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.

This bibliography contains 145 references on the technology and apparatus used in the purification of argon, helium and xenon, and on the analysis for water, carbon monoxide, hydrogen, nitrogen, and oxygen, in the purification process. The references are arranged in four classifications: general, argon, helium, and xenon. Within each classification, the references are arranged in chronological order.

Abstract: A summary of thermodynamic calculations for zirconium halides is given. Data indicates that the iodide is the most promising of the halides for arc dissociation and that good recoveries of zirconium should be obtainable provided dissociation is carried out at reduced pressure.

The following document analyzes the Automatic Isotope Mass Spectrometer that consists of a Laboratory Isotope Mass Spectrometer, covered by Union Carbide Nuclear Company Job Specification "JS-747", which has been modified to meet Union Carbide Nuclear Company Job Specification "JS-741", as well as the instrument's samples collected and analyzed.

"The experience at Oak Ridge National Laboratory in decontamination equipment and working areas from radioactivity has been summarized." The methods and reagents that were used for decontamination are discussed.

The indicated methods for determining the following constituents of Diban, which is an aqueous solution of dibasic aluminum nitrate, Al(OH)2NO3, were evaluated statistically: 1aluminum by gravimetric, volumetric, and spectrophotometric procedures, 2. basicity (hydroxyl value) by formation of an aluminum complex and titration of the free acid with standard alkali solution, 3. total nitrogen by the Kjeldahl method, 4. ammonia by the Kjeldahl method, and 5. nitrates by means of a cation-exchange resin and titration of the liberated acid with standard alkali solution. Recommendations are made regarding the preferred methods of determining the constituents in dibasic aluminum nitrate and regarding means of minimizing errors in these analyses.

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.

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.

Summary: The High Power Density Project includes a comprehensive fuel development program which has the objective of developing and demonstrating the performance of a nuclear reactor core having a high power density, long fuel life, and low fabrication cost. The fuel program is made up of two principal tasks. Task 1A consists of irradiation tests in the VBWR of Type 304 stainless steel clad, UO2 pellet type fuel rods fabricated by current commercial processes. Task 1B consists of the investigation of lower cost fabrication processes and the irradiation testing of fuel elements fabricated by these processes. Both tasks include the investigation of the feasibility and use of thin-wall stainless steel cladding as a means of improving the neutron economy and fuel cycle costs of stainless steel clad fuel. Irradiation of the Task 1A fuel assemblies in the VBWR was initiated in September, 1960. Subsequently, Task 1B fuel assemblies were inserted in the VBWR as various fabrication processes and design concepts were investigated. Fuel cladding failures have occurred in fuel rods in both Task 1A and 1B. As of this date, cladding failures have occurred in twenty-two rods of approximately 700 fuel rods which have been irradiated. Twenty of the failures …

Physics Division quarterly report - general physics research projects and accelerator operation and development.

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.

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.