Seven runs were made with the system Penn. Ref. Co. "Supersol" (dispersed) water (continuous) to investigate the effects of pulse frequency, amplitude plate spacing, volume flow ratio, and throughput on backmixing, using the technique of continuous injection of a tracer solution into the packed section. Backmixing was found to be surprisingly insensitive to all the above variables over the range studied with the exception of pulse amplitude and continuous phase flow rate, showing greatest dependence on the later. Backmixing increased with decreasing continuous phase flow rate and increased with pulse amplitude.

A program has been prepared for the 709 computer which will determine extrapolation length from horizontal traverses measurements taken in an exponential pile. The flux across the pile is assured to fit a cosine function of the form y = A cos B (X-C)

Because of the excessive vertical fragility and high replacement costs of mice-window G-M tubes used in vertical and horizontal lead-pig shelf counters, it was requested that a simple system of conversions to reliable scintillation detection be accomplished.

The chromium-nickel-manganese alloys are a group of austenitic stainless steels which were developed during the Korean War to conserve nickel. These alloys are very similar to their corresponding 300 Series grades in mechanical, physical and corrosion properties. A portion of the nickel in the 300 Series grades has been replaced by approximately 2% manganese for each percent of nickel replaced. Two compositions, AISI 201 and AISI 202, are recognized as standard grades. Two other compositions, AISI 204 and AISI 204-L, have been produced in limited quantities to replace AISI 304 and AISI 304-L. Experience with the 200 Series steels indication they are every bit as good as the grades for which they were once alternates. In some shapes, such as rod and sheet, the cost per pound is considerably lower than the corresponding 300 Series grades.

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 components for the present aluminum clad, Al-Si bonded, internally and externally cooled (I & E), uranium fuel elements are composed of impact extruded cans and spire caps as shown in Figure 1. This type of component requires two impact extrusions; however, in December, 1957, J. E. Ruffin proposed another design of component in which there was only one impact extrusion. For this component, Figure 2, the spire was impact extruded as a part of the can.

Comparison of experimentally determined relaxation lengths to the value calculated from the concrete composition.

A pile gas leak detection system consisting of a purchased mass spectrographic type of helium detector, a long sampling line for use in remote or relatively inaccessable locations, a pump to pull a continuous sample of gas from the tip of the probe to the detector, and a rotameter to measure the gas flow rate in the sampling line has been developed, calibrated, operationally tested. The system is practical for use in locating all pile gas leaks larger than about 0.1 cubic foot per hour.

Report describing the Hanford Laboratory controlled potential coulometer. This includes the theory behind the coulometer, details of its circuitry, and performance tests. Appendix begins on page 23.

Over the last decade, several computational methods have been developed and used to examine reactor flow transients caused by pump outage. The variations in system character which have been analyzed are sufficiently diverse that it appears worthwhile to compile them into a single report.

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."

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.

The purpose of this study has been to evaluate the chemical resistance of various bearing materials to solutions of nitric acid and uranyl nitrate hexahydrate with views toward selecting the best material to be used as bearings in Purex submerged rotating equipment.

Report presenting results of a study regarding the critical masses and nuclear properties of plutonium as well as the use and effects of various tampers.

The following report deals with the application of the water boiler neutron source to the exponential experiments in an attempt to speed up lattice testing measurements.

The large scale application of Zircaloy-2 pressure tubes for structural use either in or out of reactor service, is without precedent. For more common materials, there normally are adequate data and long operating histories on which to base design and service limits. In the absence of such information for Zr-2, several investigative programs have been devised to provide much of the information from which design and service limits may be defined for Zr-2 pressure tubes. These investigations encompass in-and-out-of-reactor creep and stress-rupture testing, pre-and-post irradiation testing, and bust strength, as well as the effect of flaws or defects (from both fabrication and service origins) on burst strength and fracture characteristics. Already creep and stress rupture testing of unirradiated Zircaloy-2 is well advanced, and some experimental pre-irradiation burst testing has been carried out and will be extended rapidly as improved equipment becomes available. One irradiated KER tube sample has been burst tested and the requirement for post irradiation burst testing equipment have been defined.