Static overpressure and dynamic pressure versus time over surfaces processing different physical properties were measured on two tower shots, 6 and 12. On Shot 12, three surfaces were provided: the natural desert, a water surface consisting of a flooded area, and an asphalt surface. On Shot 6, desert and asphalt areas only were available. There were 123 channels of instrumentation installed for Shot 12, and 24 for Shot 6. From the data, a system of wave-form classification was devised for overpressure and dynamic-pressure- versus-time measurements. Incorporation of this system into data analysios indicates that it is possible for an ideal peak pressure to be identified with a nonideal wave form. Introducing both variables, wave form and peak pressure, into analyses reduces ambiguioties associoated with comparing results of different nuclear tests. The data show the effect of the nature of the surface upon airblast phenomena from a nuclear explosion. The effects of surface conditions upon shock phenomena are made more understandable by a review of temperature computatioons, using shock wave parameters in addition to an analysis based upon the arrioval time of the thermal pulse. A phenomenological discussion of precursor formation is presented, and comparisons are made using data from all …

Three new americium activities (Am{sup 238}?, Am{sup 243}, and Am{sup 244?}, the latter two formed by n,{gamma} reactions) are described and some additional information is given on previously reported americium isotopes.

Abstract: "Creep and creep-rupture tests were made on 25-O aluminum sheet at temperatures of 500 and 550 C. The estimated stresses that will produce 0.5 per cent deformation and rupture in 10,000 hours at 400, 450, 500, and 550 C (data at 400 and 450 C are from BMI-T-29, dated June 9, 1950) are presented."

From abstract: "A method for fabricating 30-in.-long stainless steel - uranium dioxide sheet was developed and the properties of the fabricated sheet were investigated."

Quarterly progress report describing work related to a study of radiation physics problems involved in the design of high-level cesium-137 gamma sources. It outlines work completed and ongoing goals for the project.

The following report focuses on an investigation made to determine if vacuum melting was an absolutely necessary step in the metallurgical process of melting and casting uranium.

Report discussing performance estimates for several airplanes using General Electric AC-210 ramjet nuclear-powered engines. Assumptions used for designing the engines, radiation shield, and airframe are described. Potential tradeoffs in regards to power and weight reduction are also discussed.

Report on the principle of measuring the time-of-flight of neutrons, magnetic-core storage of detector pulses, how pulses are stored, current generator, storage cycle generator, and cathode ray oscillograph.

"This symposium is concerned with the basic aspects of radiation effects. When we turn to the genetic effects of radiation in mammals, there are so few aspects on which there is any information that the problem of sorting out the fundamental findings has hardly arisen. In this paper it will, therefore, be possible to survey most of what is known and pass on to a consideration of what is needed next. Since one of the purposes of this symposium is an interchange of views between investigators in different fields, an attempt will be made to avoid technical details. Among the practical needs in mammalian radiation genetics is a pressing one for more data on which to base estimates of the genetic hazards of radiation in man. The present paper will be concerned largely with this problem. Our own work is directed primarily in this direction, our objective being to uncover some of the basic facts in at least one mammal-the mouse. Before discussing the experimental work, however, it seems desirable to consider some of the general features of the genetic hazard of radiation."

From abstract: "A full-scale, always-safe, metal dissolver for Experimental Breeder Reactor fuel was designed, built, and installed for test operation. It was found that the dissolver operated satisfactorily, and feasible operating procedures were established for the dissolution of bare, or jacketed, EBR slugs. Minor modifications of the dissolver design have been required to accomodate [sic] a modified EBR slug, but it is believed that this will not significantly affect its operating characteristics."

Neutron density at the end of the slug is increased appreciably and therefore the heat production in the end of the slug is also increased. The end result is increased heat flow into the cap with correspondingly higher temperatures. The combined results and conclusions of documents CP-1580, CP-1989, and CP-2871 afford a means of calculating the aluminum end cap temperatures with consideration being give to the above mentioned {open_quotes}Wilkins effect,{close_quotes} i.e., that the heat production near the end of a slug with an aluminum end cap is greater than the heat production at the middle (axially) of a slug. The maximum temperature in the aluminum end cap is calculated to be about 278{degrees}F. for the {open_quotes}G{close_quotes} Pile. This temperature occurs at the center of the maximum performance process tube.

Pile temperature control is normally maintained by using four horizontal rods, two ``long`` rods extending to the far side of the pile and two ``short`` rods whose tips are on the near side. (1) This procedure prevents cycling of ``hot spots`` about the pile, but does not achieve symmetrical horizontal temperature distribution. Prior to pile operation the cadmium-containing cans were removed from the near ends of the two ``long`` control rods, numbers 5 and 11, at C pile, so that when these rods were in the ``full in`` position their poisoning effect outside the flattened region at the near side of the pile would be small. By using these ``half rods`` in conjunction with ``short`` rods it was expected that a nearly symmetrical horizontal temperature distribution could be maintained. A comparison of near-to- far temperature distribution at C-pile with other piles indicates that gains in production of 4% during early operation of a pile and 3% during later equilibrium operation can be realized by using the half-rods. On the basis of these observations ``half-rods`` are to be incorporated in the K-piles currently under construction. It is recommended that the ``long`` control rods in existing piles be replaced by rods altered …

The new KW reactor was placed in operation on January 4, 1955, and had been running at relatively low power levels for only 17 hours when it was shut down because of a process tube water leak which appeared to be associated with a slug rupture. After several days of unrewarding effort to remove the slugs and tube by customary methods, it developed that considerable melting of the tube and slugs had taken place. It was then evident that removal of the stuck mass and repairs to the damaged tube channel would require unusual measures that were certain to extend the reactor outage for several weeks. This report documents the work and findings of the Committee which investigated the KW reactor incident. Its content represents unanimous agreement among the three Committee members.

Abstract: "The elastic double scattering of deuterons by complex nuclei has been investigated experimentally. Measurements were made on carbon, aluminum, and copper at around 157 Mev; on lithium, beryllium, and carbon at around 125 Mev; and on carbon and aluminum at 94 Mev. The expected tensor components of the deuteron polarization have not been observed. Measurements have been made of the differential cross section and vector-type polarization as a function of angle for the scattering of deuterons from the above elements, at the above energies. The observed polarizations were larger than would be expected on the basis of the individual nucleon-nucleus interactions. In a second experiment we measured the 169-Mev proton-proton polarization at 10, 15, 22.5, 30, and 35 in the laboratory system. The results indicate that partial waves up to and including L = 3 are important at this energy."

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 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.

This report describes a completed counter experiment to measure the attenuation of K+ mesons in various materials.

This report presents the best estimate possible on the basis of the available information as to how high an energy would be necessary in order that the gas pressure which could be tolerated would be attainable with present techniques (say 10-(-7) mm Hg.)

Abstract: "Measurements have been made on pseudo-cylindrical graphite-enriched uranium unreflected systems. These measurements include both critical mass determinations and time dependent measurements using a pulsed neutron source to drive the assemblies."

Report discussing a plasma containment configuration which appears to have no escape cone. From abstract: "Arguments are given to show how the containment process works, including experimental evidence deduced from published reports on "electromagnetic levitation."

Abstract: "The cross section for the reaction Al²⁷(p,3pn)Na²⁴ has been measured for proton energies between 30 and 350 Mev relative to the cross section for the reaction C12(p,3pn)C11, and the absolute magnitude determined by matching with data measured with a Faraday cup at 350 Mev and at 31.5 Mev."

Studies in the 321 Building dissolver during December 1953 and January 1954, were successful in developing a laboratory-proved mercury-catalyzed dissolving flowsheet into a suitable plant procedure. However, this flowsheet was not adapted for Redox plant operation because of uncertainty about the possible presence of hydrogen above the lower explosive limit in the off-gases. Subsequent laboratory work has resulted in a better understanding of the hydrogen evolution, and has resulted in developing low hydrogen evolution flowsheets. When one of these flowsheets is selected for further work, it will be tested in the 321 Building dissolver with non-irradiated slugs to provide information for scaling-up the single-slug laboratory data to a plant-scale operation. It is the purpose of this memorandum to outline the factors considered to be pertinent to the 321 Building investigation, to be used as a guide in making preparations for the runs to be performed.

An enriched I & E fuel element failed during irradiation under Production Test IP-109-AC in December, 1957. Radiometallurgical examination of this slug was requested by the IPD Process Analysis Operation. This report presents the results of the examination work.