The following report examines methods to determine uranium nitrate hexahydrate on pretreated hexone in the range of 0 to 40 g./l. by infrared absorption measurements.

Objective: "The observations summarized in the present report were made to determine the stability of ferrous and sulfamate ions and sulfamic acid in RA Column scrub solution (RAS) and in aqueous solution comparable to the RA Column feed tee composition (RAFS). Knowledge of the stability of the reducing agent (ferrous iron) is necessary to properly plan the method of preparation and introduction of this component into the RA system and to assure dependable and reproducible performance."

From introduction: "In this report an attempt was made to summarize the results of recent research on the effective height of smoke stacks. In this summary attention is paid only to the case in which the density of the stack effluent is the same as that of the surrounding air."

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

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.

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.

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

From summary: "The relative absorptions of X-rays by various substances are listed as a guide to the application of the X-ray photometric method in chemical analysis and to the estimation of interference by extraneous substances."

This report follows an investigation of a cargo truck found contaminated by various radioactive material on a routine trip from Arco, Idaho to the Hanford plant on May 8, 1952. The report analyzes the truck's route in an attempt to find the location of the contaminating region.

Summary: A method was found for determining calcium concentrations in TBP process streams in spite of serious interferences bysodium, ferrous, uranyl, sulfate, phosphate, and sulfamate ions as well as by TBP. The precision attainable varied from sample to sample, depending upon its composition. In general, errors of 20% or greater occurred. The smallest determinable amount of calcium was about 10 mg/1.

This report presents the final results from the investigation of the ratio of Pu-239 fission cross section to U-235 fission cross section. Three sets of plutonium and uranium foils were prepared at KAPL and were investigated to acquire the final results.

Metallographic examination of an irradiated powder metal uranium slug from PT-313-105-4M⁽¹⁾ was undertaken primarily as an evaluation of recently remotized metallographic equipment. It was, also, proposed to compare the grain size with values obtained ultrasonically on the same slug. It was further proposed to make a comparison, so far as limited data permitted, of post-irradiated powder metal uranium grain size with that to be expected from normal uranium similarly irradiated.

Graphite suffers radiation damage when exposed to high energy particles. Many of its physical and chemical properties are changed. One of the effects which is easily measured is an increase in the interlayer or C₀ distance of the crystal lattice. This has been attributed to the displacement of atoms or groups of atoms into interstitial positions of the lattice forcing the planes apart. The C₀ expansion may be annealed out by heating the damaged crystal to high temperatures. This paper deals with the rate of annealing of C₀ damage at several constant temperatures.

Values of copper tubing pressure drops as determined by test for low flow rates of air, helium, carbon dioxide and water are contained herein. The work was performed in order to provide original data, useful for design work at Hanford Atomic Products Operation, and not available in any known handbook or other publication.

Reactivity measurements conducted in the Hanford Test Pile are interpreted to yield resonance integrals for uranium, uranium oxide, thorium and thorium oxide. The experiments were made using cadmium filters and are discussed in terms of the multiplication factor of the Hanford Test Pile.

The object of this study was to determine whether agitation with ultrasonic energy would significantly increase the dissolution rate of nickel in nitric acid.

These initial operating procedures have been prepared for interim use during the first operation of Basins I, II, and III. They will be revised and included in the operating manual for the entire 105-C Metal Examination Facility.

Much attention has been given to the application of zirconium and zirconium alloys to process tubing for reactors. The properties of this material which make it attractive for such use are, as compared to aluminum: lower neutron absorption; higher design strength; and better corrosion resistance in hot water. Installation of process tubes in HAPO reactors requires that gas tight and water tight joints be maintained between the gunbarrel and process tube, and the process tube and nozzle, respectively. With aluminum tubes this is accomplished by forming a Van Stone flange at the ends of the tube and clamping the flanges between the gunbarrel and nozzle with suitable gasketing. No changes would be required in the existing pile components to install zirconium or zirconium alloy tubes if Van Stone flanges could be formed on these tubes. other methods have been tested, however, which eliminate the necessity for a flange. These will be discussed later.

An improved method of water plant control has been developed at Hanford which employs a sensitive turbidiy measuring microphorometer and a model water filtration plant. The microphotometer operates on a light scattering principle and is accurate in the range of 0.0 to 0.1 parts per million turbidity. The model filter plant used is a five gallon per minute plant which can simulate the conditions normally occurring in the large water plants. It is the purpose of this report to describe the model filter plant and to demonstrate the value of the model and microphotometer for effective water plant control and water plant design scoping.

This paper is a preliminary report of experiments being carried out on the compaction of UO₂ powders by swaging within a restraining tube. Various types of UO₂ have been tried with resulting apparent densities as great as 9.89 grams per cubic centimeter.

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 material. This, of course. leads to anomalous results and cannot be tolerated in precious studies. A system was required to effectively remove the air and make available a continuous supply of desired water for the model studies.

The build up of contaminated film on the internal surfaces of high temperature in-reactor recirculating water loops has created serious radiation exposure problems to operational and maintenance personnel. A considerable amount of work has been applied to develop an effective decontamination process for the decontamination of these loops and their components.

The Atomic Energy Commission has recently developed an enlarged program for the study of graphite moderated, gas cooled power reactor systems. It has been recognized, however, that understanding of radiation damage and radiation induced chemical reactions of graphite at the proposed high moderator temperatures is inadequate and that improved understanding is essential if the design of such reactors is to be optimized. Accordingly, the Atomic Energy Commission requested Hanford to organize a modest research and development program directed toward the study of these graphite problems.