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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
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Bronze Furnace History 313 Building

Description: This study was started in May 1949 to find methods of reducing the number of element failures in the salt bath bronze furnaces. Determining the cause of the failure and methods of eliminating them is followed to completion.
Date: February 6, 1951
Creator: Correy, Thos. B.
Item Type: Refine your search to only Report
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Canning depleted uranium : production test 313-110-M, final report

Description: From summary: "Uranium billets deficient in U235 were subjected to the normal successive steps in the slug fabrication process; viz., rolling, machining, and canning. No unusual behavior was observed at any point in the process, thus indicating that the depleted metal from the standpoint of mechanical properties can be considered equivalent to normal uranium."
Date: March 27, 1951
Creator: Jones, T. S.
Item Type: Refine your search to only Report
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Coating Removal Waste Loss Reduction : Final Report, Production Test 221-B-8

Description: The following report covers a test with the objective to demonstrate that the plutonium and uranium losses associated with the aluminum jacket dissolution could be reduced by substituting a water wash for the 5 per cent nitric acid wash following the coating removal and that this change would not adversely effect the product yield of decontamination in subsequent process steps.
Date: June 25, 1951
Creator: Kirkendall, B. E.
Item Type: Refine your search to only Report
open access

Corrosion Data for Type 347 Stainless Steel Pipe Waste Metal Recovery Process

Description: Introduction: "A limited test progress for the evaluation of type 347 stainless steel pipe which failed the Huey (?) test has been complicated. The tests reported herein were similar in scope to those reported in document number EW-20765, Corrosion Tests on Stainless Steel Plate, Waste Metal Recovery Process. Material tested was obtained on order number EWC-8553, National Tube Company Heat #3X9741. Lots 9789 and 9790."
Date: May 22, 1951
Creator: Sanborn, Kenneth L.
Item Type: Refine your search to only Report
open access

Effect of Hanford Pile Effluent Upon Aquatic Invertebrates in the Columbia River

Description: Abstract: "This is the preliminary report of a radiological-ecological survey of the invertebrate fauna that inhabit the Columbia River within the confines of Hanford Works and downstream to the site of McNary Dam. The survey was carried out during the period of October, 1948 through February, 1950. Materials and methods are discussed and the results of extensive radioassays, qualitative and quantitative biological determinations, and hydrographic studies are given and analyzed. Twelve figures … more
Date: January 19, 1951
Creator: Davis, Jared J. & Cooper, Calvin L.
Item Type: Refine your search to only Report
open access

Effects of Furnance Pressures on Quality of Remelted Uranium : Final Report, Production Test 314-59-M

Description: The following report follows a test for remelting and casting uranium scrap specified that a pressure of 25 microns or less must be attained within the furnace before a charge is melted. The report was made to evaluate the effect of furnace pressures upon the quality if recast uranium metal.
Date: February 15, 1951
Creator: Kattner, W. T.
Item Type: Refine your search to only Report
open access

Estimation of Fission Product Beta Activity in Uranium Containing U-237 and UX

Description: Abstract: "It has been found that a mixture of acetone and ethyl ether containing nitric acid will wash uranium and 98 per cent of its natural daughters from a celluloss pulp column. Eight per cent of a "fission product" spike also comes through in this fraction but may be reduced by suitable modifications. A second development with two molar hydrochloric acid washes out 83 per cent of the original spike activities, and an additional three per cent is obtained by extruding the column, ashing, a… more
Date: 1951
Creator: Meinhard, J. E.
Item Type: Refine your search to only Report
open access

Heating in the Graphite Due to a Cadmium Control Rod

Description: From introduction: "This paper employs a multigroup method similar to that of J. S. Story, AERE-TR-177 to calculate, for cylindrical geometry, that heat energy source density in graphite due to absorption and Compton scattering of those gammas produced by neutron capture in a water filled cadmium control rod."
Date: September 29, 1951
Creator: Newkirk, W. H.
Item Type: Refine your search to only Report
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