The fallout hazard and protection factors in current use for large groups of buildings, i.e., urban residential areas, business districts, industrial complexes, government centers, Atomic Energy Commission facilities, and academic and medical institutions, are largely unsubstantiated by experimental evidence. These data are important for personnel protection on a national basis in the event of war and on a local basis in the event of certain types of nuclear accidents. The need for such information is discussed and methods for obtaining it are suggested. The methods suggested should provide a cross check of the data obtained on isolated structures under actual fallout conditions with the data from studies that made use of methods such as distributed point sources and a moving single-point source (as used in the Mobile Radiological Measurement Unit, Civil Effects Test Operations) to simulate actual fallout fields and with data from other studies in which predicted values of fallout protection were calculated from strictiy theoretical considerations. (auth)

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Charts are given which present information on the properties, sources, and uses of Th/sup 230/, Th/sup 228/, and U/sup 232/ They also compare these properties with competitive isotopes. (M.C.G.)

The Salt Cycle Process is a nuclear fuel processing approach designed for application in compact facilities located at the reactor sites. Irradiated UO/sub 2/ fuels would be processed through a brief sequence of steps and partially purified UO/sub 2/ or UO/sub 2/--PuO/sub 2/ powders recovered, suitable for refabrication into fuel elements. The major steps of the process are the dissolution of uranium oxides in molten NaCl--KCl eutectic by chlorination to form soluble uranyl chloride and the reduction of uranyl chloride to UO/sub 2/, which separates as a solid. The preferred method of reduction is the electrolytic method, which yields UO/sub 2/ as a conveniently handled, adherent deposit on the cathode. Means are described for separation of Pu from U and for co-deposition of the Uo. Also included are discussions of the probable nature of the U and Pu species present in the molten salt, side reactions in which uranyl chloride may participate, and the influence of certain variables on the properties of the UO/sub 2/ produced. (auth)

The design information is presented in sections on core thermal performance, fuel elements, moderator, and control rods. (J.R.D.)

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Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.

The Shippingport Atomic Power Station was operated for 715 EFPH from Ang. 11 to Oct. 7, 1959, in order to determine the performance characteristics reliability, stability, and lifetime variation of the core during rated power operation for an extended period of time. The plant was operated at successively lower power levels of 60, 43, and 17 Mwe to extend the Core I, Seed 1 lifetime. Logs and tables are included which present the events and all recorded data in this period. (D.L.C.)

Separate abstracts were prepared on 25 sections of this report. A list of publications during the period is included. (C.H.)

>The performance characteristics of small linear-induction electromagnetic pumps suitable for high-temperature liquid-metal test-loop operation were examined. Also, methods by which the performance of such pumps may be improved were investigated. The phenomenon of fluid wetting of the pump duct wall and the use of side bars provide powerful tools for improving the linear-induction-pump performance characteristics. Full advantage of the improved performance can be obtained if the hydraulic losses are minimized by using a pump section with large duct width, which also improves the power factor and decreases the phase current requirements of the pump. (auth)

For high-temperature applications, fuel element cladding materials are required to protect the base metal structure and to contain the fuel so as to minimize fission product release and fuel loss. Since the early work on clad Mo fuel element concepts, many metallic cladding systems have been investigated for direct cycle reactors. The developments in stainless steel and Ni alloy claddings are reviewed and the more recent applications of new oxidation- resistant ferrous-base and chromium-base alloys as claddings for refractory metals are presented. (auth)

BS>SNAP II is the designation for a 3 kw nuclear auxiliary power unii for utilization in a satellite vehicle. The SNAP Il system consists of a reactor source which utllizes a mercury Rankine engine for power conversion. Design details and test data for the primary fluid reactor coolant pump used to transfer heat from the reactor to the mercury boiler are described. (auth)

A theory is developed by which the motion of the main shock wave originating from cylindrical and spherical blats, as well as the formation and subsequent motion of the secondary shock. are given by explicit formulas. A formulation for giving the location of the contact surface between the detonation gases and the outside atmosphere was obtained. (auth)

Work was continued on the determination of size and distribution of dispersed phase droplets in a pulse column. The droplet behavior and dispersed phase hold-up in Yorkmesh packing was studied with an equilibrated system of methyl isobutyl ketone and water with the ketone phase dispersed. An investigation is being made of the recovery of copper and EDTA from rare-earth ion exchange wastes. The effect of vapor properties on entrainment from bubble cap trays is being investigated. The design, construction, and operation of forced convection loops for circulating liquid metals are reported. The corrosion of 430 stainless steel and 21/2% Cr-l% Mo steel by a liquid lead- bismuth eutectic is reported. The operation of a stainless-steel sodium-cooled liquid-metal condenser is described. The effect of ten additives, including V, Mg, Zr, and Ce in inhibiting the corrosion of stainless steel by lead-bismuth eutectic is being investigated. The current process for preparation of sodium ethyl sulfate is given. Single crystals of Zn, Sn, Pb, and AgCl were grown with a simple, low cost, Bridgman-type crystallizer. Tests were performed at 800 to 1000 deg C on Y, Nb, and Ta loops, circulating Th-Mg and U-Cr eutectics. Work on the development of electromagnetic pumps is …

A complilation of the procedures for the low-power physics experiments to be performed with the SRE second fuel loading is presented. Reactor power will remain below 120 kw. Critical mass, shim rod worths, statistical weights, isothermal temperature coefficient, and reactor transfer function will be measured. (W.D.M.)

Tables of gamma-ray transition probabilities predicted by the asymmetric rotor model of even-even nuclei were calculated. Tables are also presented on the coefficients of the rotational wave functions as a function of k, the asymmetry parameter. A third table gives the values of parameters needed to calculate energy levels in the hydrodynamical model using molecular spectroscopy tables. (C.J.G.)

Test equipment to determine the creep properties of Zircaloy-2 in a 750 deg F 500-psi steam atmosphere was designed and constructed. Duplicate tests were performed at stresses to produce failure in approximately 1, 10, 100, and 1000 hr. A comparison between these data and data obtained in vacuum-test equipment showed that a corrosive test atmosphere does not alter ductility or failure times appreciably. (auth)

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Site considerations for a radiochemical separations plant are discussed relative to geology, hydrology, and meteorology of an area. (C.J.G.)

A listing is presented of documents, films, slides, and those items which were formally produced for utilization by the AEC concerning the SNAP project. (J.R.D.)

A description of a 14-stage electron multiplier for use amplifying the detector signals in a surface ionization mass spectrometer is given. The system can either measure the multiplier anode current or count the anode pulses. Pulse counting may be used for- signal currents in the range from lO/sup -13/ to 10/sup -18/ amp. The range of the normal electrometer circuit is extended by the electron multiplier so that it measures currents from l0/sup -10/ to 10/sup -15/ amp with a fast response. (auth)

A description of the Experimental Boiling Water Reactor vapor-recovery system is given. The seal air operating pressures, temperatures, and moisture content were measured. Air flow through the seals was measured and seal wear was assessed. Assuming direct-cycle D/sub 2/ operation, the seals were evaluated relative to the amount of D/sub 2/ leakage that would be controlled (C.J.G.)

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Separate abstracts have been prepared for 19 sections of this report. (For preceding period see ANL-6104.) (C.H.)