From introduction: The present report describes further refinements of the apparatus and the method to meet a need for a sensitive determination of carbon in plutonium.

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.

The following document analyzes plutonium in urine which uses nuclear track film for evaluation of the quantity of separated plutonium.

From summary: "The methods of calibrating the 305 pile for impurities and density differences in graphite are reviewed and calibration constants are calculated theoretically."

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."

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.

Feasibility of conversion of uranyl nitrate to uranium trioxide by the continuous addition of concentrated uranyl nitrate solution to hot, agitated UO3 powder.

Introduction: "A corrosion test program, to determine the suitability of LaBour B-55 and Worthite for use in the construction of circulating pumps for th UO3 process has been completed and the data are appended."

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."

The following report provides data from corrosion tests meant to evaluate the performance of Type 3098Cb stainless steel in BiP04 process dissolver solution containing mercuric ion.

The following report contains data from all corrosion tests initiated to determine the amount of iron, chromium, and nickel contamination expected in the Metal Recovery Process product.

Introduction: A limited test progress on Alloghany-Ludlum type 347 stainless steel plate which failed the Huey test (ASTN A-262-44T) has been completed.

The preceding report follows an extensive study made at Hanford of methods and equipment to remove effectively the dissolver vent gases.

"The attached report summarizes the work performed in the establishment of an improved spectrographic method for determining iron in plutonium."

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 and twenty-three tables are included. All aquatic invertebrates were found to be concentrating radioactivity from the river water. A maximum activity density of 4.4-10-(-3) μc/g wet weight was found in the larvae of midges (Hydrobaeninae) collected near Hanford during September, 1949. Radioactive wastes were not found to be causing any apparent deleterious effects to the natural invertebrate fauna. Existing population variations are caused by biological and hydrographic conditions."

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.

The following report discusses a method developed by Broida and Moyer, the method describes an emission spectrometer procedure for the determination of the ratio 100 D/(H4D).

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, and counting the ash. A tentative procedure is given and recoveries tabulated."

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.

Purpose: "This test was conducted to gain information and experience in the handling of heavy aggregate concrete. The results from this test were to establish procedures for a subsequent program -- "Construction Test of High Density Concrete Shielding.""

From introduction: "Five appendices, each of which pertains to a separate phase of the Filtration of Radioactive Aerosols by Glass Fibers program."

The following report records a total of forty-nine graphite core samples that have been bored from process tube blocks in the Hanford piles with the intention to provide results to indicate that core boring is an entirely practical operation over bore scraping in obtaining powder samples.

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."

This report follows an investigation on how hydrolysis products of tributyl phosphate (such as dibutyl and monobutyl phosphoric acids, orthophosphoric acid and butanol) effect the tributyl phosphate process for uranium recovery.