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Curve Plotting Routine for the Oracle

Description: A general program has been written to plot curves on the Oracle curve plotter. A description of the code and complete instructions for preparation of input tapes and operation of the code are given. The code tape is available from the Mathematics Panel or from the author.
Date: April 11, 1957
Creator: Lietzke, M. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Brief Review of thermal Gradient Mass Transfer in Sodium and NaK Systems

Description: The fact that material transport does occur under conditions of finite temperature difference in a flowing molten metal system was established. The rate mass transfer was thought to be either diffusion limited or solution rate limited. It is believed that the mass transfer of structural materials in Na or NaK systems is solution rate limited. The limiting process has not been qualitatively or quantitatively confirmed for the Inconel-Na or Inconel-NaK system. Increasing the maximum system wall t… more
Date: February 11, 1957
Creator: DeVan, J. H. & West, J. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Two Group Calculations for Flux Distribution and Critical Mass in Clean Cold ORR Cores

Description: A series of two-group calculations has been made on the Oracle for the purpose of obtaining critical-mass and flux distribution data for various ORR core configurations. The 3G3R code of Bate, Einstein, and Kinney was used, together with the RSP code developed by Nelson. This made it possible to obtain results for the three-dimensional case. The results, which are presented graphically, are intended to serve as a guide for the design of experiments until such time as actual measurements are ava… more
Date: March 11, 1958
Creator: Binford, F. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Cross Sections for OCUSOL-A Program

Description: The OCUSOL-A program (ORNL-CF-57-6-4) for Univac is a modification of the Eyewash (ORNL-1925) multi-group, multi-region reactor code. The group=energy-lethargy-temperature relationship are given in Table A. The element code numbers are given in Table B. The cross sections now on the sigma-tape are given in tables in the Appendix numbered with the element code number. This technical report explains the bases for choosing the cross sections.
Date: June 11, 1957
Creator: Roberts, J. T. & Alexander, L. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Reaction of Zirconium with Uranium Dioxide

Description: An investigation of the causes of observed explosive reaction of zirconium-coated uranium dioxide on dissolution in nitric acid was conducted. It was concluded that such a reaction is to be expected. Possible but unconfirmed methods of alleviating the problem are suggested.
Date: June 11, 1957
Creator: Robinson, M. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
captions transcript

[Flirting With Power: 1st presidential debate, 1 of 2]

Description: Video footage from the Jo Streit Film Footage Collection consisting of original Betacam footage from filmmaker Jo Streit's documentary "Flirting with Power." Footage includes Ross Perot's campaign staff organizing before the debate, watching the broadcast, and afterwards standing on a stage as Perot delivers a speech.
Date: October 11, 1992
Duration: 1 hour 34 minutes 14 seconds
Creator: Streit, Jo
Item Type: Refine your search to only Video
Partner: UNT Libraries Special Collections
captions transcript

[Flirting With Power: 1st presidential debate, 2 of 2]

Description: Video footage from the Jo Streit Film Footage Collection consisting of original Betacam footage from filmmaker Jo Streit's documentary "Flirting with Power." Footage covers Ross Perot answering questions at a rally after the first presidential debate.
Date: October 11, 1992
Duration: 21 minutes 33 seconds
Creator: Streit, Jo
Item Type: Refine your search to only Video
Partner: UNT Libraries Special Collections
open access

Determination of the S. S. N. M. Content of the Shipment to the Davison Chemical Company, Erwin, Tennessee, December 20, 1960

Description: A carrier containing 138.99 liters of solution, uranium concentration 202.04 g/liter with an isotopic concentration of 97.3% U-233, was prepared for shipment. The total uranium was 28,062 +/- 60 g (95% confidence level) and the U-233, 27,305 +/- 66 g (95% confidence level).
Date: January 11, 1961
Creator: Sadowski, G. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experiments on the Release of Fission Products from Molten Reactor Fuels

Description: Experiments in the controlled melting of irradiated fuel specimens, particularly of the APPR, STR, and MTR types, have confirmed that prolonged heating in air at temperatures in excess of the melting point results in the release of a large portion of the radioactivity. On the other hand, a moderate amount of heating in air or steam sufficient only to melt a specimen results mainly in the partial volatilization of rare gases, iodine, bromine, cesium, and rubidium. In the presence of air or water… more
Date: March 11, 1958
Creator: Parker, George W. & Creek, George E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Preliminary Study of Pre-Solvent Extraction Treatment of Stainless Steel-Uranium Fuels with Dilute Aqua Regia

Description: The continuous dissolution of 304 stainless steel and stainless steel-UO2 alloy in dilute aqua regia was studied with subsequent stripping of the dissolver product to remove chloride ion. The process has the advantage of producing, by means of a simple head end treatment, a solvent extract feed in a conventional nitric acid medium so that existing solvent extraction processes, materials of construction and waste disposal methods can be used. The purposes of this study were to investigate the va… more
Date: October 11, 1957
Creator: Kitts, F. G. & Perona, J. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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