Separation of Azeotropes by Means of Diffusion through Porous Membranes (open access)

Separation of Azeotropes by Means of Diffusion through Porous Membranes

Thesis discussing experiments to separate azeotropes into pure components testing eleven minimum boiling point azeotropic systems: (1) acetone-methanol, (2) carbon tetrachloride-ethyl acetate, (3) cyclohexane-ethanol, (4) benzene-isopropanol, (5) benzene-n-propanol, (6) benzene-cyclohexane, (7) benzene-methanol, (8) benzene-ethanol, (9) acetone-carbon, (10) isopropoanol-water, and (11) ethanol-water.
Date: October 1953
Creator: Hagerbaumer, Donald H. & Kammermeyer, Karl
System: The UNT Digital Library
Facilities for Irradiation Within the MTR Reactor Tank (open access)

Facilities for Irradiation Within the MTR Reactor Tank

Information on experimental facilities and reactors.
Date: June 5, 1953
Creator: Leyse, C. F.
System: The UNT Digital Library
Practical Reactor Theory (open access)

Practical Reactor Theory

Derivation and basic formulas the physicist or nuclear engineer needs to do the necessary nuclear calculation for a reactor design.
Date: October 21, 1953
Creator: Webster, J. W.
System: The UNT Digital Library
Scintillation Hand and Foot Counter (open access)

Scintillation Hand and Foot Counter

From abstract: "The design of a scintillation counter for measuring radioactive contamination of hands and feet is described."
Date: January 27, 1953
Creator: Goldsworthy, William
System: The UNT Digital Library
Operation and Maintenance Instructions for Gamma Scintillation Monitor - Model 3 (open access)

Operation and Maintenance Instructions for Gamma Scintillation Monitor - Model 3

Gamma scintillation monitor Model 3 is designed to continuously monitor and record the gamma activity of a process solution.
Date: October 1, 1953
Creator: Connally, R. E.
System: The UNT Digital Library
Radiation Damage in Boron Carbide (open access)

Radiation Damage in Boron Carbide

From introduction: "Report describing the study of radiation damage in boron carbide with an integrated thermal neutron flux of 3x10^20 neutrons/cm² in the Materials Testing Reactor (MTR)."
Date: August 18, 1953
Creator: Tucker, Charles W., Jr. & Senio, Peter
System: The UNT Digital Library