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."

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

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.

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.

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.

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).

From introduction: "The prime motive behind the experiments described in this report and in those preceding it in this series is the desire to reduce the number of Redox cycles necessary for decontamination from fission products of the plutonium and uranium streams sufficient to allow final disposition of these two products...This report deals with the mechanics of manganese dioxide handing, laboratory development of manganese dioxide scavenging, and a series of experiments at multicurie level combining ruthenium volatilization and manganese dioxide scavenging in stainless steel equipment."

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.

The following report describes a countercurrent extraction column, which employs timed solenoid valves and pressurized feeds to provide a pulsing action to disperse the phases. This report further describes the 4-stage cycle of the column operation.

This report follows work that is meant to determine the settling rate and viscosity of Hanford Waste metal slurry as a function of prolonged agitation and shear, and to repeat these determinations on a synthetic incubated material similar to that used in the acidification studies, HW-18367, and to make a direct comparison between the genuine and simulated wastes.

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.

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."

Basis: "It is desired to test the effect of neutron flux on the creep rate of zirconium. These data will greatly add to the metallurgical information needed for design specifications of reactor components utilizing this metal."

Report summarizing data from Purex tests for pulse column specifications. These test results were used to estimate pilot plant specifications.

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

The following report describes work carried out to investigate whether the Hanford IB column as designed in a previous report will decontaminate the uranium adequately from plutonium, particularly if there's any slowness in either the rate of reduction or transfer of the plutonium.

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.

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."

This report describes an improved infrared absorption method to analyze aqueous samples and TBP after extraction. The method described in the following pages is the carbon tetrachloride extraction method.

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 investigates measurements to calculate the thermal neutron flux in the test pile.

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

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.