This report contains seven different configurations of support blocks.

Before a reactor is launched into a satellite orbit about the Earth, the hazards to the population must necessarily be considered in the event that the reactor re-enters the Earth' s atmosphere and possibly impacts with the ground. Analytical and experimental efforts for calculating these potential hazards as they apply to SNAP-2 and -10A are described. (auth)

This report is to evaluate a silver plated aluminum Bar-X seal's effectiveness in extending the range of ability to seal such a damaged plug.

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An analysis of the effects of a sodium-water reaction in The Babcock & Wilcox Full-Size Steam Generator was conducted. A leak in a tube of the unit would cause a sodium-water reaction which would result in the rapid generation of quantities of reaction products, including hydrogen and high temperature

The analytical results reported herein are a description of the nuclear environment produced by the Aerospace System Test Reactor at General Dynamics/Ft. Worth in the LRP Mechanical Radiation Test No. 901.

A critical experiment program is carried out in a configuration similar to the BONUS reactor. The results give information concerning: the effects of different boilersuperheater geometries; the reactivity changes associated with superheater voiding or flooding; power regulation between the boiler and superheater regions; epithermal transmission probabilities for B-stainless steel and Cd control rods; the power flattening characteristics; and void simulation properties. The calculational methods used in the study predict the measured reactivity and power distribution to within the limits of experimental accuracy. (T.F.H.)

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"Acoustic energy generated by mechanical or electrical signals and its effect on pool boiling of isopropanol were studied. Daring the course of the investigation, a method was devised to determine the amount of heat-transfer surface wetted by the boiling isopropanol. Plots of heat flux versus temperature difference for each frequency showed that the acoustic energy did not significantly affect the heat flux at burnout, but slightly increased the critical temperature difference. No general effect of frequency variation was found even at the frequencies of the "boiling songs" of isopropanol. The over- all effect of the acoustic energy was to disturb the vapor tending te coat the heat transfer surface. This was most evident from the absence of film boiling even at temperature differences far above the critical temperature difference. The application of alternating current to the boiling system gives promise of a self-regulating method to increase boiling heat transfer when required, and is the most significant new finding of this investigation. Two pertinent Russian papers were translated and are appended."

Studies were made to ascertain what useful satellite and/ or space missions may be accomplished with the SNAP 2, 8, and 10 power systems within the 1960 to 1970 time period, to delineate useful satellite and/or space missions which would most profitably employ nuclear power sources, to ascertain what restrictions are imposed on various payloads as a result of having a nuclear power system on board, and to investigate the general vehicle integration and installation requirements of the SNAP 2 and 10 power units. Space flight programs, characteristics and limitations of SNAP, applications of nuclear power supplies. design integration, and system integration are discussed. (M.C.G.)

Methods are presented for determining the electric power requirements of a given communications mission in terms of mission and orbit parameters. Analyses were made of possible applications of available and projected space auxiliary power units in these satellites. The satellitc as a communication node is discussed. Example calculations are given. (M.C.G.)

Investigatiors were made of various materials for development of metal- canned and semi-homogeneous GCRE-II fuel element concepts. The materials were studied for application to development of fuels, grapanite, silicon-silicon carbide coatings, metal claddings, carburization barrier coatings, and graphite joining. A survey of the literature showad that uranium carbide fuels are superior to other types for the applications described and that refractory metal or metal carbide fuel coatings appear superior to other types for use with the types of graphite investigated. Experimental measurements were made of the thermal conductivity, tensile strength, stress-strain reiationships, and thermal expansion of graphite powdsr bonded with baked carbon at a final firing temperature of 760 deg C. Results showed that these materials were stronger and more isotropic at all test temperatures than a standard structure graphite such as ATJ. The thermal conductivity is somewhat lower and the thermal extansion slightly higher than the corresponding properties of ATJ. A silicon-silicon carbide coating was developed as an osidation-resistant coating for graphite. Preliminary air oxidation tests at 1000 deg C showed that the first samples survived 2000 hr with 10% failure. Subsequent experiments showed that it is reasonable to expect better performance in further tests. Tests for compatibility with …

Report presenting a state-of-the-art survey of automatic indexing systems and experiments. It was conducted by the Research Information Center and Advisory Service on Information Processing, Information Technology Division, Institute for Applied Technology, National Bureau of Standards. Consideration is first given to indexes compiled by or with the aid of machines, including citation indexes. Advantages, disadvantages, and possibilities for modification and improvement are discussed. Experiments in automatic assignment indexing are summarized. Related research efforts in such areas as automatic classification and categorization, computer use of thesauri, statistical association techniques, and linguistic data processing are described. A major question is that of evaluation, particularly in view of evidence of human inter-indexer inconsistency. It is concluded that indexes based on words extracted from text are practical for many purposes today.

This the the final report documenting some basic studies on radiation technology for the purpose of generating and developing new technical information of pertinence to radiation processing through basic studies in radiation technology.

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Two IBM-704 codes have been written which are auxiliary to the Bevatron orbit code BOC. The first, BEFCYF, interpolates among tabulated values of the median-plane magnetic flux density of the Bevatron to produce an equivalent array of values in a form appropriate to BOC. The second, DBDT, produces azimuthal derivatives of the fields produced by BEFCYF. The internal operation of BEFCYF and DBDT is described, and instructions for their execution are given.

The scope of this report defies a concise abstract. In lieu of an abstract, the following topical outline will both indicate the subjects covered and show how these subjects are organized. Part I, Engineering Aspects: Blister Formation, Temperature Effects, Cooling Effects, Drive Connections, Housing Effects, Housing Materials, Radiation Effects. Part II, The Behavior of Boron Carbide-Aluminum Poisons: Swelling, Swelling Rates, Restraint, Material Behavior.

This technical report reviews the general purposes and immediate goals of the Heat Transfer Group at BNL's study of the heat transfer characteristics of alkali metals with phase change in forced convective flow. This report also presents a brief description of the design and development of the test loop. Figures detailing findings accompany the report.

From introduction: The study is based entirely on observations which have been made at a number of different installations at which boiling songs and vibrations were noted during heat transfer experiments.

Abstract: An experimental and analytical research program is described which is designed to meet certain specific needs for data and methods required to make improved predictions of transient voids, burnout, flow, and fuel temperature during extreme accidents in sodium-cooled reactors.

The Richland 02 Five-Year Process Development Program has been divided into 10 missions. The missions by title were: Basic Production; Coproduct; Transplutonium; Pu-238; Other Isotopes; Enriched Fuel Processing Target Space Enhancement Nuclear Safety; Waste Management; and Columbia River Studies. Although in general most of the same efforts are incorporated, the mission concept is being dropped, and the following designations for programs have been adopted: Basic Production; Product Flexibility; Waste Management; and Environmental and Regulatory Technology. The programs to be carried out are described in this document. The reports are brief, but as per AEC-RL instructions, additional details can be found in the annual documents issued at the beginning of the fiscal year and the semiannual research and development reports issued in January of each year. In some instances it is anticipated that the level of funding will be supplemented by process technology funds.

The concept of overboring the graphite channels in an older Hanford reactor and installing oversized tubes charged with oversize fuel elements is being investigated at C reactor. Recently a column of these oversized test fuel elements exhibited three uranium cleavage (split) type failures after experiencing severe reactor flux cycling. This report presents a preliminary description of both the fuel failures and the flux cycling encountered by the reactor.

Abstract: The design and initial test of cutting and welding equipment developed to remotely cut and re-weld the bottom process tube joint are discussed in this report.

This report provides some of the selected references on Capital Punishment