The following documents are progress reports that follow chemical research studies in subjects such as ruthenium tetroxile distillations, extraction-scrub studies of zirconium and niobium, and oxidation of plutonium and stabilization of plutonium(VI) during extraction of IAF solutions.

Abstract: "Diameter measurements of 25 slugs taken before and after a prolonged heat treatment showed no evidence of differences that would indicate blistering. The average effects of the treatment was different for the various slugs. Large differences in diameter measurements between slugs. Large differences in diameter between slugs and significant differences between indices and positions were found."

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

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

Judging scratch depth or surface roughness by unaided visual inspection under controlled conditions, while rapid and popular, is not quantitative. Comparison methods improve reproducibility but are generally not applicable to evaluation of depths of single widely spaced scratches. Stylus-type contour recorders yield valuable scratch contour data but may themselves plow through soft materials and fine details. Depth measuring microscopes are particularly applicable to measurement of pinhole depth but do not graphically reveal profiles and provide only a small field of view. The comparatively large field of view and graphic display of contour provided by profile microscopes make them particularly suitable for evaluation scratch depth as well as surface roughness. A HAPO-constructed instrument has demonstrated an accuracy of +/- 50 micro inches in the range of 50 to 15,000 micro-inches scratch depth. It is a pocket-sized, portable, and can be used on horizontal and vertical surfaces by untrained persons with only brief instruction.

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.

In solvent extraction purification processes such as are used at Hanford, the fuel elements or "slugs" from the reactor containing uranium, plutonium, and fission products are dissolved in nitric acid, adjusted to the required feed composition, and pumped to the solvent extraction columns. Figure 1 in a schematic diagram of such a solvent extraction process. In the A column, the uranium and the plutonium are extracted into an organic phase while the bulk of the fission products remain in the aqueous phase and leave as waste with the column raffinate.

Abstract: "The valve-actuated pulse column is employed to give phase separation on each half cycle in the countercurrent flow cycle and provides independent control over each step in the cycle. The dependence on temperature of operation, on pulse frequency and amplitude, and on plate design and spacing has been studied for extraction and stripping of uranium with tributyl phosphate in a hydrocarbon diluent. It is found that the efficiency increases quite significantly as the temperature is raised regardless of the direction of transfer and this increased efficiency is accompanied by greater operational freedom. A decrease in hole size, decrease in plate separation and increase in frequency all lead to higher efficiency in agreement with the concept that small drops continually formed coalesced and reformed, lead to maximum interphase transfer. The high extraction efficiency of the column is probably aided further by the relatively sharp pulse produced."

Introduction: "The adoption of aluminum nitrate as salting agent in the Redox process made it imperative that a method be available for determining plutonium in the presence of aluminum. However, large amounts of aluminum have been found to interfere with the determination of plutonium by the lanthanum fluoride procedure. Previous attempts to increase the accuracy of the lanthanum fluoride method, by precipitating LaF3 from 4 M HF (rather than 2 M), have been successful only when the initial plutonium level was high."

Abstract: "Following nitrate removal by means of a three-stage hydrochloric acid digestion, uranium was reduced with chromous sulfate reagent. In an inert atmosphere, the quadrivalent uranium was titrated at 80-95[degrees] with standard ferric sulfate solution. The end point was obtained with a potentiometric cell including a platinum in-titrant reference electrode and a platinum indicator electrode. Application was made to various low leverl uranium solutions. For samples containing 1 - 12 milligrams or uranium, less than one percent error may be expected. Iron and chromium do not interfere."

Thermal oxidation of graphite in flowing CO2 is being studied at 650 to 850 C, in a single-pass gas system at atmospheric pressure, by observing weight loss rates. The method is used to provide comparative data for candidate reactor graphites. The effects on oxidation rates of graphite purity, structure, coke type, graphitization temperatures and other manufacturing variables are determined. In addition, the effects of gas flow rates and graphite surface to volume ratios are observed.

Whenever fissile materials are handled in significant quantities such as in fuel element fabrication, separation processes, or in exponential and/or critical experiments a potential criticality hazard exists. The usual procedure which is followed by those persons conducting critical mass experiments is to either place the potential reactor in a heavily shielded cell or to conduct the experiments remotely in which case distance provides a measure of safety in the event of an unscheduled radiation outburst. In considering potential critically incidents, especially for the personnel not specifically engaged in critical mass studies, it is very likely that at the time of the incident neither the conditions of shielding nor distance will prevail for the personnel involved.

With the development of the zircaloy-2 clad uranium fuel element, it was necessary to develop a method of closing the end of the element after the extruded tubes were cut to the desired length. Regardless of the ultimate design of the closure, a satisfactory zircaloy-2 fusion welding technique had to be worked out. The first fully successful welding was performed with electron beam welding in a vacuum chamber. To make satisfactory welds, the electron beam welding involved time and equipment, plus undue maintenance on the equipment.

The purpose of this procedure is to present a detailed, chronological presentation of the preliminary decontamination and post decontamination steps necessary to fulfill the requirements of the Production Test Authorization IP-239-N. The procedure attempts to present the required operation in sufficient detail to successfully accomplish the intent of the test. Certain procedures involve operations of a standard nature and have not been elaborated upon to any great extent, as it is expected that the reactor operations and radiation monitoring personnel will implement these instructions according to standard operating procedures.

This document reports the circumstances surrounding the failure of sheathed thermocouples during a test being conducted in the KAPL-120 Loop. The report is prepared to provide a record of these events and to acquaint those who use these thermocouples for testing of other applications with the difficulties that are sometimes encountered.

Theoretically aqueous hydrazine will react with dissolved oxygen for form only nitrogen and water. Most of the experimental evidence, however, indicates that the reaction proceeds rather slowly in low-temperature systems. Tests are currently being conducted to determine whether or not it is feasible to use activated carbon to catalyze the reaction in filtered water. A system of this type would be useful in high temperature reactors when it becomes necessary to convert to single-pass operation.

The following report analyzes random walks and whether or not they can be used to shed any light on problems of neutron diffusion.

Purpose: "The Hanford Works Analytical Manual for Process Water is designed to specify the analytical methods to be applied for control purposes in the Reactor Section, Process Sub-Section laboratories. The procedures are in general form and serve as references rather than outlined laboratory instructions. The manual us designed to replace the "Hanford Works Manual," HW-12862."

The decontamination of the present Hanford reactors involves a once-through cleaning operation. Considerable interest has been shown in determining the feasibility of this once-through technique for cleanup of certain portions of the NPR system. This is the second interim report of a series that covers tests performed in the 242-B Single Pass Flow Facility. The first was distributed in January, 1960.

Summary: "The low carbon 18-8 stainless steels containing approximately 1.7 per cent boron used for vertical safety rods at Hanford were found to be structurally stable in the temperature range 0-450 C. The addition of boron decreases the stability of this metastable austenitic alloy. Sufficient ferrite formation is induced by sub-zero temperature treatments to result in dimensional changes and a magnetic alloy. The difficulties encountered in machining this material are believed to be due primarily to segregation in the castings resulting in small areas of the hard intermetallic compound, FeB."

The fixation of aqueous radioactive wastes in a stable solid media by means of calcination has been the subject of considerable research and development effort. Several methods of doing this on a continuous basis have been devised and a few have been demonstrated to be feasible for the handling of non-radioactive or low activity simulated wastes. Currently an investigation of calcination by means of radiant-heat spray drying is being carried on by the Chemical Research Operation of the Hanford Laboratories Operation. The process consists of atomizing the liquid to be treated into the top of a cylindrical column, the walls of which are maintained at a high temperature. The resultant suspension of droplets in the water vapor formed by evaporation passes through successive zones of drying, calcination, possible chemical reaction or melting, and partial cooling as it proceeds down the tower. Separation of the resultant solids, steams, and uncondensable gas is made by conventional methods.

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.

Nuclear safety in the dissolution of irradiated 0.95 U235 enriched fuel has been investigated. In particular, critical conditions of fuel of this enrichment in a 52-inch diameter dissolver crib were studied. Since a crib this size is not safe by geometry, dissolution procedures as well as maximum safe batch sizes were analyzed. Uranium-water lattices are normally studied in systems in which rods are uniformly dispersed in the moderator. The results of such a study for 1.34-inch diameter solid rods as well as I. and E. fuel having a 1.37-inch O.D. by a 0.48-inch I.D. have already reported.

Operating plant experiences in restoring to useful service failed equipment contaminated through exposures to radioactive processes is of international interest to the nuclear industry. In accordance with a request from the Hanford Operations Office of the United States Atomic Energy Commission this report of the various measures taken in rehabilitating for re-use expensive engineered equipment has been compiled by the General Electric Company. This report is a review and summary of the disposition of contaminated major processing equipment at Hanford Atomic Products Operation during 1958-1959 and a listing of 1) equipment buried, 2) equipment stored, to be buried or decontaminated, and 3) equipment decontaminated and returned to service.