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- An 8-Matrix Theory of the Vertex p - NN Based on the Strip Approximation
- The present study was motivated by an attempt to understand low energy [formula] scattering within the framework of the bootstrap principle and the un-Reggeized version of the strip approximation. This work attempts to generate low energy [formula] scattering in the p(1,1) and p(3,3) states assuming the potential operating in these states is generated by the exchange of low mass meson states in the crossed t-channel and low mass baryon states in the crossed u channel. In particular, the p-meson is kept in channel t; the p mass and the coupling of [formula] and [formula] appear as parameters. The parameters of the nucleon and (3,3) poles are taken as the elements to be determined by self-consistency.
- 80" Bubble Chamber Expansion System Preliminary Operating Procedures
- These procedures are intended to be used for the initial operation of the expansion system and serve as a basis for a more complete and revised form to be written once operating experience has been gained. An attempt has been made to offer a logical and systematic presentation to facilitate operation and maintenance of the system by the operating personnel. Thus, the sequence of valve actuations has been presented in matrix and check list form to minimize errors; this also has the advantage of making it easier to adapt certain expansion system procedures to programmed control by a process control computer.
- 80" Bubble Chamber Expansion System Summary of Piston Motion Studies
- Prior to assembly into the 80" bubble chamber, the expansion system was subjected to a series of tests to check piston dynamics and gain information on the reliability of the various components. Furthermore, the rest provided operating personnel with the opportunity to become familiar with the operation and maintenance of the expansion system. Two separate tests were performed with the apparatus that was located at the north end of the AGS experimental area; one during the week of Oct. 15 and the other during the week of Nov. 12. The system was run with helium gas supplied from AGS compressor room and the piston was operated at room temperature.
- 80" Chamber - Low Energy Beams
- One of the major, as well as first, decisions which must be taken on a large chamber is to decide on the direction of the magnetic field, i.e., vertical or horizontal. Either alternative has advantages and disadvantages ad it is the intention of this note to discuss these features.
- 1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 1
- From introduction: "Summary report of the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company."
- 1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2
- From introduction: "Presents the detailed description of a 1000 MW Electric Power Plant employing one or two Boiling Water Reactors as the steam source."
- 1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3
- From introduction: "Contains the appendices and a complete set of drawings related to the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company for the United States Atomic Energy Commission."
- 6144-Channel Time-of-Flight Analyzer
- Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
- ABCC-NIH Adult Health Study Hiroshima 1958-60. Cardiovascular Project Report Number 6, Heart Size Norm
- Data on 13,000 person 15 yr of age or older obtained during detailed clinical examinations, including radiological recorded heart size, were correlated with sex, age, height, and weight of subjects to arrive at a standard heart size for Hiroshima residents This information will be used in investigations cardiovascular disease in the population.
- Accurate Nuclear Fuel Burnup Analyses; Ninth Quarterly Progress Report, (December 1963 - February 1964)
- The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
- Adult Health Study : Review of Substudies, June 1962, Hiroshima and Nagasaki
- Data are summarized from a series of studies to determine the late effects of radiation in adult populations of Nagasaki and Hiroshima. Results ae reported from studies on skin aging, hair greying, cardiovascular findings, neuromuscular response, antibody levels, ocular aging, auditory aging, and miscellaneous aging characteristics in persons exposed to radiation from the atomic bombs as adults; growth and development studies on exposed persons born between 1935 and 1945; the incidence of neoplasms in the exposed populations; possible genetic effects of radiation in selected groups; the incidence of tuberculosis and other infectious diseases in exposed populations; hematological studies; metabolic studies, and other related studies in exposed persons and their offspring. Possible future programs are discussed.
- Advanced Test Reactor Burnout Heat Transfer Tests
- From abstract: "Results of burnout test to determine the limiting heat flux in a simulated Advanced Test Reactor fuel element channel."
- Advanced Test Reactor Servo Regulator Rod Test Program
- From abstract: "Verify rod mechanism characteristics reported by the United Shoe Machinery Corporation, demonstrate that rod mechanism characteristics were compatible with reactor kinetics and that over-all reactor system behavior was stable, and to recommend system modifications needed for satisfactory performance."
- Advanced Test Reactor Turbo Report
- From abstract: "The time-dependent behavior of the Advanced Test Reactor was calculated by the Babcock & Wilcox Company on the Philco 2000 computer, using the Turbo depletion program."
- AEC Fuel Cycle Program Design and Fabrication of Special Assembly 9-L : Irradiation Performance Test of UO2-Cermet Fuel
- Technical report describing a UO2-Mo cermet fuel assembly fabricated for long-term irradiation performance testing in the Vallecitos Boiling water Reactor. The design and fabrication histories of this assembly are described and pre-irradiation data on each individual rod are presented. Molybdenum was added to improve the bulk thermal conductivity of the fuel, so that fuel temperatures would remain comparatively low during high-power level operation of the fuel element. The molybdenum was incorporated into the compacts either as fibers or as a thin coating on individual UO2 particles. Fuel pellets were produced from these materials by vacuum hot pressing. The distribution of the molybdenum in both types of cermet fuels appeared favorable to good heat transfer. The fibers were oriented predominantly in the radial planes of the pellet as a result of the uni-directional compaction during the hot-pressing operation. In the pellets made from the coated particles, a continuous network of molybdenum occurred as a result of the coating welding together during the hot-pressing operation. The test assembly contains eight fuel rods; three contain UO2-Mo cermet, three contain the cermet produced from the coated particles, and two are for reference and contain the conventional sintered UO2 pellet fuel. The nominal outside diameter of the fuel rods is 1.308 cm (0.515 inch), and the clad wall thickness if 0.051 cm (0.020 inch). the cladding material is Type-304 stainless steel. The fuel pellets were all centerless ground to achieve a uniform outside diameter and thereby control the pellet-to-clad diametral clearance within a range of 0.076 to 0.102 mm (0.003 to 0.004 inch). Operation of the fuel rods will be at high specific power levels with surface heat fluxes of about 157 W/cm(2) (~500,000 Btu/h-ft(2)). The assembly was designed for a lifetime of 4.1 x 10(20) fission/cc (15,000 MWD/T) exposure.
- Aeroradioactivity Survey and Geology of Puerto Rico (ARMS-I)
- Report containing an aeroradioactivity survey of Puerto Rico made on behalf of the Division of Biology and Medicine, United States Atomic Energy Commission. Topics include the types of bedrock noted in the area as well as their levels of radioactivity.
- The Anadarko Basin (of parts of Oklahoma, Texas, Kansas, and Colorado)
- Abstract: This report is a synthesis of published and unpublished data on the rocks of the Anadarko basin.
- Analog Computer Simulation of a Pulsed Extraction Column
- Report describing "computer techniques used in the simulation and parameter determination, how the data were prepared for inclusion in the computer simulation, (and) methods used in presenting the results" (p. 3-4).
- Analog Models for HNPF Control and Protection Studies
- Abstract: This report, intended as a working document, contains analytic representations and analog models of the Hallam Nuclear Power Facility as used in studies of the Control and Protection Systems.
- Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model
- Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions.
- Analysis of Stresses in Bellows
- Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
- Analysis of the Combustion of Graphite-Uranium Fuels in a Fixed Bed or Moving Bed
- The first step in a proposed processing method for recovery of uranium from graphite-uranium fuels consists of oxidation of the fuel by oxygen to volatilize the carbon. Residue ash from the combustion step can be treated in a variety of ways to recover and purify the uranium. The combustion step may be caried out by contacting the solid fuel in a fixed or moving bed with a stream of oxygen-bearing gas in a tubular or annular reactor. Oxidizing gas may be introduced to the reactor at several points up the reactor and there may be continuous or intermittent addition of fresh fuel and removal of residue ash.
- Analytical Chemistry Division Annual Progress Report, September 30, 1968
- Report containing the ongoing research and development of the Oak Ridge National laboratory's Analytical Chemistry Division.
- Appendices to: An Assessment of Large Nuclear Powered Sea Water Distillation Plants
- Series of five appendices to accompany a report about nuclear-powered seawater distillation plants including case studies, financial assessment, evaluations of water markets in California, and other compiled information and documentation.
- Application of Electron-Bombardment Heating for Boiling Liquid Metals
- Report discussing the "problem of obtaining a curve of the heat flux vs. temperature difference for boiling liquid metals" (p. 3). Contains discussions of a variety of heating techniques, though it focuses on electron-bombardment heating.
- Applied Health Physics Annual Report for 1963
- Report issued by the Oak Ridge National Laboratory discussing work and progress made by the Health and Physics Division during 1963. Instrumentation, personnel monitoring, and laboratory monitoring is presented. This report includes maps, tables, illustrations, and photographs.
- 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.
- Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1964
- Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
- Gas-Cooled Reactor Project Semiannual Progress Report: March 1964
- Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project. From summary: "A study was made of the effect of the energy of extraneous source neutrons on the amplitudes of higher modes in the flux distribution of a subcritical reactor."
- An Assessment of Certain Avenues of Improvement for Nuclear Desalination Technology
- From the questions which have been asked, I gather that I am expected to bring you the news of the latest exciting developments in desalination at the Oak Ridge National Laboratory. However, the agenda for this meeting does not include reports of unfinished investigations; moreover, although there are some new ideas afoot at Oak Ridge, they are aimed toward the very large stations which are somewhat beyond the scope of the more current interests represented here. So instead of presenting new developments, I would like today to talk about where to look for them--to give you some purely analytical considerations that assess the incentives we have to seed certain improvements in this or that portion of the equipment in a dual-purpose station.
- Autoradiographic Study on the Origin and Fate of Small Lymphoid Cells in the Dog Bone Marrow: Effect of Femoral Artery Clamping During in Vivo Availability of Thymidine-H
- Mammalian bone marrow contains a considerable number of small lymphoid cells (small lymphocytes and small lymphocyte-like cells). The total number of these cells (50,000 to 500,000 per mm3) depends on species, age and other factors. The origin, function and fate of these cells remain obscure in many respects. In particular, it has not been shown beyond doubt, if and to what extent small lymphoid cells enter the bone marrow via the blood stream or if their origin is in part or entirely within the bone marrow. In addition it has not been clearly shown whether or not these cells may function as multipotential hemopoietic stem cells. Results obtained from experiments with irradiated parabiotic animals and animals given regional fractioned doses of X-irradiation, and transplantation of leukocytes from peripheral blood into lethally irradiated recipients afford indirect evidence that peripheral blood of mice and rats may contain stem cells capable of DNA synthesis and division.
- The Bactericidal Activity of the Serum of Healthy Beagles
- Report describing the methods and results of studies conducted on the bactericidal activity of serum collected from beagles, including tables.
- Barrier Attenuation of Air-Scattered Gamma Radiation
- Report of a study that "was conducted to determine the attenuation provided by vertical and horizontal barriers exposed only to skyshine radiation from cobalt-60 and cesium-137 sources. Materials of steel, aluminum, concrete, and wood were used as barriers" (p. 5).
- Bending of Circular Plates Under A Uniform Load on a Concentric Circle
- 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.
- Bending of Circular Plates Under A Variable Symmetrical Load
- 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.
- Beneficiation Studies of the Oregon Coastal Dune Sands for Use as Glass Sand
- Report issued by the Bureau of Mines on the coastal sands and their potential for being used as glass sand. Samples were tested, and properties of the sands are presented. This report includes tables, maps, and photographs.
- Beta-Gamma Dose Rates from U232 in U233
- This report defines in detail the source of the dose rate of U233 and describes a method by which they may be predicted.
- Bibliography of the Literature on Dropwise Condensation 1930-64
- Report presenting a comprehensive bibliography on dropwise condensation that has been created as part of a study on the dropwise condensation characteristics of inorganic hydrophobic systems.
- Biological Effects of Thermal Neutrons and the B10 (n,c) Li7 Reaction
- Boron-10 has a high thermal neutron capture cross section (3880 barns). Following neutron capture, the subsequent nuclear disintegration produces an alpha particle and a lithium-7 nucleus with the release of an average of 2.34 MeV for the particle irradiation, and in 93% of the reactions there is also the emission of an 0.48 MeV gamma ray: [equation not transcribed]. The kinetic energy is divided between the lithium-7 nucleus and the alpha particle giving the equal and opposite momentums with a range in tissue of about 8-14μ or approximately 1 cell diameter (1). This fact and the reported favorable partition of boron between tumor and the normal brain suggested a possible therapeutic usefulness which has been investigated clinically. The object of our study is to document the biological effects of the B10 (n,α) Li7 reaction on the brain of dogs injected with boron-10 30 minutes prior to irradiation with thermal neutrons. For this, we felt it desirable to estimate a dose for the boron-10 reaction which if exceeded, produces destruction of normal tissue. This dose could then be a reference dose to be utilized as a maximal limit for the irradiation of normal tissue. We have assured that the largest fluence of thermal neutrons that permits a healing radioepidermitis in pigs injected with 35 mg/kg of boron-10, 30 minutes prior to irradiation would be suitable first approximation.
- Biology Division Semi-Annual Progress Report for Period Ending February 15, 1964
- Technical report on the activities of the Oak Ridge National Laboratory Biology Division for the report period including a list of 346 publication and lectures and 205 short articles by members of the division on their research and activities.
- Blueprints of an Automatic Zonal Scraper and Sample Collector for Radioassay of Thin-Layer Chromatograms
- From introduction: Zonal radioscanning of thin-layer chromatoplates using a specially designed manual scraper capable of removing 1, 2, or 5 mm zones has been described.
- Boiling Depressurization Transients
- Abstract: An analytical and experimental effort toward a better understanding of the mechanisms involved in nuclear power reactor loss-of-pressure accidents is presented.
- Boiling Studies for Sodium Reactor Safety: Part 2, Pool Boiling and Initial Force Convection Tests and Analyses
- Abstract: In fulfillment of the general objective of developing information on two-phase flow required in the safety evaluation of sodium cooled reactors, pool and forced-convection boiling of sodium were studied both experimentally and analytically.
- Bubble Chamber Vacuum System
- The vacuum system for the bubble chamber must evacuate rapidly a volume of approximately 500 cubic feet and eliminate the outgassing of a surface area of approximately 50,000 square inches. The backstreaming of oil from the diffusion pump must be kept to an absolute minimum to prevent oil films forming on the window. The vacuum system must also provide the protection against liquid nitrogen and hydrogen/leaks to prevent pressure buildup.
- By-Products from Saline Water Conversion Plants: A Feasibility Study
- Report issued by the Office of Saline Water over studies conducted on by-products of saline water conversion plants. As stated in the introduction, "the objective of the survey has been to determine whether recovery of salable by-products from minerals present in saline waters offers a practical route to reducing the overall cost of converting these saline feeds to fresh water, and to delineate areas for further research and development on recovery processes" (p. 1). This report includes tables, and illustrations.
- Calculation of Explosion-Produced Craters
- In this study, a physical-numerical model is used to investigate processes important for cratering, or excavation, physics for high-explosive sources in desert alluvium. High explosives do not vaporize much of the geological environment surrounding the initial cavity containing the explosive. Thus, a relatively simple, and in some cases a well-known, equation of state exists for the high-explosive cavity gas for pressure greater than 1 atmosphere. However, nuclear explosives are known to vaporize a great deal of surrounding geological environment during the early part of cavity life history. This vaporized material is believed to condense late in the life history of the cavity, and prior to vent of the cavity gas to the atmosphere, such that the latent heat of condensation plays an important role in nuclear excavation. So far, no numerical-physical models of the response of a geologic environment to a nuclear explosive includes the effect of condensation on the hydrodynamics of late times. Thus, the calculation of the cavity pressure at late times including the effect of condensation is one of the current unsolved problems in the calculation of a crater formed by nuclear explosives. This study, then, develops a predictive, numerical-physical model for H.E. sources of the cavity life history, the earth's free-surface motion, and the formation of the lip (by up-thrust) up to the time of the vent of the cavity gas to the atmosphere.
- Calculation of Sunrise and Sunset Times at Ionospheric Heights Along a Great Circle Path
- Formulas, computer program, and illustrations for a great circle path at ionospheric heights.
- Calculation Of The Shock Wave From An Underground Nuclear Explosion In Granite
- In any underground nuclear explosion, the shock front that propagates from the shot point carries with it energy from the explosion, and distributes this energy by doing work on the surrounding material. In the process, the material undergoes changes in both its physical and mechanical states. If enough energy is deposited in the material, it will vaporize or melt thus changing its physical state, or cause it to crush or crack. During the past few years, special computer codes have been developed for predicting the close-in phenomena of underground nuclear explosions using the laws of physics, and the knowledge of the properties of the materials in which the detonations occur. As a consequence, a better understanding of experimental observations and measurements has evolved.
- Case Reports -- 1962. Cytomegalic Inclusion Disease of the Submaxillary Gland. Etiologic Factors in Obstruction of the Superior Vena Cava
- The case history and autopsy finding are presented for a case of cytomegalic inclusion disease in the salivary glad of a 5-month-old male infant. The relation of viruses to cytomegalic inclusion disease is discussed briefly. The etiologic factors in obstruction of the superior vena cava in a group of cases that came to necropsy are discussed.
- Chamber Geometry in Multi-Stage Flash Evaporators
- Report regarding "the importance of various parameters on the length of a typical stage in a multi-stage sea water flash evaporator" (p. 1). Parameter values were examined to determine their influence on chamber length.