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Analytical procedures for the plutonium Metal Fabrication Process

Description: A report describing a the results of a fluorimetric and volumetric method for the determination of fluoride. This method was developed for the determination of ionizable fluorine in gases in the range of 1-500ppm. This method was chosen because the determination depends on the generation of a color rather than the bleaching effect or on a change of color.
Date: January 15, 1951
Creator: Kendall, L. F.
Item Type: Refine your search to only Report
open access

The Anodizing of Zirconium

Description: Five continuous coatings were produced on zirconium coupons using an anodizing technique. These layers appear to be quite adherent and not subject to visible or audible failure caused by flaxion of the basis metal, Their abrasion resistance, though not investigated thoroughly, appears to be moderately good.
Date: November 3, 1953
Creator: Ray, William E.
Item Type: Refine your search to only Report
open access

APDAC-I, A PCTR Data Analysis Code for the IBM 709

Description: A flexible foil data processing program is described. Raw data on foil radioactivity are the basic input information required. Output may consists of relative activities, saturated activities, and/or cadmium ratio and flux spectrum data. A statistical analysis of the data is executed with the direct calculation, and errors estimated for the output data.
Date: September 7, 1960
Creator: Lilley, J. R.
Item Type: Refine your search to only Report
open access

Application of Plastic Bags and Sheeting for Operation and Maintenance Across a Contamination Barrier

Description: The following document describes the usage of Vinylite or plastic sheeting for operation and maintenance across a contamination barrier, presenting ecological advantages, photos of special equipment and techniques used during procedure, and the purpose of eliminating open air transfer in contaminated area.
Date: 1952
Creator: Moulthrop, H. A.
Item Type: Refine your search to only Report
open access

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
open access

An Aqua Recia Flowsheet for Uranium Dissolution

Description: Relatively long time cycles are required for the standard nitric acid dissolution of enriched uranium using safe batch size techniques for criticality control. Upwards of forty eight hours are required for the total dissolution of solid of I and E enriched slugs in nitric acid. The dissolution capacity may be increased by: (1) using a dissolver critically safe by virtue of its geometry or, (2)increasing the rate of uranium dissolution. Dilute agua regia -- a mixture of hydrochloric and nitric a… more
Date: July 21, 1959
Creator: Shefcik, J. J.
Item Type: Refine your search to only Report
open access

Artificial Cooling of the Columbia River By Dam Regulation Part 1

Description: In early July, 1958, it appeared that Columbia River temperature at HAPO would be near 24.5ºC by the end of August. River temperature were averaging 4º to 5º above 1957 figures and were 3º to 4º above the ten year highs. It seemed desirable to examine the problem to determine if any corrective measure could be taken, since it was apparent that production losses were imminent.
Date: May 25, 1959
Creator: Kramer, H. A.
Item Type: Refine your search to only Report
open access

Autoclave Corrosion Behavior of U-Low Carbon and U-Low Zirconium Alloy Fuels

Description: A preliminary evaluation of the autoclave corrosion behavior of a series of U-low C alloys and a series of U-low Zr alloys prepared by Fuels Fabrication Development Operation has been made. The corrosion testing was conducted by Coatings and Corrosion Operation by the experimental methods and procedure outlined in HW-61378.
Date: December 1, 1959
Creator: Goffard, J. W.
Item Type: Refine your search to only Report
open access

An Automatic Polarograph for the Determination of Uranium in Process Waste Streams

Description: The automatic polarograph is ideally suited for the analysis of waste streams for uranium in the Metal Recovery Process, and with modification, it is applicable to other processes, pilot plants, and even to laboratory set ups. The instrument is simple, dependable, and relatively trouble free in operation. It provides an immediate record of the uranium in the waste and, through better control of the process, lower processing costs.
Date: December 10, 1953
Creator: Koyama, K.; Michelson, C. E. & Alkire, G. J.
Item Type: Refine your search to only Report
open access

An Automatic Water Deaeration System

Description: Laboratory studies involving fluid flow through porous media require use of fluids having low dissolved gas content. Water is the major fluid used in various and box model and soil permeability studies carried out by the Geochemical and Geophysical Research group. Tap water supplied to the 222-U Bldg. contains a large amount of dissolved air. Under the reduced pressure encountered during model studies, the air is released from solution and gradually clogs the pores of the sand or other porous m… more
Date: April 20, 1959
Creator: Raymond, J. R.
Item Type: Refine your search to only Report
open access

Backmixing in Pulse Columns II, Experimental Values and Effect of Several Variables

Description: Seven runs were made with the system Penn. Ref. Co. "Supersol" (dispersed) water (continuous) to investigate the effects of pulse frequency, amplitude plate spacing, volume flow ratio, and throughput on backmixing, using the technique of continuous injection of a tracer solution into the packed section. Backmixing was found to be surprisingly insensitive to all the above variables over the range studied with the exception of pulse amplitude and continuous phase flow rate, showing greatest depe… more
Date: August 11, 1953
Creator: Swift, W. H. (Ward Henry), d 1929- & Burger, L. L.
Item Type: Refine your search to only Report
open access

Behavior of S.I.R. Fuels Irradiated in Sodium: Final Report, Production Test 105-180-P (Special Request KAPL-79: The "Beta Experiment")

Description: Report describing the effects of pile irradiation on fuel materials and coil springs for the Submarine Intermediate Reactor. The investigation was called for by Hanford Irradiation Request No. 79. Results of investigation are detailed in the report.
Date: August 12, 1952
Creator: Lambert, J. B., 1929-
Item Type: Refine your search to only Report
open access

Beta In Line Monitor for RCU Stream

Description: Interest has been expressed in continuously monitoring the beta activity of the uranyl nitrate solution pumped to the RCU receiver tank, to facilitate operation at higher flow rates and with younger feeds. A beta scintillation detector has been developed which should make this feasible, and it is proposed that it be tested on stream for this use.
Date: May 1953
Creator: Leboeuf, M. B. & Connally, R. E.
Item Type: Refine your search to only Report
open access

Biology Seminar : methods of assaying for plutonium in biological materials

Description: From introduction: "Since plutonium is manufactured at the Hanford Works, a study of its effect on biological materials is important. To determine the amount of plutonium deposited in a biological sample, it is necessary to have an accurate method for extracting plutonium from these samples. Some of the different methods for plutonium assay are reviewed and given in this paper."
Date: November 1948
Creator: Case, A. C.
Item Type: Refine your search to only Report
open access

The Blast Cleaning Process as an Aid to Visual Weld Inspection

Description: Late in 1958 it became apparent that some fuel elements were failing in the Hanford reactors as a result of water entering through the weld. The mode of entry appeared to be first through a void in the weld, then through a non-wet area or a train of voids in the braze, and finally to the uranium core. Defective closures of a similar nature were also typical of many fuel elements which have failed in the autoclaving operation as shown in Figure 1.
Date: March 9, 1960
Creator: Hanson, G. R.
Item Type: Refine your search to only Report
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