Technical Report Archive & Image Library (TRAIL) - 233 Matching Results
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- Salt Bath Heat Transfer Rates for Uranium Plate
- Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.
- The Influence of Design and Production Parameters on Fabrication Costs of Nuclear Reactor Fuel Elements
- The objectives for this study were to determine fuel fabrication and assembly costs in a large nuclear power industry for several reactors, fuel rod sizes, and fuel materials.
- Calculation of the Doppler Coefficient Plutonium-Oxide-Fueled Fast Reactors
- Report issued by the APDA over studies conducted on Doppler coefficient fast reactors. Calculations, methods, and results of the studies are presented. This report includes tables, and illustrations.
- Final Report: Investigation of Boiling Flow Regimes and Critical Heat Flux
- From abstract: A program to investigate the mechanism of the critical heat flux condition from the standpoint of flow regimes has been initiated at Dynatech for the AEC. This report covers the work done on this investigation in the first year.
- Magnetic Properties of Insulators : Quarterly Report No. 7 Covering the Period from August 16, 1962 to November 15, 1962
- The following quarterly progress report covers the period of August 15 to November 15, 1962. It summarizes three activities of the group. The first part is the optical study of the absorption band associated with the F-center in RbCl. The second part discusses some elementary calculations of the spin-lattice relaxation times, the primary purpose of this step is to indicate the nature of the theoretical problem faced and show the large gap between the value calculated theoretically and measured experimentally. The last section includes more data on the shape and recovery of the hole in a EPR band associated with the F-center in KCl.
- Magnetic Properties of Insulators : Quarterly Report No. 8 Covering the Period from November 16, 1962 to February 15, 1963
- The following quarterly progress report covers the period from November 16, 1962 to February 15, 1963. This report summarizes three activities that study the ratio of the maximum absorption of the K band to the maximum absorption of the F band has been made in additively colored and [gamma]-irradiated rubidium chloride.
- Manual of Radiation Protection Standards
- "The following is an alphabetical listing of terms and units in common usage at Hanford Atomic Products Operation. Other terms and definitions may be added as the need becomes apparent or as revisions or additional terms are issued by the NCRP and ICRP."
- Investigations in Automated Activation Analysis
- Introduction: The Texas A. and M. Activation Analysis Research Laboratory has been studying the basic technology of activation analysis and its applications since 1958, under the spondorship of the Division of Isotopes Development, U. S. Atomic Energy Commission, and more recently, the National Aeronautics and Space Administration. The information presented in this report summarizes the progress which has been made in these efforts during the period from May 1, 1961, to October 31, 1962.
- Radiation Safety and Control Training Manual
- Introduction: The Laboratory follows the recommendations of the National Committee on Radiation Protection concerning permissible exposure limits for those working with radiation. A system of controls and regulations has been established which should ensure that no person at the Laboratory will receive more than the permissible exposure. This manual is intended to provide the minimum background necessary for intelligent cooperation with the regulations.
- Uranium in Peru
- Introduction: From the inception of the effort to utilize atomic energy Perú has been of interest as a possible source of radioactive raw materials because of its great variety and abundance of metals. Because of this and a desire at that time to develop additional supplies of uranium, a cooperative program to search for uranium deposits was initiated in 1953 by the Junta and the USAEC.
- Uranium in the Southern United States
- From introduction: The purpose of this study was to compile information on and systematically assess uranium and other radioactive occurrences in the region.
- The High Intensity Food Irradiator: Report 17
- From introduction: A thorough investigation, both experimental and theoretical was carried out on plaque type radiators. Five phases of the work are reported: preliminary design analysis, experimental measurements, computational program and analytical studies, followed by a general discussion of source design principles. The results are summarized in graphs and formulae which may be applied to other design requirements.
- Evaluation of Irradiated OMRE Fuel Elements First Core Loading
- Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.
- OMR Degasifier Loop Experiment
- Abstract: A loop has been constructed to study the removal of water and highly volatile materials from Organic Moderated Reactor coolant by vacuum degasification. An analysis of the process was made to determine the most important parameters for study during the experimental program.
- OMRE Fuel Plate Surface Temperature Measurement
- Abstract: Accurate measurement of OMRE fuel-element surface temperatures is important for evaluation of the performance of organic compound as moderator and coolant materials in nuclear reactors; a mixture of polyphenyls has been used in reactor operation to-date.
- Plutonium: Enriched OMR Cores
- Abstract: The influence of plutonium on the nuclear characteristics of organic moderated cores is studied.
- Engineering Evaluation of a Mixed Alloy Fuel Element Irradiated at Elevated Temperatures in the SRE
- Abstract: A fuel material evaluation was made by destructively examining a full-scale experimental fuel element, irradiated in the SRE to a maximum of 850 Mwd/MTU.
- Current Beryllium Literature : A Selected Bibliography, August 1959 - December 1969
- "This bibliography lists selected books, articles, and unclassified reports which have appeared in the following abstracts and indexes between August 1959 and December 1960."
- OMRE Fuel Removal and Shipping Equipment
- Abstract: A portable assembly for handling and shipping OMRE fuel elements is described and details of its operation are given. Problems of heat transfer and radiation shielding are discussed, and detailed analysis are presented.
- Final Safeguards Summary Report for the Piqua Nuclear Power Facility
- Summary: This report contains a description of the final design of the Piqua Nuclear Power Facility (PNPF); an outline of the test and operating procedures, and the organization and responsibilities; and a summary of the hazards and safeguards analyses that have been conducted to evaluate the safety of the facility operations.
- Thermal Cycling and Leakage Tests of 12-inch Valves for Sodium Service
- Abstract: Tests were performed to determine the effect of thermal cycling on the across-the-seat leakage characteristics of commercially available valves considered for use in the sodium coolant system of the Hallam Nuclear Power Facility.
- 300,000-KWE SGR Nuclear Power Plant of Current Technology
- Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.
- UC Fuel Element Design and Fabrication
- Abstract: Uranium monocarbide shows considerable potential for use as a fuel in high temperature, high power density, nuclear power reactors. As Atomics International is proposing its use in sodium graphite type reactors, it was necessary to develop a process for fabricaing sodium bonded uranium carbide fuel elements.
- Study of SCTI Control System
- Introduction: This report has been prepared to document the extensive analytical work required to design the control system for the Sodium Components Test Installation (SCTI), constructed for the Atomic Energy Commission at the Atomics International field laboratory.
- Irradiation Swelling, Phase Reversion, and Intergranular Cracking of U-10 wt % Mo Fuel Alloy
- Abstract: A fuel development program has been conducted, to investigate the behavior of U-10 wt% Mo alloy at the fission rates and temperatures anticipated in Core I of the Hallam Nuclear Power Facility.
- Refabrication and Encapsulation of Highly Irradiated Uranium Dioxide
- Abstract: One hundred gram quantities of uranium dioxide, irradiated to burnup as great as 21,000 Mwd/MTU and previously reprocessed by AIROX (Atomics International Reduction Oxidation), were refabricated into high density pellets and encapsulated for re-irradiation.
- The NAA 47 U - 10 Mo Fuel Irradiation Program for HNPF Core 1
- Abstract: Atomics International conducted a fuel irradiation program to investigate and define the behavior of U-10 Mo fuel at the temperatures and fission rates anticipated in Hallam Nuclear Power Facility (HNPF) Core I.
- Development of High-Temperature Electrical Ground Test Heaters for the SNAP 10A Program
- Introduction: The development and qualification of the system acceptance test heaters and the reactor simulator heater are described in this progress report.
- Performance of Cesium Thermionic Diodes Operated in Series-Parallel Circuits
- Introduction: The purpose of this experiment is to determine the loss of electrical power output due to operating many unequally-heated cesium diodes, connected in series and parallel circuits.
- Final Design of Sodium-Heated, Modular, Steam Generators for the SCTI
- Abstract: The following report covers the final design of the modular steam generators.
- Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 2, March-August 1963
- From summary: The full 140 element loading of the core was completed on October 10, 1962. At this point, critical operation was begun for operator training and post-critical testing purposes.
- Material Bucklings of Critical and Subcritical Uranium Carbide Fueled Graphite Assemblies: Part 1, Experiment
- Introduction: A series of critical and subcritical experiments have been carried out as part of the Advanced Sodium Graphite Reactor (ASGR) Critical Experiments program to provide physics information which would be directly applicable to the AGSR concept.
- 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.
- Multi-Channel Boiling Stability for Sodium Graphite Reactors
- Abstract: This report presents an analysis of coolant boiling in sodium graphite reactors.
- Thermal Stress Testing of Beryllium Oxide Moderator Shapes
- Abstract: Perforated BeO plates were thermal shock tested to evaluate the effect of: (1) localized temperature variations adjacent to the perforations, and (2) radial gradients across the entire plate.
- Uranium Carbide Transient Heating Experiments - Phase 1
- Abstract: Two in-pile capsules containing mock-up uranium carbide fuel rods were subjected to a total of five neutron bursts in the TREAT facility with initial reactor periods ranging from 0.26 to 0.10 sec.
- Thermal Conductivity of Silicon and Iron From 300 to 1400°K
- From Abstract : "The thermal diffusivities of pure silicon and of Armco iron have been measures from 300 to 1400°K. The specific heats of the same materials have been measured over the same temperature range."
- Fabrication of Beryllium: a Bibliography
- This bibliography contains 147 references on the fabrication of beryllium. References are also given on the brazing, casting, cladding, extrusion and welding of beryllium and some beryllium-rich alloys. The bibliography is limited to the period 1950 - 1959. references are arranged alphabetically by title, with author and subject indexes provided. Sources used in compiling this bibliography are: Abstracts of Classified Reports, ASM Review of Metal Literature, Bibliographies of Interest to the Atomic Energy Program - Classified and Unclassified Versions, Engineering Index, Nuclear Science Abstracts, TISE, List of Bibliographies in the Atomic Energy Program.
- A Proposal for the Mc2 Isochronous Cyclotron: A General Purpose High-Intensity 810-MeV Proton Accelerator
- Abstract: "The Oak Ridge National Laboratory proposes to build an isochronous eight-sector proton cyclotron to provide an extracted beam in excess of 100 A at 810 MeV. The primary proton beam and the secondary meson and neutron beams will be used to investigate nuclear structure, and the interactions between elementary particles. Biomedical and Space-oriented research programs are also planned. Shielded research areas and an extensive beam transport and analysis system are provided. Theoretical and experimental studies have shown that the Mc2 Cyclotron is a practical concept; high extraction efficiencies can be obtained, and the residual radiation problems are manageable. The project would require less than seven years to complete, and would cost about $43,000,000."
- A Class of Casualty Functions with Special Application to Circular Targets
- Abstract: "Methods developed by [the Systems Evaluation Department] to analyze circular targets are extended to handle a particular family of casualty curves."
- SNAP Programs : M-1 Monte Carlo Radioisotope Shielding Code : Final Report
- From foreword: This final report summarizes the results of a project to develop a machine calculation code program using the Monte Carlo technique to compute radiation flux or dose rates from radioisotope sources.
- Estimating Safety Probabilities from Fallout Forecasts for Nevada Test Site
- Abstract: "Available data on wind persistence and wind forecasting capability have been applied in estimating the probability of a fallout pattern shifting from an uninhabited safe sector into a populated region. Safety probability is computed from win variability, forecasting accuracy, initial height and particle size of radioactivity landing at a point in the predicted fallout pattern, predicted wind speed, length of forecast period, and safe-sector angular width."
- A Study of Nevada Test Site Wind Variability
- Abstract: "Wind observations collected at Yucca Flat since 1951 are analyzed for timewise variability. Variability functions of altitude, season, wind speed, and vector wind are described. Derived variability parameters are incorporated into calculations of fallout safety probability for NTS operations."
- Mechanical Properties of Zircaloy-2
- Abstract: The mechanical and physical properties of Zircaloy-2 were determined as a function of five test variables: temperature, grain size, direction to rolling, hydrogen content, and the presence or absence of a notch.
- Radioactivity Transport in Water: the Dispersion of Radionuclides in Open Channel Flow
- From introduction: It is the purpose of this study to present field measurements of dispersion in a river and a canal, whose characteristics are unlike streams in which similar work has been done. The Colorado River and the Pierce Canal were selected for testing.
- Experimental Gas Cooled Reactor, Final Hazards Summary Report: Volume 2, Plant Operation
- From introduction: The information provided in Volume II describes programs, requirements, and procedures established by the Operator to minimize the probability of equipment failure, actions taken during any emergency to minimize radiation exposure dose to the general public and to plant personnel, and actions taken following a hazardous condition to prevent its recurrence.
- Design and Properties of a Neon Filled Spark Chamber in a Magnetic Field
- Introduction: Recently a new type of charged particle detector, the so-called spark chamber, has been developed. The detector has certain advantages in high energy physics over bubble chambers aside from its much lower cost.
- Boiling Nuclear Superheater (BONUS) Power Station : Final Hazards Summary Report
- Summary report of final hazards for the Boiling Nuclear Superheater (BONUS) Power Station with illustrations.
- Development of a Gas Injector System for Homogeneously Labeling Gas Storage Reservoirs
- "The laboratory experiments and field testing which were carried out in the development of a homogeneous gas labeling device are described. Detailed drawings of the injector and its most critical components are included. Recommendations are made for a production model of the device along with estimated costs of construction."
- Flux Control for Irradiation Experiments
- Abstract: This report reviews various means which have been used to control experimental conditions in irradiation experiments, and presents the concept of local flux control.