For presentation at ASCE Convention in Reno, Nevada on Thursday, June 23, 1860. A description of the Hallam Nuclear Power Facslity is presented. The history of the project, program participants, site description, component development program, reaetor building, reactor structure, reactor core, sodium systems, instrumentation and control, fuel and component handling, auxsilary sustems, special design features, and advantages of sodium graphite reactor systems are discussed. (M.C.G.)

The admittance and transfer functions of large, solidcore electromagnets were determined. The effects of eddy currents and hysteresis were considered in deriving the functions. The study was concerned with the type of magnet employed in nuclear physics research which requires very precise regulation of the magnetic field. The study originated during the design of an analyzing magnet regulator for the ORNL 63-inch cyclotron. (W.D.M.)

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Development of a radioisotope-fueled thermoelectric power-conversion system for the SNAP program is discussed. The generator operates at somewhat less than 1% over-all efficiency, has a power output of approximately 1.45 watts, and has a specific power of 0.l42 watts per pound. The power-flattening device did not perform as expected. A second generator is also described which produces a maximum power of 1.6 watts, has a maximum efficiency of 1.20%, and has a specific power of 0.32 watts per pound (exclusive of the weight of the heat source). (auth)

Report regarding the study of an underground group-shelter meant to protect against nuclear blasts, radiation, and fallout. The report presents a design for such a shelter, the minimum requirements that such a shelter should meet, a description of its facilities, illustrations, and an operating manual.

A pilot model of an Aerodynamic Raindrop Sorter was constructed along the lines suggested by mathematical analysis. The function of the analyzer is to sort natural rain according to drop size and to collect the sorted drops for further analysis. The pilot model, a small wind tunnel inclined at 45 deg to the horizontal, demonstrated the feasibility of aerodynamic rain drop sorting over a wide range of drop sizes. (auth)

An apparatus for determining linear thermal expansion data up to 1350 deg C for materials that cannot be heated in air is described. Expansion is not measured directly, but is derived from the differential expansion between the material being tested and the materials of construction of the dilatometer. The apparatus is calibrated against published data on the linear thermal expansion of both fused silica and polycrystalline tungsten metal. It can be operated either as a high-vacuum or as a controlled-atmosphere apparatus. Recording of data is either fully automatic or manual. The percentage error is believed to be no greater than plus or minus 0.1 to 0.2%. Original data for linear thermal expansion of materials such as hot-pressed BeO, hafnium-free ZrC/sub 2/, zirconium-free HfO/sub 2/, INOR-8 alloy, siliconized silicon carbide, uranium dioxide, compositions of Be + BeO, and samples of CS 312 graphite, boron nitride, and tungsten metal. (auth)

Separation processes for production of pure rare earth oxides in useful quantities are discussed. A review of applications of these oxides in the ceramic industry in production of glasses, glazes, porcelain enamels, refractories, abrasives, electronic ceramics, and nuclear ceramics is also presented. 46 references.

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Report issued by the Argonne National Laboratory over design studies conducted on Argonaut reactors for training and research purposes. As stated in the abstract, "the design presented in the form of a steady-state analysis based upon the small-signal linearization of the reactor kinetics transfer function. The measured controller performance and construction details of the equipment is given" (p. 7). This report includes tables, illustrations, and photographs.

A study has been made of the wear and friction phenomena associated with sliding molybdenum surfaces lubricated by liquid sodium. Operating conditions included sodium temperatures from 250 to 1300 deg F, sliding speeds of from 0.22 to 2.5 nan per sec, and contact stresses of 80,000 psi. Sliding specimens consisted of a ball and a flat rectangle. Sodium was found to influence the sliding behavior of molybdenum by modifying reacted films which provided boundary lubrication. These effects were also found to be temperature dependent. Addition of clean sodium between dry rubbing molybdenum surfaces in an argon atmosphere of high purity produced a marked drop in friction coefficient, and the character of the wear scar changed from galling to superficial scratching. Furthermore, these effects persisted after removal of sodium by evaperation. Studies of the films formed on molybdenum surfaces during sliding in liquid sodium and under controlled atmospheres were carried out using electron and x-ray diffraction, electron microscope, and differential thermal-analysis techniques. It was established that a sodium molybdate film on the molybdenum surfaces can be associated with low friction and diminished surface damage. Studies in vacuums up to 10/sup -6/ mm of mercury showed that native oxides on molybdenum also …

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Production of Pu nitrate from separations plants exceeded commitments. Two Np recovery runs were made, a routine one at Purex and a demonstration run at Redox. Total Np recovered in CY 1959 was 5.7 kg. The UO{sub 3} plant production and shipments also met commitments. Production of unfabricated Pu metal continued. Process studies are being conducted in Purex to resolve the problems in the Np recovery effort. A new solvent (hexone) condensate decanter was operated in Redox. Reprocessing of nonproduction reactor fuels is being reviewed. (DLC)

This report presents a brief survey of the current status of technology on organic-cooled reactors.

The current technical and economic status for each reactor concept in the Civilian Power Reactor Program is summarized. The individual techical status reports which present detailed information will be published by AEC as TID-8518. Included in this summary are: power costs for various reactor types versus coal- fired plants; construction schedule for heavy-water natural-U reactors; and annual program costs. (T.R.H.)

The status of technology of nuclear power reactors in 1959 is reviewed. General research and engineering development activities are discussed. The reactors considered include the pressurized water, boiling water, light water moderated superheat, organic cooled, sodium graphite, gas cooled enriched fuel, gas cooled natural uranium, fast breeder, aqueous homogeneous, and heavy water. Power costs are compared with the cost of power from conventional plants. (C.H.)

The status of pressurized water reactors on a technical, economic, and operating experience basis is reported. Items covered include concept description, PWR objectives, general research and development prcgram, reactor data, reactor illustrations, operating experience, construction and operation schedules, and present limitations and problems. (W.D.M.)

The status of a program to develop a thermal breeder power reactor which is based on the Th-U/sup 233/ cycle is discussed. The general characteristics of two-region power breeder reactors which are either solution-core slurryblanket or slurry-core slurry-blanket are described. A review of studies on corrosion, physical properties, and metallurgy of fuel materials, in particular aqueous ThO/ sub 2/ suspensions, is presented. Development studies on cladding alloys are discussed. The processing of fuel and blanket materials for removal of fission and corrosion products and recovery of fissionable material is discussed. A flowsheet for the preparation of ThO/sub 2/ slurries is contained. Development studies on reactor components, systems, instrumentation, and control are reviewed. Reactor-control, safety, and criticality studies are discusspd. (C.J.G.)

Estimates indicate that, within the D/sub 2/O-moderated natural-uranium- fuel reactor category, the lowest cost reactor will be cooled by boiling D/sub 2/ O. The margin over nonboiling is small, especially for reactors in the 100Mw(e) size and smaller. A major area in which research must be advanced before any of the reactor concepts can be successful is fuel-element fabrication and irradiation behavior. Both oxide and metallic elements have their own advantages, and each type should be developed. Other areas in which additional work must be done are the reactivities of various fuel lattices. fuel element burnout (especially for the boiling regime), zirconium pressure tubes and their connections to steel, and methods of reducing and detecting D/sub 2/O leakage. (auth)

This report addresses the status report on boiling water reactor technology as of 1959.

The current development status of the sodium graphite reactor concept is described. The development history is summarized, and all important areas of development are discussed. The discussion of the SGR program is broken into three categories: (1) general research and development, dealing with reactor physics, fuels and materials, components, etc., (2) experimental reactors, operating or in some phase of design or constnuction, and (3) power demonstration reactors, operating or in a design or constnuction phase. (W.D.M.)

A description of fast reactor types is given and the objectives of the AEC program on fast reactors are outlined. General research and development programs completed and in process on physics, fuel and materials, heat transfer, fluid flow, coolant chemistry, reactor safety, and components and systems are discussed. Reactors completed, under design and construction, and under study are described. (W.D.M.) A general description of ship and power plant, tabulation of principle characteristics, economics, potential advances, and necessary research and development are discussed in detail. (W.D.M.)