Chemical Separation of Isotopes Section Semiannual Progress Report For Period Ending December 31, 1954 (open access)

Chemical Separation of Isotopes Section Semiannual Progress Report For Period Ending December 31, 1954

New systems involving the exchange of boron between boron trifluoride and boron trifluoride addition compounds have been explored. These systems have large separation factors and potentially simple reflux mechanisms. A precise determination of this separation factor for the anisole-boron trifluoride system gave the value (see report). Boron exchange was found to occur between BF and BCl3. Several homogenous catalysts have been found which activate the hydrogen-water exchange, but none are adoptable to the production of deuterium because of the slow exchange rate. Platinum or platinum oxide may be usable as a heterogeneous catalyst with proper support or dispersion techniques. The high-pressure solubility of hydrogen in several amalgams was investigated in connection with a unique countercurrent exchange system. A proposed system involving isotopic exchange between lithium dipivaloylmethane in diethyl ether and lithium hydroxide in aqueous solution was shown to give little or no isotopic separation. Column studies of the carbonate system exchange reaction were concluded with a 40°C run. Slightly higher enrichment of N15 was obtained than at 30°C . The temperature dependence of all in this system was measured between 15 and 45°C. The factor increases with temperature, showing a tendency toward a maximum near 45°C. Isotopic exchange appears to …
Date: May 20, 1955
Creator: Clewett, G. H & Drury, J. S.
System: The UNT Digital Library
Stress Corrosion in the HRT Mockup (open access)

Stress Corrosion in the HRT Mockup

Stress corrosion was found in 8 components of the HRT mockup; only of four of these actually shut down the loop. All of the failures have occurred in the high-pressure system of the loop.
Date: May 20, 1957
Creator: Harley, P. H.
System: The UNT Digital Library
Nuclear and Radiation Hazards Evaluation of SRE Fuel Processing and Storage (open access)

Nuclear and Radiation Hazards Evaluation of SRE Fuel Processing and Storage

Nuclear and radiation hazards have been investigated for all phases of operation to be carried out in the mechanical decladding of SRE fuel elements. The SRE fuel is 2.8% enriched with a maximum burnup of 1,000 Mvd/ton and minimum cooling of 120 days. Each element contains 9 kg of uranium metal (~2 kg U-235) and is made up from 84 slugs (3/4"D x 6'"), clad with (10 mil wall) stainless steel tubing. It is planned to ship the fuel from Santa Susana, California, to Oak Ridge in the modified PAR loop carriers, with a maximum of 10 elements being shipped in each carrier per trip.
Date: May 20, 1959
Creator: Suddath, J. C.
System: The UNT Digital Library