Abstract: "A method is described for the identification and quantitative determination of trace amounts of rare earths in graphite by measurement of the energies and decays of the activities induced by neutron irradiation. The specific rare earth elements identified are europium and samarium. During the development of this method, the half-lives of Eu-152 and Sm-153 were determined. These are reported as 9.32 +/- 0.04 hours and 46.34 +/- 0.23 respectively."

This report is a document summarizing all information available on life aspects of various measures proposed to reduce or eliminate corrosion of Van Stone flanger.

Summary: "The laboratory data collected during the metallurgical evaluation of these rods indicate that lower rolling temperatures increased the ultimate and yield strength, the amount of cold work, and the degree of preferred orientation existing in these uranium rods."

Abstract: "A batch of slugs is being prepared for which the U-235 content will be 1.75 per cent, and it is of interest to calculate the minimum number of such slugs required for a critical assembly in water. Using Handbook (CL-697) methods, a critical assembly of these slugs arranged in a lattice with a spacing of 5.5 cm."

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.

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."

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.

Fractional absorption of gamma photons from a source by uranium or plutonium in solution is measured to determine concentration of these elements.

The objective of this report is to analyze the basic engineering problems involved in the design of a pressurized demonatration reactor to be moderated and cooled with heavy water. Two fundamental concepts of this reactor, here referred to as the HWER, are as follows: (1) a tank-type reactor, in which the moderator pressure is maintained at or near atmospheric conditions, and (2) a pressurized vessel-type reactor in which the moderator pressure is maintained at 1000 to 1300 psi. The fuel and primary coolant channels in either case will be designed for an internal pressure pressure of 1000 to 13000 psi.

A exploratory study was made of a polarographic technique in which an alternating sine or square-wave potential is superimposed upon the applied d.c. potential of the polarographic scan. Recording of the a.c. component of the polarographic current results in derivative-type waves. It was shown that the technique yields greater sensitivity and greater selectivity than normal polarographic technique.

A series of diffusion length measurements were carried out on graphite stacks of various constructions in an attempt to resolve the discrepancies between the graphite diffusion lengths measured in the Hanford reactors and that value measured in the Hanford Standard Pile. It was found that the diffusion length of the graphite in the Hanford reactors is in good agreement with the value for the Hanford Standard Pile when corrections are made for the absorption and scattering of neutrons by the aluminum process tubes, and for neutrons streaming in the channels of the reactors.

The creep problems associated with zircaloy-2 process tubes and the factors affecting the creep of these tubes were discussed in detail. Emphasis was placed on the determination of the tube wall thickness for an SPR tube, whose minimum thickness is limited by creep considerations. It was concluded that, at the present time, there is not enough information available to design zircaloy-2 process tubes on a realistic basis. Various experiments were suggested to supplement the creep rate testing program being pursued by Battelle Memorial Institute.

A method is described whereby many types of flaws lying close to the surface of a metal can be ultrasonically detected, regardless of the time duration of the interrogating pulses. Lamb waves are established in the metal between a flaw and the surface by an ultrasonic beam which impinges at the proper angle of incidence. A suitably positioned receiver transducer picks up the waves to reveal the flaw. In this method the usually troublesome surface echo is eliminated from the receiver by an acoustic barrier, making it well suited for routine and automatic testing. Results of applying the technique to several testing problems are discussed.

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.

A flexible foil data processing program is described. Raw data on foil radioactivity are the basic input information required. Output may consists of relative activities, saturated activities, and/or cadmium ratio and flux spectrum data. A statistical analysis of the data is executed with the direct calculation, and errors estimated for the output data.

The purpose of this program is to determine the effects of neutron radiation and reactor gaseous atmospheres on the structural integrity of candidate materials for the PRTR gas-cooled loop. An exploratory investigation is being conducted to select a high temperature resistant alloy for the fabrication of tubes and supporting appliances for the PRTR gas-cooled loop. In addition to a low neutron cross section, the material must be able to withstand the operating conditions outlined in Table 1.

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.

Early in the U.S. gas-cooled reactor program, it was recognized that a considerable research and development effort would be needed to utilize the full potential of gas cooling. Hanford Laboratories contribution to this program began in August, 1958 when a graphite studies program was initiated. The primary objectives of the Hanford program are: (1) to secure improved knowledge of the reaction of gas coolants with protected and unprotected graphites over a range of conditions of practical interest for gas cooled power reactors with tolerable damage to the graphite moderator.

Soil chemistry studies have been carried on at Hanford for a number of years in support of the disposal of low and intermediate level liquid wastes to the ground. Equilibrium type experiments were carried out to investigate the mechanisms of the reactions of Sr, Cs, and rare earth ions with soils (1, 3, 4, 5). Experiments were also conducted with simulated and actual wastes in soil columns and an empirical method was developed for prediction of radionuclide breakthrough from ground disposal facilities into ground water on the basis of short, laboratory soil columns and equilibrium experiments (6,7). In this method it is assumed that the shape and position of the breakthrough curve is the same under laboratory conditions as in the larger scale field case. It is also assumed that the "column volume" or amount of soil effectively used for fission product sorption is that directly under a disposal facility without considering any spreading of waste solutions. These assumptions are known to be on the conservative side, but the degree of conservativeness is not known.

periodically the Industrial Hygiene Unit has the occasion to perform efficiency tests on respiratory protective devices and on filter cartridges used with these units. A study of the relative merits of the flame photometer and conductivity meter was made to determine which is more applicable for the determination of NaCl in filter samples.

Extremely radioactive particles result from the abrasive wheel cutting of irradiated fuel elements in the cut-off cell located in the 327 Building. Due to the use of water during the cutting operation these particles are in suspension and must be removed before the liquid can be discharged to the liquid waste tanks in the 340 building. The filters presently employed in the cell total activity discharged to the 340 Building tanks is attributed to the particles which pass these filters. With the start-up of a new, larger cut-off cell the cutting is expected to increase considerably, thereby increasing the amount of radioactive cuttings requiring disposal. The installation of equipment which would more efficiently remove the suspended particles would (1) reduce the activity level of wastes disposed to ground, (2) reduce the radiation exposure level to drivers who truck the wastes to the 200 Area, and (3) prevent the forming of localized high radiation zones due to the deposition of particles in the waste line in the 327 Building.

Disposal of liquid radioactive wastes to ground requires knowledge of the area ground-water hydrology. Information is desired on direction and velocity of ground-water flow. Direction of flow can be determined from maps showing contours on the water table surface, such contours being derived from well water elevations. Ground-water velocity is more difficult to ascertain.

Through the years, considerable effort has been expended in studies of the explosive reactions sometimes observed in the dissolution of uranium-zirconium alloys in nitric acid. It has been shown (1) that such reactions result from the rapid oxidation of finely dived solids released by the preferential dissolution of the metallic matrix. The explosive portion of such solids has been identifies (1) as an intermetallic compound with the approximate composition UZr2. This compound, referred to as the epsilon phase in previous work, has more recently (2) been termed the delta phase. The latter designation will be employed here.

One of the UO2 fuel element designs proposed for use in the PTRT is the nested tubular concepts. This configuration compromises a central fuel todo surrounded by two concentric tubes of fuel (see sketch, appenx I.) . These UO2 shapes are to be jacketed in the Zircaloy and must be separated from each other and the procuresses tyvm vt annular spaces for the passage of coolant. The annuli are established and and maintained by the longitudinal ribs on the outer surface of all three jacketed fuel elements.