Report discussing the relative thermal conductivities of liquid lithium, sodium, and eutectic NaK, and the specific heat of liquid lithium, as well as the methods and materials used to determine this information.

This report describes the manufacture of 25 Aluminum clad, 10 w/o plutonium-aluminum alloy and 5 w/o plutonium-aluminum alloy cored specimens for Argonne National Laboratory-University of California irradiation tests in the Materials Testing Reactor. The manufacturing method: preparation of cores and cladding material, assembly and welding of compacts, outgassing, roll bonding, shearing, identification marking and final fabrication into napkin "rings" is described in detail. Of ninety-six specimens fabricated, ninety-one were completed as finished specimens. Forty-four of these contained 5 w/o plutonium alloy cores and forty-seven contained 10 w/o plutonium alloy cores. Five specimens ere rejected for bond blistering.

The purpose of this work was (1) to investigate the possibility of producing zirconium-clad zirconium-uranium alloy objects by casting the core alloy directly into zirconium and zirconium-3 w/o tin jackets, producing a diffusion bond at the jacket-core interfaces, and (2) to produce small scale heat thru-put test specimens by this method.

Experiments are described in which the pile-induced changes in electrical resistivity and elastic modulus of graphite were investigated as functions of the sample temperature during bombardment and the amount of bombardment. The data are for relatively low bombardment times (up to ca. 20 L-units) and temperatures (up to 340*C) and are not sufficiently extensive to permit unequivocal conclusions.

Corrosion rates of present reactor grade uranium were measured in boiling distilled water and were found to have higher values almost by a factor of two then previously reported corrosion rates of uranium. Mallinckrodt biscuit metal showed corrosion rates in the same medium somewhat lower than reactor grade uranium, and high purity metal prepared at Argonne National Laboratory corroded considerably less rapidly than the biscuit metal.

This report describes the specifications, materials and the sequence of operations used to found and fabricate the first charge of enriched uranium fuel in the Experimental Breeder Reactor.

Report issued by the Argonne National Laboratory discussing meteorological data collected between 1952 and 1953. Wind, temperature, pressure, and precipitation studies are presented. This report includes tables, illustrations, and a map.

Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.

The gastight steel building (400,000 cu ft) in which all radioactive components are to be housed has been completed by the Graver Tank Company. This structure was tested for strength at 18.75 psig (20% above design pressure) and then tested for leaks. No leaks were found in soap bubble testing of all welded seams. Continuous measurements of temperature and pressure over a ten-day period showed the leakage, if any, to be less than the 500 cu/ ft/day at 15 psig specified. The gastight cylinder was, therefore, accepted. General construction work by the Sumner Sollitt Company on the remainder of the plant has begun.

A preliminary design study, Phase I of the ALPR project, has been made in accordance with the Army Reactors Branch specifications for a nuclear "package" power plant with a 200-260-kw electric and 400 kw heating capacity. The plant is to be installed at the Idaho Reactor Testing Station as a prototype for remote arctic installations. The "conventional" power plant as well as the exterior reactor components are described in the accompanying report and cost estimate by Pioneer Service and Engineering Company, Architect-Engineers for the project."Nuclear" components of the reactor are designed by Argonne National Laboratory as described in the present report.

Physics calculations have been made for various combinations of the four types of fuel assemblies to be used in the EBWR core. Two thicknesses of plates, 0.205 in. and 0.274 in., including the two 0.020-in. cladding layers, are to be made of both natural U and U containing 1.44% U235. A total of 148 assemblies, 74 natural and 74 enriched, are to be fabricated with six identical plates each. Various configurations of these fuel assemblies will be used to (1) change the critical size of the core, (2) change the power distribution in the core, and (3) change the amount of reactivity corresponding to a given stream volume in the core. The physics calculations show that uncertainties in critical mass are adequately covered by the number and variety of fuel assemblies and that the possible changes in core characteristics with the different fuel assemblies should provide valuable information about the factors affecting maximum power density and stability in a boiling water reactor.

Report describing a zero-power reactor facility (ZPR-VII), its systems, and associated hazards.

Report regarding "[t]he Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II), the process equipment, and the operations to be conducted in the facility are described. The Fuel Cycle Facility is a plant for reprocessing, by pyro-metallurgical methods, the core and blanket material discharged from EBR-II. The reactor core alloy is uranium-5 percent fissium and contains about 46 wt.% Uranium-235 . The blanket material consists of uranium in which plutonium is bred. Core and blanket subassemblies contained in transfer coffins are transferred between EBR-II and the Fuel Cycle Facility, which is in an adjacent building." (p. 13)

From Introduction: "The Fast Reactor Test (FARET) program is part of the United States Fast Reactor Program directed toward the demonstration of breeder reactors essential to the long-range goal of utilizing fertile fuels. (1) With-in this program is the current thinking that the early construction and operation of two or three prototype nuclear power plants of the order of 250 Mw(e) will lead eventually to the construction of practical and economic full scale breeder reactors by the early 1980's. (2)"

Errata sheet listing corrections to three pages of a report that describes a transistorized automatic counting and recording system built for the determination of foil-activation data.

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during March 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.

Report containing "analyses of thin, flat, circular plates subject to bending" (p. 7) using various equations for use as equipment for the Argonne National Laboratory Zero Gradient Synchrotron.

Report containing "analyses of thin, flat, circular plates subject to bending" (p. 7) using various equations for use as equipment for the Argonne National Laboratory Zero Gradient Synchrotron.

Report concerning the study of the two-phase flow through the cooling channels of a natural-circulation boiling water nuclear reactor. "One-dimensional conservation equations describing the flow through each channel are written in the linearized perturbed form, and Laplace transformation in time is performed." (p. 5)

From Abstract: "An alternative approach is presented with attempts to demonstrate that insight may be gained from a consideration that the basic cause of the effect may be due to reactivity rather than to period as the previous authors assumed. Methods for compensating for this effect are discussed."

Report concerning "the unstable behavior of a heat-transfer loop operating at a super-critical pressure (p. 7)" within a nuclear reactor.

"WR16, a program written in 3600-FORTRAN for a CDC-3600 digital computer, calculates, as a function of time, the concentrations of all the species taking part in the simultaneous first- and second-order chemical reactions occurring during and after exposure to ionizing radiations occurring during and after exposure to ionizing radiation of any chemical system (for example, an aqueous solution). Homogeneous reaction kinetics is assumed for the computation. The variation of electrical conductivity and optical absorbance of the system can also be computed" (p. 1).

Report issued by the Argonne National Laboratory discussing the PACER-65 computer program. As stated in the summary, the program "has been developed and utilized for flow sheet calculations and process-data reduction. PACER-65 is an executive program in which material- and energy-balance equations, conversion factors, etc., for each processing step are described by separate subroutines" (p. 5). This report includes tables, and illustrations.

Report issued by the Argonne National Laboratory discussing acoustic-boiling-detection techniques. As stated in the abstract, "this report summarizes literature through June 1967 concerning acoustic methods. In the acoustic method for boiling detection, either acoustic waveguides or high-temperature acoustic sensors are recommended" (p. 1). This report includes tables, and illustrations.