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The solvent-extraction performance of small scale redox IA columns using Fenske helix packing, ammonium nitrate salting agent, and unirradiated uranium

Description: A report which deals with the Redox IA Column studies made in small-scale columns packed with 3/16-in. Fenske helices and using NH4NO3 salting agent.
Date: April 13, 1949
Creator: Woodfield, F. W.; Bradley, J. G.; Switzer, W. O. & Merrill, E. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Applied Potential Corrosion of Aluminum and 18-8 Stainless Steel Alloys

Description: Introduction: In anticipation of the design of equipment for heat transfer tests, a series of short exposure corrosion tests was initiated in an effort to determine the order of magnitude of the corrosion involved. Information was required on the effect on corrosion rates of applying a potential between two concentric tubes, the annulus between them containing condensate water.
Date: March 13, 1930
Creator: Sanborn, Kenneth L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Corrosion Tests : SAE 1010 Mild Steel in Synthetic Neutralized Redox Waste Solution

Description: From introduction: "This report gives the results of a 1000-hour corrosion test of SAE 1010, low carbon steel, in synthetic Redox waste solutions...The present test was designed to obtain corrosion rates for waste solution temperatures of 180 F, 200 F, and 220 F in solutions neutralized to pH values of 11, 12, and 13.
Date: November 13, 1952
Creator: Endow, Noborn
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford Works Analytical Manual for Reactor Process Water

Description: Purpose: "The Hanford Works Analytical Manual for Process Water is designed to specify the analytical methods to be applied for control purposes in the Reactor Section, Process Sub-Section laboratories. The procedures are in general form and serve as references rather than outlined laboratory instructions. The manual us designed to replace the "Hanford Works Manual," HW-12862."
Date: February 13, 1953
Creator: Hanford Works
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experimental Rolling of Uranium : Lackawanna No. 3

Description: The following report is one of a series of rolling tests to establish the rolling process for Feed Materials Production Center at Fernold, Ohio. The primary objective of this program is to find a mechanically feasible process for continuous rolling of uranium.
Date: December 13, 1951
Creator: Riches, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Decontamination of the Irradiated Rupture Prototype with Peroxide-Carbonate and Apace

Description: Considerable work has been done on decontamination procedures for both corrosion products and fission products. Testing of promising procedures under typical rupture conditions is an important phase of this work. The Irradiated Rupture Prototype (IRP) has been used since August in this evaluation work. This document is one of a series reporting these data.
Date: January 13, 1960
Creator: Neibaur, G. E. & Weed, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design, Development and Research Contract DDR-33

Description: This report summarizes experimental results obtained for the General Electric Company under terms of Design, Development and Research Contrast DDR-33. A discussion of the results, the manner in which they were obtained and their probable accuracy are included. Suggested improvements or modifications of properties of this nature be contemplated.
Date: March 13, 1958
Creator: Johanson, L. M.; Campbell, Robert J. & Mueller, Edward E
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary Report - Pump and Agitator Development 1959

Description: A part of the development activities of the Process Equipment Development Group, Chemical Development, HLO through the year 1959 has consisted of test evaluation of some of the never products of manufacturers, design and refinement of novel units to do certain specialized jobs and development of improved components for existing plant equipment. Modification of present chemical processing methods and investigation of new basic procedures have made it necessary to utilize different and "exotic" m… more
Date: January 13, 1960
Creator: Dunn, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Scintillation Nuclear Incident Alarm Monitor

Description: This report was written to describe the instrument and test results obtained. It is understandably imperative that such alarming devices be incorporated in various areas of the plant to provide an alarm or warning for increasing dose rate from gauss radiation fields.
Date: March 13, 1959
Creator: Spear, W. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Multi-Region Simulation of Xenon Poisoning in the PRTR

Description: A previous study has been completed on the buildup and decay of xenon poisoning in the PRTR by simulating the reactor as a single region. The results of this study indicated that a study using a more refined model of the reactor would be valuable.
Date: April 13, 1959
Creator: Cameron, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Rates of Reaction of Irradiated UO2 and Uranium Metal with Sulfuric Acid

Description: In the decladding of stainless steel clad fuel elements with sulfuric acid (the Sulfex process), the loss of core material to the decladding solution is determined by the rate of reaction of the core material with the solution and the time of exposure if the core to the solution. Since very little was known about the effects of irradiation history on the rates at which core materials dissolve in sulfuric acid, the present study was undertaken in an effort to determine the magnitude of such effe… more
Date: August 13, 1959
Creator: Swanson, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Status Report on the Hanford Developed Tester for the Coextruded Fuel Elements

Description: In October 1959, a combination testing station developed at HAPO was reported to the Sheath committee. This testing station consisted of electronic instrumentation and mechanical scanning equipment to check coextruded fuel elements (rod and tube) for clad thickness, clad integrity, bond, and core integrity. The clad tests are performed by eddy current methods and the other are ultrasonic.
Date: April 13, 1960
Creator: Lambert, T. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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