The purpose of the test used to make this report was to determine if anodizing could become a part of the canning operation prior to autoclaving, other factors permitting, or if it must follow autoclaving.

Abstract: "Small amounts of acetic acid, equivalent to 400 ul. of 0.3 to 0.13 g/L. can be titrated coulonatrically in the presence of a 10 to 25-fold excess of HN03 in 70%, isopropanol. An accuracy of +/- 0.1% and a precision of +/- 8.5% (99% limite) are obtained.

Abstract: "A new method of determining 8-hydroxyquinoline by titration with electrolytucally-generated bromine has been developed. Results show good precision in the range 0.4 mg. to 1.6 mg. total 8-hydroxyquinoline, with 99% confidence limits of less than +/- 2%. An electronically-regulated constant current source, required by the method, is described. A new indicator system with high sensitivity to free bromine is discussed."

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

Abstract: "A method has been devised and successfully used for marking a leaking pile process tube prior to its removal from the pile, such that subsequent location of the leak is more easily accomplished. An acetone solution of Testor's Dark Red Airplane Dope is poured into the suspect tube. The solution leaks from the hole and stains the surrounding area a light pink. To date the method has been used on tubes 3573F, 0486F, 0867F, and 3670F."

An analytical method for Cu-64 in reactor effluent has been studied based upon electrodeposition of the active copper with inert copper carrier. A two hour plating time was employed at a current density of 10 ma/sq cm and four volts across the cell. A stainless steel cathode plate was used. Carrier yields of greater than 80% were obtained with a standard deviation of the yield-corrected counting rate as low as 0.24%. Very little, if any contamination by other radioactive elements present was shown by decay curve studies. Self-absorption and self-scatter factors to correct the counting rate were obtained.

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."

R. H. Fillnow and H. Pennington of WAPD visited HAPO on September 14-15, 1955, to discuss HAPO special irradiation facilities and review fuel element problems with HAPO personnel. During their meeting with Metallurgy Research personnel, the progress of the evaluation of UO₂ elements for the PWR and the results of recent HAPO irradiations of oxide type fuel elements were discussed. Although brief, this information exchange was particularly valuable as many of the problems associated with the application of oxide fuel materials was reviewed. A summary of these discussions is outlined below.

A general method is developed to allow calculation of the critical buckling of an assemblage of fissile regions coupled by neutron leakage. Consideration is given both to regions embedded in vacuum and in material media. Several cases of simple geometry are further developed to illustrate the theory.

This report is a survey of methods for determining trace amounts of nitric oxide and nitrogen dioxide in air. The methods are evaluated in relation to their applicability to continuous monitoring procedures for these substances in stack gas and in air for human consumption.

This paper presents the results of a series of buckling measurements involving the use of enriched uranium rods (1.007% by weight U²³⁵) in light water. The effect of replacing a water reflector with one of uranyl nitrate solution of two different concentrations, 536 and 188 grams of U per liter of solution was investigated for the 0.925" rods with the 1.74 H₂O/U-volume ratio in the core. Some information was also obtained on the extrapolation length to be used in unreflected cases. The application of theory to these lattices, and others, is given in an appendix under separate title, "Buckling Calculations for One Per Cent Enriched Uranium-Water Rod Lattices."

Relations governing the measurement of Stainless Steel corrosion rates by activation analysis are derived and discussed. The principal neutron induced radioactivities are calculated and graphed. Shielding requirements are considered and it is concluded that six inches of lead shielding should be sufficient for the proposed experiments if the samples are allowed to cool for one day in the reactor storage basin.

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

A presentation of the values for the Pu²³⁹ fission cross section f factor extended into a higher energy range than previously reported in BNL-250. The values were obtained by integrating the standard expression defining the f factor on the Hanford IBM-CPC equipment. The un-fit experimental data of Leonard, as corrected for resolution and doppler effect, was used above 0.03 ev being attached to an analytic fit applicable below this point. Results are shown on the accompanying graph.

The purpose of the short duration corrosion test was to obtain preliminary data regarding the corrosion resistance of the spring steel wire in Purex process waste solutions and to measure any changes in the tensile properties of the wire resulting from this exposure.

Zircaloy-2 has a strong tendency to absorb oxygen and nitrogen at elevated temperatures. These gas impurities are extremely harmful, causing brittleness and loss of corrosion resistance. The production of ductile corrosion-resistant welds by present methods required shielding of the weld metal by an inert gas atmosphere or by a vacuum. The alternative to an inert gas atmosphere or a vacuum is reduction of the welding time to a few milliseconds of time to prevent gas absorption.

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."

At the request of the Hanford Operations Office of the Atomic Energy Commission, a criticality instrumentation meeting was held at Hanford on August 17 and 18, 1959. The purposes of the meeting were: (a) to review types of criticality control and/or alarm instrumentation at each site, their problems, shortcomings and potential obsolescence; (b) to discuss instrumentation in the area if approaching criticality; and (c) to consider for material balance purposes, the feasibility of devising instruments to detect the buildup of plutonium and enriched uranium bearing residues in process systems.

A method of performing a series of solvent extractions using a minimum of pulse generators is briefly outlined.

This document covers work done in 3- and 4-inch-diameter glass columns directed toward the development of improved cartridges for the Purex Plant final uranium cycle extraction column, the 2D column. A nozzle plate cartridge for the extraction section and a mixed plate cartridge containing both stainless steel and fluorothene sieve plates for the scrub section were developed. In 3- and 4-inch-diameter glass columns these cartridges have a uranium extraction efficiency as good as or better than the present cartridge; and a scrubbing efficiency, based on the transfer of chloride ion, about the same as the present cartridge.

M-388 is an aluminum alloy consisting of 2S aluminum with an addition of 1% nickel. Preliminary corrosion studies which were conducted by Dreley and by Dillon indicated that the material exhibited excellent resistance to intergranular type of corrosion in distilled water at temperatures of up to 350 C. The combination of a low thermal neutron cross-section and good corrosion resistance make M-388 alloy a candidate material for use in reactor process tubes and fuel element cans. The purpose of the study was to determine some of the mechanical properties of M-388 aluminum alloy at room temperature and at elevated temperatures.

This is a report of what may be an invention in a process or processes for preparing roughly spherical uranium metal particles suitable for use in matrix type nuclear reactor fuel elements.

The purpose of this report is to establish a practical control limit for the activity density (concentration) of radioactive material that may be permitted in large-volume waste waters discharged from the Hanford separations plants to open ponds on the surface of the ground nearby, in consideration of the radiological hazards,

The recovery of plutonium and neptunium by anion exchange has been well demonstrated on a laboratory scale. (1, 2,3,4) The specific adsorbed by the resin is the tetravalent hexanitrate complex of either element. With plutonium (IV) and neptunium(V) in IWW, the plutonium is adsorbed but the neptunium is not. If nitrite is used as the reductant in strong (preferably 8 M or over) nitric acid, both plutonium and neptunium are obtained in the tetravalent state, and both are adsorbed on the resin. With stronger reductants, such as semi carbazide or ferrous sulfamate, plutonium (III) and neptunium (IV) are obtained so that only the neptunium is adsorbed. Optimum recovery of either element is obtained with between seven and eight M nitric acid.