Progress Report on Refining of MgX and Other Uranium-Bearing Materials (open access)

Progress Report on Refining of MgX and Other Uranium-Bearing Materials

From abstract: "Results of two methods of reducing the phosphate and vanadate contents of MgX, a uranium precipitate from the Belgian Congo, are described...Chemical analyses of several samples of pitchblende and MgX are presented."
Date: August 31, 1950
Creator: Ewing, R. A.; Kiehl, S. J., Jr. & Bearse, A. E.
System: The UNT Digital Library
Enamels for the Protection of Aluminum Cans for Uranium Slugs (open access)

Enamels for the Protection of Aluminum Cans for Uranium Slugs

The following report examines the most suitable enamels recommended for protection of aluminum slug cans.
Date: August 31, 1955
Creator: Schultz, John; Tripp, Harlan P.; King, Burnham William, 1907- & Duckworth, Winston H.
System: The UNT Digital Library
Progress Report No. 37 for the Period June 1, 1955 through August 31, 1955 (open access)

Progress Report No. 37 for the Period June 1, 1955 through August 31, 1955

This is the thirty-seventh progress report of the Laboratory for Nuclear Science at the Massachusetts Institute of Technology. Progress during the period of June 1, 1955 through August 31, 1955 is reported on: (1) Chemistry of the fission elements group, (2) Nuclear chemistry (inorganic) group, (3) Nuclear chemistry (organic) group, (4) Cosmic ray group, (5) Elementary particle scattering group, (6) neutron physics group, (7) ONR generator group, (8) Radioactivity group, (9) Cyclotron group, (10) Synchrotron group, (11) Theoretical group, (12) Personnel listing.
Date: August 31, 1955
Creator: {{{name}}}
System: The UNT Digital Library
Distribution Coefficient of D₂O Between Triethylamine and Water (open access)

Distribution Coefficient of D₂O Between Triethylamine and Water

Summary: "Water containing 1.8% D2O was distributed between the two liquid phases formed with triethylamine at 20 and 35 C. The triethylamine was removed from each phase by aseotropic distillation with benzene before analyzing the water by determining its density with a quartz float. The ratios of the concentrations of the D2O in the water layer to that in the amino layer were 1.007 and 1.004 at 20 and 35, respectfully. The differences from unity are about the same as the errors of analysis."
Date: August 31, 1943
Creator: Carlson, H. C.
System: The UNT Digital Library
The Production of 320 Mev Deuterons By He3 Stripping (open access)

The Production of 320 Mev Deuterons By He3 Stripping

The purpose of this report is to describe a method of obtaining deuterons from the 184-inch cyclotron of higher energy than can be achieved from direct acceleration.
Date: August 31, 1953
Creator: Ise, John, Jr.; Pyle, Robert V.; Hicks, Donald A. & Main, Robert M.
System: The UNT Digital Library
Adsorption of Radioactive Gases on Activated Carbon (open access)

Adsorption of Radioactive Gases on Activated Carbon

The purpose of this experiment is to study the quantitative adsorption characteristics of a carbon adsorber bed receiving a radioactive inert gas in a helium stream. An objective of the experiment is to measure the equilibrium transmission of the radio-active gas through a carbon adsorber in order to determine if radio-active decay of the adsorbed gas permits additional adsorption.
Date: August 31, 1960
Creator: Madey, Richard; Barker, J. J.; Beebe, M. R. & Stephenson, T. E.
System: The UNT Digital Library
Pebble Bed Friction Factor and Thermal Expansion Tests (open access)

Pebble Bed Friction Factor and Thermal Expansion Tests

Tests were conducted to determine the friction factor of randomly packed beds of 3/4-inch diameter spheres in 8-inch and 15-1/4-inch diameter beds, and of 1-1/2-inch diameter spheres in 15-1/4-inch diameter bed. The bed depths were varied in an attempt to isolate the effects of entrance and exit losses. The bed Reynolds number, base on sphere diameter, was varied from 5,000 to 50,000.
Date: August 31, 1960
Creator: Leeman, C. A.
System: The UNT Digital Library
New Production Reactor Thermal Shielded Studies (open access)

New Production Reactor Thermal Shielded Studies

The relative neutron capture gamma production in several prospective iron thermal shielding materials for the New Production Reactor was measured to determine the merit of adding boron to the metal. It was found that for the beam geometry the used addition of 1 1/2 percent boron to the iron before casting reduced the soft gamma production by a factor of 6.5 and the hard gamma production by a factor of 10. No attempt was made to measure gamma or neutron transmissions.
Date: August 31, 1959
Creator: Friesenhahn, S. J.
System: The UNT Digital Library