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Determinations of Aerodynamic-Drag Parameters of Small Irregular Objects by Means of Drop Tests: Report concerning the results of an experiment that determined the masses and velocities of over 20,000 objects and laboratory animals by simulating the blast winds of nuclear explosions.
Nuclear Bomb Effects Computer (Including Slide-rule Design and Curve Fits for Weapons Effects): From Introduction: "The primary purpose of this report is to describe the analytical procedures involved in the design of a circular slide rule and to discuss its usage and limitations in the evaluation of the effects of nuclear weapons."
Nitride Fuels for Fast Breeder Reactors: Fuel Cycle Considerations: This report follows a study that was made to develop comparative fuel cycle costs for nitride and carbide fuels in a 1000 MWe sodium-cooled fast-breeder reactor.
Post-Test Physical, Chemical and Metallurgical Analysis of SNAPTRAN-3 Fuel: The fuel element damage which occurred during the SNAPTRAN-3 Destructive Test of a Snap 10A/2 reactor is described. Chemical analysis of the fuel indicated that approximately 15% of the hydrogen was released and that the core flux was higher toward the center both radially and axially. Metallurgical analysis of the fuel determined the presence of the epsilon, delta, and gamma phases in the grain structure and evidence of a possible alpha or beta phase.
Hematological Effects of Whole Body Irradiation: The development of nuclear arms added the effects of ionizing radiation to the direct and indirect mechanical, chemical or thermal hazards of "conventional" weapons. The biological effects of ionizing radiation are the result of absorption of energy and the morphologically recognizable damage is poorly understood. Although new in their use in weapons and difficult to evaluate in their consequences, ionizing radiations are by no means new to physicians. Furthermore, medical experience has shown that clinical consequences of radiation injury are similar to those with which the clinician has to deal with every day in the treatment of neoplastic disorders and its complications. Soon after the discovery of x-rays by Roentgen and of the phenomenon of radioactivity by Bequerrel in the last decade of the last decade of the 19th century, it was found that ionizing radiation can produce marked biological effects by interfering with cell- and organ functions. Senn and Hussey were the first to effectively treat leukemia by this means. This, since about 60 years, ionizing radiation has been a powerful tool in the hands of physicians both in diagnostic procedures and for therapy of malignant disease. It should not be forgotten however, that the price paid for this contribution of outstanding importance was high. Long before any nuclear weapons were used, a long list of fatalities and injuries among physicians, investigators, technicians and nurses, witnessed the possible consequences of radiation exposure. However, the number of lives saved through the use of ionizing radiation exceed greatly the number of lives ever lost through the harmful effects of radiation.
Pathogenesis and Regeneration of Radiation Induced Bone Marrow Injury, and Therapeutic Implications: This report reviews aspects of experimental and clinical research performed in the investigation on the pathogenesis and recovery of bone marrow injury caused by total body irradiation.
Problems of Bone Marrow Cell Transfusions: This technical report explores bone marrow cell transfusions and the effectiveness of treatments in both animals and humans in the clinical setting. It also proposes a means by which to label bone marrow prior to transfusion in order to follow the fate of the cells. Includes six figures to accompany the findings of this report.
The Fate of Transfused H3 Thymidine Labeled Bone Marrow Cells in Irradiated Recipients: It has been established by chromosome marker studies, histochemical, immunological, and cytological methods that the hemopoietic tissues of animals exposed to lethal doses of whole-body irradiation can be repopulated by transfused autologous, homologous or heterologous bone marrow cells. However, the morphology of the cell responsible for the regeneration of hematopoietic activity in the various hemopoietic organs has not been identified. It has been shown that the bone marrow contains the cell or cells capable of regenerating all types of hemopoietic tissues. In order to identify transfused cells, one must have a label which persists through successive divisions. Odell and Smith labeled the donors with S35 methionin and were thus able to follow the accumulation of the donor marrow cells in the recipients lungs and subsequently their releases to the bone marrow and spleen. However, this compound has a relatively rapid turnover in the labeled cells and thus a relatively limited capability of serial studies to observe mitosis and differentiation. Tritiated thymidine is ideal for this purpose since it is incorporated solely into DNA and is diluted only by mitosis. In addition the high resolution with tritium makes it certain that one is observing nuclear labeling. Bond et al. have studied the migration of labeled cells from a non-irradiated parabiotic rat to the irradiated member. Nagal and Knisely have studied the fate of in vitro labeled autologous and homologous bone marrow cells after transfusion into two patients. Balner et al have labeled bone marrow cells in vivo with H3TDR and transfused these labeled cells into irradiated homologous newborn mice and studied their distribution as a function of time following transfusion by [unintelligible] of autoradiography.
Nuclear Superheat Quarterly Project Report: Fifteenth Quarter, January-March 1963: From introduction: "This is the fifteenth in a series of quarterly reports which cover the progress and results from the conceptual designs, economic evaluations and research and development work performed by the General Electric Company as part of Contract AT(01-3)-189, Project Agreement No. 13."
Nuclear Superheat Quarterly Project Report: Seventeenth Quarter, August-October 1963: From introduction: "This is the seventeenth in a series of quarterly reports which cover the progress and results from the conceptual designs, economic evaluations and research and development work performed by the General Electric Company as part of Contract AT(01-3)-189, Project Agreement No. 13."
Nuclear Superheat Quarterly Project Report: Sixteenth Quarter, May-July 1963: From introduction: "This is the sixteenth in a series of quarterly reports which cover the progress and results from the conceptual designs, economic evaluations and research and development work performed by the General Electric Company as part of Contract AT(01-3)-189, Project Agreement No. 13."
Nuclear Superheat Quarterly Project Report: Eighteenth Quarter, November, 1963-January, 1964: From introduction: "This is the eighteenth in a series of quarterly reports which cover the progress and results from the conceptual designs, economic evaluations and research and development work performed by the General Electric Company as part of Contract AT(01-3)-189, Project Agreement No. 13."
Determination of Beryllium, Thorium, and Uranium in Sulphuric - Phosphoric Acid Mixtures: Methods are described for the determination of traces of Be, Th, and U in concentrated sulfuric-phosphoric acid mixtures. When the Be concentration is sufficiently high, the chrome azurol S spectrophotometric method may be applied directly, and a small correction made for phosphate interference. At lower concentrations Be should be first separated by an acetylacetone extraction. Th must be separated from sulfate and phosphate before the thoronol spectrophotometric method can be used. This is achieved by precipitating Th as the fluoride, using Y carrier. U may be determined spectrophotometrically with arsonazo after separating Be, Th, suIfate, phosphate, and other impurities by anion-exchange from hydrochloric acid solution. In an alternative procedure, U is reduced to the tetravalent state and precipitated with Th as the fluoride, again using Y carrier. The determination is then completed by a-c polarography.
Final Report of Piping Components for Organic Coolants: Organic compounds with high boiling points and low corrosion qualities have been considered for use as reactor coolants and moderators. Those being considered, however, have a greater tendency to leak than does water. A program to evaluate mechanical closures to be used for a leak-tight system for organic fluids has been established. Report HW-59446 covered descriptions of the facility used in this study and the primary results of tests covering two liquids, fittings, and instrumentation. This report will cover final results and other pertinent information.
A New Design Concept for Reverse Osmosis Membrane Cells: From Introduction: "A new concept, that of lateral permeation of product water through a porous substrate, is the basis for both the cost reduction study of plate-and-frame reverse osmosis units and the study of field replacement of membrane and is therefore the subject of the development studies encompassed by this report."
Process and Configuration Development for Tubular Reverse Osmosis Units: From Introduction and Summary: "The overall objective of this program was to develop an economical tubular reverse osmosis system for desalination of brackish water. Major emphasis was placed on the following aspects of the system. The work accomplished is summarized in the following paragraphs."
Conceptual Design Study of a 50 Million Gallon Per Day MSF Desalination Plant and Test Module: Report issued by the Office of Saline Water over design studies for a 50 million gallon desalination plant. As stated in the introduction, "this report presents a conceptual design of a 50 MGD multistage flash plant and a conceptual design of a test module based on the 50 MGD plant design and proposed to demonstrate large plant design concepts. The report also includes a discussion of the more important engineering design studies employed in the development of the conceptual designs" (p. 1). This report includes tables, and illustrations.
Absorption-Multistage Flash Distillation Process: "The major factors which influence the cost of water production from sea water by distillation methods are (1) the cost of fuel or energy required by the distilling plant, and (2) the required capital investment. Preliminary studies on the application of absorption or solution cycles to distillation methods for saline water conversion indicated that the fuel cost or thermal economy of a distillation plant could be improved by combining the distillation process with an absorption or solution cycle" (p. 1).
The Use of Activated Charcoal Iodine Monitors During and Following a Release of Fission Product Iodines: The present core of the Brookhaven Graphite Reactor consists of some 4900 highly enriched uranium fuel loaded in 615 horizontal fuel channels passing through a 25 foot cube of graphite moderator and reflector. The core is divided into two halves (north and south) by an 8 cm. wide vertical gap in the center of the graphite. The cooling air enters the reactor through inlet filters, at the rate of 270,000 CFM, passes into the central gap and flows bi-directionally through the north and south halves of the core. It then enters the collecting plenums and flows into the north and south ducts. The air is first monitored by the north and south exit air monitors located within the pile building. These are moving filter tape monitors with beta scintillation detectors. They are essentially operational monitors and are maintained by reactor operations. They are essentially operational monitors and are maintained by a reactor operations. The air then passes through the exit air filters, heat exchanger, venturi and on to the fan house where the north and south ducts join. After the fan house the air is monitored by Argon-41 by a Kanne ion chamber syste.
Design Summary Report on the Juggernaut Reactor: Report issued by the Argonne National Laboratory over design studies conducted on the Juggernaut reactor. Design processes, and methods are presented and discussed. This report includes tables, illustrations, and photographs.
Two Modes of Pulse Recording on Magnetic Tape: Methods and equipment are described whereby electrical pulses are recorded on magnetic tape in two different ways, using a commercial, single-track type deck, The first method is used to record count rate information regarding regularly or randomly occurring pulses. Random count rates up to approximately 2,000 per second can be directly recorded without serious dead-time loss. By the addition of a simple, high-resolution scale-of-4, the input count rate can be increased to approximately 20,000 per second. By the other method information about relative pulse amplitude as well as count rate is recorded. The usable amplitude analogue output corresponds to an input range of at least 7 to 1, with linearity of approximately 1 1/2 per cent of maximum amplitude. Amplitude resolution of 2 to 3 per cent is obtained over the upper 70 per cent of the range. Transistorized circuitry is described which enables the output pulses of the tape recorder to be analyzed by a Radiation Counter Laboratories Inc. 256 channel scaler-analyzer.
Argonne National Laboratory Metallurgy Division Annual Report: 1963: Annual report issued by the Argonne National Laboratory discussing work conducted by the Metallurgy Division during 1963 including progress related to experiments, programs, and studies. This report includes tables, illustrations, and photographs.
Metallurgy Division Quarterly Report [for] October, November, and December 1955: A total of nine clad plates, containing uranium -5 w/o zirconium 1.5 w/o niobium alloy cores and clad with Zircaloy-II, were rolled in plain carbon steel jackets, heat treated, physically evaluated, and corrosion tested. All these plates were found to be within predetermined dimensional tolerance in width, thickness, length, cladding thickness, and core distribution. Improved control of wielding variables and of the length of the seal pin projecting above the end plugs resulted in the elimination of frequently observed segmented inclusions at the seal pin interfaces.
The Synthetic Liquid Fuel Potential of Louisiana: Report documenting the suitability of Louisiana for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.
Mass Yields From Fission by Neutrons Between Thermal and 14.7 Mev: Radiochemically determined mass-yield curves are given for the fission of U235 and U236 by 14.7-Mev neutrons.
Photoproduction of Beryllium-7: From abstract: "The nuclide Be7 has been produced by photoactivation of Be9, B and C12 using the bremsstrahlung beam of an electron synchrotron operated at 45 Mev. Integrated cross sections for the formation of Be7 have been estimated by comparison with the Ta181([gamma],n)Ta180m reaction. The reaction C12([gamma],2p3n)Be7 has also been observed in irradiations at 30, 35 and 40 Mev maximum energy. Its yield has been compared with that of the C12([gamma],n) reaction at 45 Mev. The reaction A127([gamma],2p3n)Na22 was observed at 45 Mev."
Helium-Purification Unit for High-Purity Inert-Atmosphere Boxes: From Summary: "A device for purifying and recycling the helium atmosphere of two dryboxes having a combined volume of 60 ft3 is described. Regeneration procedures are given."
Cubic Spline, a Curve Fitting Routine: A method of mathematically fitting a curve through a given ordered set of points has been developed and programmed in fortran computer language.
Generalized Heat Conduction Code for the IBM-7090 Computer: The IBM-70% code GHT has been programmed for the 7090computer, to be run under control of the IBM-7090 FORTAN Monitor System. By eliminating the use of tapes for intermediate number storage, it has been possible to reduce computing time by a factor of 26 over the 704. A minimum of three tapes are required; one for input, one for output, and the System tape. One scratch tape is required for transient problems, and one punch tape is required if the steady-state temperature distribution is to be punched on cards.
Equipoise-2: A Two-Dimensional, Two-Group, Neutron-Diffusion Code for the IBM-7090 Computer: Equipoise-2, a two-dimensional, two-group neutron-diffusion code in R-Z geometry, has been programmed for the IBM-7090 computer. This code was designed to permit the running of large numbers of cases without requiring excessive machine time. Typical running times are of the order of one to three minutes per case for a 1000-point problems. The maximum number of mesh points that can be used is 1444.
Preliminary Solution Critical Experiments for the High-Flux Isotope Reactor: Report containing experiments conducted at the Oak Ridge National Laboratory's Critical Experiments Facility. These experiments involved "determining the critical parameters of the assembly with varying amounts of neutron absorber in the D20 reflector, measuring the relative neutron flux distribution for various conditions of reflector poison and fissile solution concentration, determining the ratio of the absolute thermal-neutron flux in the center of the assembly to the power in the fissile solution , and determining the effect on reactivity of reducing the hydrogen density in the central region of the assembly" (p. 1).
A Simulator for High-Density Ion Guns: Report the describes a simple accurate simulator that can predict the ion trajectories in and ion gun for certain electrode geometries.
High-Energy, Low-Thrust Jupiter Missions: Previous studies have been made of the relationship among acceleration, specific power, payload fraction, and travel time for many interplanetary missions. These utilized tangential thrust and correspond to the high thrust Hohmann transfer orbits. In addition, a complete optimization of the one way Mars mission has been accomplished. Since the minimum Jupiter round trip time was six and a half years for tangential thrust, calculations were carried out using higher energy transfer orbits. It is shown that the orbit-matching problem cannot be solved with tangential thrust programming in this case. The initial period of acceleration away from the earth's orbit was accomplished using tangential thrust in order to minimize energy expenditure. This was followed by a period of coasting until the proper moment arrived for commencing the orbit-matching maneuver. This terminates when the velocity and spatial coordinates of Jupiter's orbit are matched. The technique used for accomplishing these various orbit matching conditions without iteration are described. Best results for the final maneuver were obtained with the thrust vector approximately normal to the velocity vector. By this technique it is shown that the round-trip Jupiter mission may be carried out in four and an half years with 16% payload and 0.10 kw/kg specific power. The acceleration is about 0.12 cm/se,. Increasing he specific power by a factor of two does not materially affect the time. Although the specific power requirement is about the same as for the Mars or Venus trips, the mission is in fact much more difficult since the required power-on-time of the power plant is increased by a factor of three. Typical values are one and half to two years.
Propellants for Electrical Propulsion Systems : Panel Discussion of Rocket Propellants, American Chemical Society Meeting, Berkeley, August 8: As we might suspect, the propellant problems for electrical propulsion systems are quite different than those of chemical or nuclear propulsion schemes. In those cases, two of the most important parameters were the propellant temperature and mean molecular weight. Here we are sidestepping the temperature requirement entirely by using electrical energy for the energy source rather than chemical or thermal energy. Of course, mission analysis have demonstrated that the energy per unit weight requirements are so large as to rule out all except nuclear or solar sources for this energy. As a result, nearly all the weight of the propulsion system is in the electrical power supply. Consequently, the efficiency of the thrust system in converting this electrical energy into directed mechanical energy of the propellant is one of its most important parameters. In addition, it must have exceedingly long operating life, say a year or so, and its electrical characteristics must match those of the power source.
Preliminary Designs for Four Integrated Gas-Cooled Ceramic-Fueled and -Moderated Reactor Core and Steam Generator Units: Report containing preliminary designs for four reactor core and steam generator units. The units, their difficulties, and the layout of the reactor building are described.
Sources and Availability of Helium: A review of helium sources, availability, consumption, and future production capacity indicates that the helium consumed in the operation of 100 helium-cooled reactors for 300-Mwe power plants over a 20-year period will run no more than a few per cent of the helium consumed in the U. S. in the next 25 years and less than 1% of the helium that is to be stored during that period under the helium conservation act of 1960 (Public Law 86-777).
A Comparison of Gas-Turbine and Steam-Turbine Power Plants for Use with All-Ceramic Gas-Cooled Reactors: Report that "compares gas turbines with steam turbines as means of producing electric power from gas-cooled reactors with all-ceramic fuel elements." (p. 1)
Preliminary Design of a 10-Mw(t) Pebble-Bed Reactor Experiment: The objectives of this study have been to examine the problems of the pebble-bed reactor concept and to conceive a design of a facility for investigating the feasibility of this type of reactor. The design must provide for adequate leaktightness of the contaminated-gas system and adequate maintenance of contaminated components, the most vital feasibility questions of the concept.
Design Study of a Pebble-Bed Reactor Power Plant: Sanderson & Porter have carried out a series of studies over the last four years which indicate that the pebble-bed reactor way be an attractive way to obtain low-cost power. At the request of the Atomic Energy Commission, two design studies have been carried out on this concept at the Oak Ridge National Laboratory. The first of these a preliminary design of a 10-Mw(t) reactor experiment, the PRRE, was initiated September 10, and a report on the study was issued November 1960. The second phase of the work, a conceptual design study of a 330-Mw (e) central station, was initiated November 1, and is the subject of this report.
Steam Generators for High-Temperature Gas-Cooled Reactors: Report describing a study that "was undertaken to provide a sound basis both for the optimization of either axial-flow or cross flow steam generators and for the evaluation of the relative merits of major design features" (p. 2).
Electrostatic Separation of Granular Materials: From Introduction: "It is purpose of this publication to describe the development of the electrostatic method of particle separation from the early beginning to the present resurgence of interest. Most of the information for this description has been derived from references, a few of which were not available for thorough review."
The Diffusion of Fast Neutrons: From American Nuclear Society Meeting, New York, Nov. 1963. The use of the asymptotic solution to the one-velocity transport equation is considered. The angular distribution for fast neutron elastic scattering by heavy elements is discussed. An exponential angular distribution on is assumed to simplify the decay length calculation. The diffusion length of 1 to 15 Mev neutrons in iron is calculated, as well as the vector flux angular dependence. The asymptotic solution for an arbitrary angular distribution of a plane delta -function source is also found. An isotropic source is investigated, and some applications of the model are examined.
Irradiation behavior of unalloyed hypostoichiometric uranium carbide, experiment AI 3-11 and review: A report regarding the irradiation behavior of Unalloyed hypostoichiometric uranium carbide experiment AI 3-11 and review
An Experimental Gamma Irradiator for Hospital Sterilization: From foreword: This report presents the preliminary design of a gamma irradiator intended for use as an experimental hospital sterilizer.
An Industrial Gamma Irradiator for Medical Supplies: From foreword: This report presents the preliminary design of an industrial gamma irradiator for the sterilization of medical supplies.
Spark-Source Mass Spectrometric Analysis of Common and Radiogenic Lead: Analysis that is fast and has extremely low levels of detection for more than forty elements that may be present in lead.
Fluoroscopic Crystal Investigation: "An investigation was carried out on the possibility of increasing the light output of single crystals by applying an electric field throughout the crystal lattice. Pulses of frequency 2.5 x 10/sup 5/ cps were used with a voltage gradient of 10/sup 4/ volts/cm, and gamma radiation from Cs/sup 1//sup 3// sup 7/ and Co/sup 6//sup 0/ was used to excite the crystals. Tests were run on many types of scintillators. The visible light output was found to be increased by electric pulses for many of the scintillators, the best results being obtained with ZnS(MnCl/sub 2/, AgCl) crystals."
A Differential Transformer Measuring Apparatus: The equipment described was designed for static displacement measurements with linear differential transformer transducers in applications requiring high sensitivity and low drift. The output from the circuit is display on a 10 mV f.s.d. potentiometric recorder and an a.c. back-off arrangement allows the same basic sensitivity up to 20 times full scale deflection. Weekly drift of the output is less than 0.1 mV which is equivalent to an input drift of 0.005 mV. For longer term measurements any drift due to valve aging etc. can be corrected by inbuilt self-checking facilities.
Automatic Scaler A.A.E.C. Type 2A -- Service Manual: This manual is intended to give operating and maintenance information for the range of counting equipment in use by the A.A.E.C. at Lucas Heights, designation of Scaler Type 2A. This equipment has been designed in the General Physics Section of the A.A.E.C. General Nucleonics Division. The equipment was built by an Australian manufacturer (Siemens Nucleonics).
Nuclear Emulsion Experiments in the Inner Radiation Belt: Since the discoveries by the early U. S. and Russian satellites of the great radiation belts which surround the earth a considerable amount of effort has been expended to determine the nature, flux, and energy distribution of the trapped particles. This is done for serval reasons. First, it is important for purely geophysical and geomagnetic purposes to understand the source of these particles as well as the magnetic trapping phenomena and loses mechanisms. Secondly, it is imperative, if one is to travel through space to have knowledge of the radiation present there so that he may shield himself sufficiently and avoid bodily harm from over-exposure to radiation.

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