, I/sup 132/, and Sc/sup 48/. Experiments on the effects of tri-n-octylamine on the extraction of Th by thenoyltrifluoroacetone are reported. The standard potentials of four metal ion -metal systems in a sulfate eutectic were determined. Electrochemical studies of fused salts are reported. Other aspects of the hot laboratory operation, e.g., radioisotope production and wastes, are discussed. Metallurgy. The operation of loops and capsules for testing materials in liquid metals is described. Pure Fe was obtained by vacuum melting in an A1/sub 2/O/sub 3/ crucible in a Ta-gettered furnace. Heating to 800 deg C for 30 hr resulted in complete removal of entrapped Xe from irradiated UBi/sub 2/ dispersed in Bi. The thin liquid film technique combined with mechanical polishing was successful in depositing uniform Zr films of reproducible thickness on 21/4 Cr-1 Mo steel surfaces from liquid BiZr alloys. The solubilities of Al and Lu in liquid Bi were determined. A partition function is presented for liquid metallic solutions that form no solid solutions or intermetallic compounds. The operation of the Brookhaven Graphite Research Reactor Radiation Loop is discussed briefly. Radiation effects on the low-temperature properties of pure Fe were studied. The stored energy in the Medical Research Reactor graphite was measured. The growth and recovery of the Graphite Research Reactor graphite after the 14th and 15th anneals are reported. Surface area meas

Research Organization:
Brookhaven National Lab., Upton, N.Y.
DOE Contract Number:
AT(30-2)-GEN-16
NSA Number:
NSA-15-030331
OSTI ID:
4840741
Report Number(s):
BNL-659
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-61
Country of Publication:
United States
Language:
English