The following report provides information conducted with the purpose of ascertaining the effect of oxygen on activated charcoal at approximately one atmosphere by measuring the amount of CO2 formed over a known length of time.

From introduction: The present report is a summary of the experimental work on a laboratory scale to date involving the ammonia reduction and the one step TF4 processes.

"These notes are intended to serve as a summary of the current knowledge of properties of materials. In the future some need may exist for related information of methods of testing, design and fabrication. This issue presents information on low tin-zirconium alloys with subdivision..."

Abstract: "Variations in receiver slot design produce changes in quantity and quality of product and recycle, not only instantaneously, but also as a function of time in approaching equilibrium. The case of fixed feed concentration and fixed inventory of Uranium is described here for standard and Dip-Lip wider R slot receivers. The effects of the two types of receivers on recycle and product X and W concentrations, X production rate, plant X utilization efficiency, integrated X production and effective mass output are shown graphically."

Either system appears to be fairly satisfactory from a containment standpoint. Current results indicate probable over-all rates of about 0.2mils/mo for titanium vs. 1.5-3.0 mils/mo for Ni-o-nel. Tests are not 100% comparable due to changes made in flowsheet conditions, but have been of sufficient variation and length as to allow good predictions to be made. Both metals show some tendency toward local attack in Thorex solutions. These tendencies are increased by poor welding techniques.

Equilibrium loading of uranium on Dowex 21K has been studied in a sulfate system for uranium concentrations from 0.0005 M to 0.0005 M, total sulfate concentrations of 0.45 M to 0.6M, and sulfuric acid concentration of 0.020 M. Loading data have been fitted to Langmuir adsorption isotherms and Langmuir constants have been evaluated. Resin was equilibrated with uranium feed solutions by flowing the feed through a shallow fixed bed of resin.

The Atomic Energy Commission has assigned the Hanford Atomic Products Operation the responsibility of providing the technology and facilities for the interim reprocessing of slightly enriched uranium fuels discharged from power and propulsion reactors. The fuel from the various reactors vary greatly in physical dimensions and in the composition of the core and cladding. For the purposes of chemical reprocessing, the fuels may be divided into the three main categories of aluminum, Zircaloy or stainless steel clad elements. The fuels may be sub-divided by the nature of the core material; e.g. metallic uranium, uranium dioxide, uranium-molybdenum alloys uranium-aluminum alloys, etc.

For purposes of an earlier consideration of the effects of in-reactor test loops on PRTR operation and program, the design of the high pressure, H20 cooled fuel test loop was assumed to be similar to that for the high pressure, gas cooled loop. Detailed design criteria for the H20 loop have recently been completed so that this assumption is no longer necessary. Therefore, to insure that the effects of all proposed in-reactor loops are fully evaluated with respect to Plutonium Recycle Program objectives, the present study has been carried out. Much of the qualitive discussion in the original analysis is still considered valid. Thus, rather than repeating the entire analysis as it pertains to the H20 loop, only those departures resulting from differences between the assumed design and the scope design are presented.

The following quarterly report covers the period between April, May and June of 1954. The reports presented in this document discusses subjects of medical health and physics such as: biological studies of radiation effects, the metabolic properties of various tracer materials, radiation chemistry, health chemistry, and health physics.

Tests on twenty identically prepared 26 gauge Chromel-Alumel thermocouples have been completed. It appears that wires of this material without protection are unsatisfactory mechanically and thermoelectrically for service in atmospheres of CO₂ at 1000°C.

Technical report. Quite pure anhydrous ThCl4 in small quantity (8-10 g charge) has been prepared by the action of a mixture of Cl2 and CCl4 vapor on ThO2 at 675 degrees to 725 degrees C.

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.

This technical report analyzes an experiment designed to test the theory of seismic decoupling of underground explosives proposed by Latter, LeLevier, Martinelli, and McMillan [1959]. The theory calculated the amplitude of a 1.7-kiloton nuclear explosive in a hole in salt and compares it to the measured value of the 1.7-kt Rainier shot in tuff at the same distance. A decoupling factor of about 300 resulted. The experiment, called Cowboy, was designed to test the decoupling principle by carrying out a series of eight high-explosive shots in two spheres made in a salt dome and nine tamped shots for comparison purposes. The seismic data reported here was obtained primarily at 14,000 and 22,000 feet from the shot at frequencies of 10 to 30 cps. A salt-to-salt decoupling factor of 100 was obtained which is consistent wit the predicted 300 tuff-to-salt factor. When the sphere was over-driven so that the walls did not move elastically (a condition which violates the theory), decoupling factors of 10 and 30 were measured. The report interprets the seismic data to give the dependence of decoupling on the various parameters of the experiment. The decoupling deduced from measurements made 80 feet from the shot points is found …

In another paper there was reported an attempt to observe the charge-exchange process in a counter-triggered multiplate cloud chamber at the Bevatron but the interpretation was ambiguous. Shortly after the close of that experiment the 30-in. propane bubble chamber at the Lawrence Radiation Laboratory was completed and able to be used for a combined engineering test and experiment. The existence of Reaction (1) has been confirmed in this experiment, and an approximate cross-section value for carbon is calculated.

An experiment was designed utilizing a charge-exchange reaction to study the decay and interactions of the neutral K mesons produced. The experiment produced no events that could be interpreted as either the decay or interaction of neutral K mesons. The nature of the experiment and the possible explanations of this unexpected result are presented in this paper.

The purpose of this work was to produce a reliable, inexpensive instrument for the detection of hard beta contamination on the clothing of personnel. Also, the monitoring was required to be accomplished without interrupting the normal activities of the employees.

This report was written from the notes used by Dr. York in delivering his three lectures on considerations pertinent to the problem of utilizing controlled thermonuclear reactions for the production of power. The first lecture discussed fundamental properties of the DD and DT reactions and the reacting substances. The second lecture described the stellarator, a proposed machine for the controlled production of power from the above reactions. The third lecture described the pinch effect and considered its possible application to the thermonuclear power problem.

Introduction. As stated in Report KAPL 116, one of the objectives of the KAPL reactor is "to provide a prototype demonstration of the practical general of electrical power from Nuclear energy using molten sodium as the primary coolant. The reactor will generate steam at a temperature of 550 degrees F and 465 psia, including 90 degree superheat potentially capable of an efficiency of twenty-eight per cent in electrical output." The work reported here is intended to increase the scope and supply an independent check on the heat transfer system analysis that has previously been done. The purpose of these analyses is to investigate the effects on load rating and top reactor temperature.

This bibliography contains 37 references on self-shielding cross sections. The bibliography is limited to the period from 1951 through November 1959 with the references arranged alphabetically by title. The sources used in compiling this bibliography were: Abstracts of Classified Reports Nuclear Science Abstracts

To determine whether or not the (n,2n) reaction in Be would produce a net increase in fission neutrons in a power plant, the distribution of In resonance neutrons slowed down from fission energies in a graphite block was measured with and without a 2" of Be in front of a U3O8 slab undergoing fission. The thermal neutrons producing the fissions were obtained by slowing down neutrons from a cyclotron source. The observed distribution without Be was well represented by a Gaussian source range 36 cm. (corresponding to an initial fission energy of 3 MeV) and a similar sink of range 7.8 cm. The total In resonance intensity with Be was 5% less than without Be. On the assumption that the effect of the Be is entirely due to its different mean free path and moderating power, the In distribution with Be was calculated. Since the m.f.p. as a function of energy is not known for Be, two separate calculations were made using the highest (2.9 cm.) and the lowest (1.80 cm.) possible values for the effective Be m.f.p. Both calculated curves were found to be higher than the observed Be distribution, indicating that at least 10% of the fission neutrons …

Attached hereto are copies 1 through 4 of a classified secret report titled "Purex - A Hanford Separations Plant." We are also sending under separate cover a classified confidential report No. HW-36496 titled "Photographs of Purex - A Hanford Separations Plant," which is a counterpart of the above report. These documents are submitted for publication and should be incorporated as a single article.

An inconel loop circulating fluoride fuel (62 1/2 make [unintelligible] NaF, 12 1/2 make [unintelligible] ZrF4, 25 make [unintelligible] UF4, 92 [unintelligible] enriched) was operated at 1485°F with a temperature difference of about 35°F in the Low Intensity Test Reactor for 645 hr. For 475 hr of this time the reactor was at full power, and fission power generation in the loop was 2.7 kw, with a max length power density of 0.4 kw/cc. The total volume of fuel was 1290 cc (5.o kg [unintelligible] and the the flow through the irradiated section was 8.6 fps (Reynolds number 5500). The loop has been disassembled and has been examined by chemical and metallographic analyses. Ne acceleration of corrosion of decomposition of fuel by irradiation was noted, although deposition of fission-product ruthenium was absorbed. Ne mass transfer of Inconel was formed, and the corrosive [unintelligible] was general and relatively light. The average corrosive generation, in the usual form of subsurface yields, was 0.5 [unintelligible], the maximum penetration was 2 to 3 miles.

This report describes the results of evaluation tests made on several glass-coated bayonet heaters supplied to Separations Equipment Development by the Pfaudler Company. The glass-coated heaters were found to be resistant to thermal shock, mild mechanical shock, and chemical attack by boiling 60% nitric acid.

Thus we see that the derivation of elementary age theory is based on replacing the probability of collision governed by the Milne kernel by a Gaussian probability having the same zeroth and second moments. It is apparent that the age theory distribution will fail close to the source and at many free paths from the source.