PROMPT RADIATION EFFECTS ON CABLES AND LINEAR POWER INSTRUMENTATION CHANNELS (open access)

PROMPT RADIATION EFFECTS ON CABLES AND LINEAR POWER INSTRUMENTATION CHANNELS

Tests were conducted to determine the amount of error introduced in reactor power data by radiation-induced voltages in cables and electrometer preamplifier chassis. The results, obtained near the central exposure facility of the KEWB (Reacter Safety Experiments), showed no observable radiation effects under the conditions of present use. Cable insulation resistance was measured during the radiation bursts. (C.J.G.)
Date: June 12, 1959
Creator: Harris, S.P. & Gardner, E.L.
System: The UNT Digital Library
EQUILIBRIUM CALCULATION IN THE SYSTEM: URANYL NITRATE, NITRIC ACID, WATER, TBP, AND KEROSENE DILUENT USING THE ORACLE DIGITAL COMPUTER (open access)

EQUILIBRIUM CALCULATION IN THE SYSTEM: URANYL NITRATE, NITRIC ACID, WATER, TBP, AND KEROSENE DILUENT USING THE ORACLE DIGITAL COMPUTER

A set of equations was written which allowed the calculation of equilibrium concentrations in the solvent phase of nitric acid and uranyl nitrate, given the initial TBP concentration in the solvent and the aqueous phase concentrations of acid and uranium. An ORACLE subroutine was written based on these equations which will calculate a set of equilibrium values in about 35 milliseconds. The subroutine was incorporated into a short program to calculate equilibrium points. A set of calculated points are presented in graphical form for 5, up to 7 M and uranyl nitrate concentrations up to 0.6 M in the aqueous phase. Since these calculations were based on limited data, it is the purpose of this memo to invite comment on their accuracy. The equations were reworked from a Russian paper by A. M. Rozen and L. P. Khorkhorina, using emperical polynomial fits for some poorly defined parameters, and were based principally on data from J. W. Codding. This project was undertaken to provide a subroutine to calculate equilibria in a general purpose ORACLE program to calculate the performance of multi-stage compound extraction cascades with more than one significant solute. (auth)
Date: August 12, 1959
Creator: Jury, S. H. & Whatley, M. E.
System: The UNT Digital Library
EFFECT OF TRANSFER TIME ON THE RECRYSTALLIZATION BEHAVIOR OF BETA-COOLED URANIUM (open access)

EFFECT OF TRANSFER TIME ON THE RECRYSTALLIZATION BEHAVIOR OF BETA-COOLED URANIUM

A study was made of the recrystallization behavior of beta-quenched uranium by incorporating the effects of transfer time from the beta heat-treating bath to the quench media. A critical transfer lime which relates to the time required to immerse samples at a temperature above the beta-alpha transformation in a quench media directly affects the beta-cooled structure and its ease of recrystallization upon alpha phase annealing. Within the critical transfer time, the ease of recrystallization and degree of grain refinement of beta-cooled samples as measured by alpha-phase annealing temperatures and times are superior to samples quenched beyond the critical transfer time. (auth)
Date: January 12, 1959
Creator: Carloni, Q. C. & Lewis, L.
System: The UNT Digital Library