Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

NUCLEAR ENGINEERING DEPARTMENT PROGRESS REPORT FOR JANUARY 1-MARCH 31, 1958

Technical Report ·
OSTI ID:4298408
An improved method of drying MgCl before making up ble U partition coefficient in salt-Bi equilibration. The activity coefficient of Zr in very dilute Bi solutions was found to be 7 x 10/sup -4/ at 7O0 C. Annealing of irradiated quartz optical cells at 500 C is reported. The behavior of fission products I and Xe in LMFR fuel systems was studied. Corrosion tests of several materials in fused salt mixtures are reported. The operation of five in-pile loops is reviewed. Bench contactor experiments are described. Rates of transfer of Sm from Bi-Mg-Sm alloy to the ternary eutectic salt mixture were measured for the case of small drops falling through a column of salt. The pumping and corrosive effects of thorium bismuthide slurries were studied. Corrosion of steel immersed in Bi-Mg-U-Zr alloy was evaluated. A number of measurements of neutron slowing-down and diffusion parameters were made with graphite, bismuth, and graphite-bismuth mixtures. Satisfactory dissolution media were found for the Enrico Fermi Fast Breeder core. A 15-ft-long clay column experiment with a simulated waste solution spiked with 2c Sr/sup 90/ gave a decontamination factor of 1.6 x lO/sup 8/. The mechanism of Y/sup 90/ bonding to an anion exchange resin wss deterrained. Reactor irradiation of LiOH produces no detectable 0/sup 20/ at currently available neutron fluxes. A satisfactory system was developed for milking As/sup 72/ from its Se/sup 72/ parent. A process for producing pure carrier-free Mo/sup 99/ was developed. (For preceding period see BNL-491.) (W.D.M.)
Research Organization:
Brookhaven National Lab., Upton, N.Y.
NSA Number:
NSA-13-001451
OSTI ID:
4298408
Report Number(s):
BNL-506
Country of Publication:
United States
Language:
English