The principal relations for the stress analysis of flat circular plates according to the classical theory are presented in a convenient form. Almost any flat circular plate of uniform thickness, with or without central holes, loaded with any combination of axisymmetrical loads may be analyzed by the procedures. (A.C.)

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This report discusses analytical and experimental heattransfer studies of cyclic temperature oscillations rn a fluid medium and their effect on the temperature of an adjacent solid boundary. These studres are intended to aid in the analysis of thermal stress caused by cyclic temperature fluctuations. The results of experimental measurements of thermal amplitude attenuation for an effectively infinite wall are presented together with heat-transfer analyses for two cases with finite walls. (auth)

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The purpose of these investigations is to determine, grossly and simply, if a shock hazard exists from an explosive failure of the pressurizer vessel within the vapor container. Because of the geographical location of the reactor, an explosive failure which ruptured the vapor container might release radioactive contamination from the reactor to nearby inhabited communities. The study is considered more as a generic problem than of a specific design and is concerned with the shock hydrodynamics of an exploding steam vessel. (auth)

Progress is reported on the following investigations: separation of Nb and Ta by solvent extraction; separation of Ti and Nb with TBP, and of Hf from Zr with methyl ethyl ketone; preparation of HfF/sub 4/, CeF/sub 3/, LaF/sub 3/, ThCl/ sub 4/, and V chlorides; preparation of Ce, La, V, Nb, anf Hf; phase studies of U- -Zr, U--Ag, U--Nb, V--Al, V--Ta, Th--Mg, Zr - Zn, and Ta alloys; corrosion of high-melting metals and alloys by liquid U-Cr and Mg--Th alloys; casting U into U- Zr alloy cans; coating and electroplating of U; reactions of U with Al-Si alloys at high temperatures; corrosion of U - Zr--Nb alloys in water; crystal structure of sodium tungsten bronze; physical properties of Dy; and phase studies of CaO- CaF/sub 2/ systems. (C.W.H.)

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Activities of the National Monitoring System are summarized for the period March 1 to June 15, 1953, during which eleven nuclear devices were fired at the Nevada Proving Grounds during Operation Upshot-Knothole. The program employed a world-wide network of 125 sampling locations. Each station collected samples of atmospheric dusts for radiometric analysis. A comparison is made of air concentrations and fall-out activities. Data are tabulated.

This report summarizes the effect of irradiation on the properties of fissionable and non-fissionable materials. General property changes, irradiation of zirconium, zirconium-tin alloys, the irradiation of aluminium, irradiation of thorium and uranium, are a few of the topics discussed.

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This report is a summary of the physics design work performed on the Engineering Test Reactor. The ETR presents computational difficulties not found in other reactors because of the large number of experimental holes in the core. The physics of the ETR depends strongly upon the contents of the in-core experimental facilities. In order to properly evaluate the reactor' taking into account the experiments in the core, multi-region, two-dimensional calculations are required. These calculations require .the use of a large computer such as the Remington Rand Univac and are complex and expensive enough to warrant a five-stage program: 1. In the early stages of design, only preliminary two-dimensional calculations were performed .in order to obtain a rough idea of the general behavior of the reactor and its critical mass with tentative experiments in place. 2. A large amount of work was carried out in which the reactor was approximated as one with a uniform homogeneous core. With this model, detailed studies were carried out to investigate the feasibility and to obtain general design data on such points as the design and properties of the gray and black �control rods, the design of the beryllium reflector, gamma and neutron heating, the …

This volume continues with discussions of shielding provided for the heat exchanger building, concrete biological shield, top area and bottom area shielding, canal shielding, water shielding requirements during fuel element exchanges, and supplementary shielding requirements.

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This report describes the objective of this production test which is to simulate with a few tubes operation of the old piles with small water annulus at power levels in the range of 800--900 MW.

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The meeting was opened by Leo Brewer, who spoke on a ``Self-Purifying Reactor.`` This is a reactor with theoretically designed-in separations processes, involving calculations to show that it is possible to vaporize many fission products away from fuels. The reactor would be analogous to a graphite rod impregnated with a uranium or thorium compound, vapor-coated with zirconium, and cooled by liquid metal. The fission products will vaporize when the rod gets hot enough, and will be carried out of the pile in a flow of helium. The details of what will happen to the rest of the pile at these temperatures, and of the materials of construction required to handle the situation are yet to be worked out. Remarks were heard from representatives of BMI, GE, Lockland, ANL, ORNL, KAPL, AEC and MCW on properties of uranium oxides and other refractory oxides.

Nickel-plated uranium corrosion samples, 1 inch dia. X 0.180 inch thick, press-clad with 30-mil aluminum at both 10 and 15 thousand psi, show improved corrosion resistance over samples press-clad at 6 thousand psi with the same time-temperature conditions. Design of equipment for the internal cladding of uranium tubes is progressing. The basic tools will be applicable to several variations of the proposed method of {open_quotes}inverse die sinking.{close_quotes} Analyses of double and triple melted Horizons` electrolytic thorium show a significant increase of H{sub 2} and O{sub 2}, upon remelting with a corresponding increase in the hardness of the metal.

The 105-B Pile which was shut down on July 18, 1951 to permit removal of a ruptured uranium slug from tube No. 2169-B. The rupture was detected from effluent water monitor evidence and a survey of rear face pigtails. Removal was accomplished with the pneumatic charging machine using only normal pushing force.