1,958 Matching Results

Search Results

Results: 1 - 24 next
open access

Aircraft Reactor Test Removal and Disassembly

Description: Report documenting the dissection of a reactor called the Aircraft Reactor Test (ART). Includes the removal of the reactor from its test cell, component removal, and plans for a for a disassembly building facility.
Date: 1960?
Creator: Abbatiello, A. A. & McQuilkin, F. R.
Partner: UNT Libraries Government Documents Department
open access

Isotopic Analysis of Boron as Trimethyl Borate

Description: Boron-impregnated polyethylene tape was irradiated in the Engineering Test Reactor Critical Facility to study the effect of boron as a burnable poison in reactor fuel. Isotopic analysis of the boron was performed with a conventional CEC Model 21-103 mass spectrometer. The tape was distilled off and the residual boron was converted to trimethyl borate. The reaction mixture was analyzed without separation. Good precision was obtained with samples containing less than 0.5 mg. boron. Features of th… more
Date: January 28, 1960
Creator: Abernathey, R. M.
Partner: UNT Libraries Government Documents Department
open access

Temperature-Induced Stresses in Solids of Elementary Shape

Description: Report discussing how solids subjected to non-uniform temperature change develop internal stresses determined by, (1) the temperature distribution within the solid, and (2) certain physical constants of the material. For two varieties of heating, the equations determining stress have been put in convenient form for practical use, and tables of certain temperature functions show how to determine stresses in a slab, in a cylinder, or in a sphere subjected to either of two modes of heating. The te… more
Date: June 21, 1960
Creator: Adams, Leason H. & Waxler, Roy M.
Partner: UNT Libraries Government Documents Department
open access

Development test IP-342-AG increase of bulk outlet water temperature 105-DR

Description: The objective of this test is to determine the DR-Reactor effluent systems characteristics under 95 degrees Celsius bulk temperature operation. This proposed bulk temperature increase from 93.5 to 95 degrees represents a 33% decrease in the bulk temperature suppression below the boiling point. A major aim of this test will be to evaluate the degree of increased maintenance at this higher temperature operation. The basis and justification, test preparation and instrumentation, procedure, costs, … more
Date: July 14, 1960
Creator: Adams, O. E. Jr.; Hedges, J. W. & Jones, S. S.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Activated Charcoal Fission Gas Adsorbers Designed for the GC-ORR Loop Experiment No. 1

Description: The activated charcoal traps designed for the Gas-Cooled Oak Ridge Research Reactor Loop Experiment No. 1 are evaluated for room temperature operation involving the decontamination and atmospheric disposal of helium coolant gas contaminated by experiment failure. The maximum quantity of fission products expected to be released was calculated and the resulting hazard was examined on the basis of probable radiation doses to laboratory personnel resulting from exposure to the gas cloud.
Date: January 14, 1960
Creator: Adams, R. E. & Browning, W. E.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Experiment Off-gas System for the EGCR-LITR Capsule Experiment

Description: A proposed modification to the experiment off-gas system for the EGCR-LITR Capsule Experiment is evaluated by comparing the atmospheric radiation doses to laboratory personnel that could result in the event of an experiment failure while utilizing the present off-gas system to those doses that would result if various modifications to the existing system were effected. The modifications considered include the addition of an iodine vapor adsorber and a krypton-xenon adsorber. The addition of an i… more
Date: September 2, 1960
Creator: Adams, R. E. & Browning, W. E.
Partner: UNT Libraries Government Documents Department
open access

Removal of Radioiodine from Air-Steam Mixtures

Description: A short-term study was made to investigate the removal of radioiodine vapor from air-steam mixtures as could occur immediately following a nuclear incident in a pressurized water reactor. Activated charcoal traps, designed to simulate a small section of a commercial charcoal canister, were tested at gas velocities of 23.9 to 74.9 ft/min over the temperature range of 75 to 118°C. The iodine removal efficiency was found to range from 99.80 to 99.4% with an average of 99.9%. One test performed at … more
Date: November 14, 1960
Creator: Adams, R. E. & Browning, W. E. Jr.
Partner: UNT Libraries Government Documents Department
open access

Removal of Radioiodine From Air Streams by Activated Charcoal

Description: Contamination of the atmosphere by radioactive isotopes of iodine constitutes a serious biological hazard and, for this reason, provisions should be made at reactors to prevent such releases in the event of an accident. The efficiency of activated charcoal for adsorption of iodine vapor from air streams was measured by using a radioactive tracer method, and efficiencies of 99.6 to 99.999+% were obtained for various conditions. Comparative tests were run with silver-plated copper ribbon. A crite… more
Date: April 1, 1960
Creator: Adams, R. E. & Browning, W. E., Jr.
Partner: UNT Libraries Government Documents Department
open access

Project Cowboy : Final Report : Seismic Decoupling for Explosions in Spherical Cavities

Description: A series paired explosions in a salt mine near Winnfield, Louisiana, has been conducted to test a theory by A.L. Latter concerning seismic decoupling by underground cavities. The theory predicted a decoupling of 132 Free-field and surface measurements from an explosion in either a 6-ft- or a 15-ft-radius spherical cavity were compared with similar measurements from a completely tamped explosion of equal size. Shot sizes were from 20 pounds up to a ton. Surface measurements were made out to 100 … more
Date: August 1960
Creator: Adams, William M. & Allen, DeWitt C.
Partner: UNT Libraries Government Documents Department
open access

Seismic Decoupling for Explosions in Spherical Cavities

Description: Abstract. A series of paired explosions in a salt mine near Winnfield, Louisiana, has been conducted to test a theory by Dr. A. L. Latter concerning seismic decoupling by underground cavities. The theory predicted a decoupling of about 100. Free-field and surface measurements from an explosion in either a 6-ft- or a 15-ft-radius spherical cavity were compared with similar measurements from a completely tamped explosion. Shot sixes were from a 10 lb up to a few tons. Surface measurements were ma… more
Date: September 30, 1960
Creator: Adams, William M. & Carder, Dean S.
Partner: UNT Libraries Government Documents Department
open access

Final Report on the Pinot Experiment

Description: The Pinot Project was designed to provide some indication of the extent to which gases from a confined underground explosion in oil shale would migrate parallel to the bedding planes. At 0800 on Aug. 2, 1960, 946 lb of nitromethane was fired in shot hole No. 1. There was no visible damage to the mine adit or to any structure associated with cation of the extent to which gases from a confined underground explosion in oil shale would migrate parallel to the bedding planes. At 0800 on Aug. 2, 1960… more
Date: December 27, 1960
Creator: Adelman, F. L.; Bacigalupi, C. M. & Momyer, F. F.
Partner: UNT Libraries Government Documents Department
open access

Theoretical Feedback Analysis in Boiling Water Reactors

Description: The dynamic behavior of boiling-water reactors for small perturbations was investigated in a systematic way. General expressions for the transfer functions associated with the individual feedback mechanisms were obtained for an arbitrary flux distribution, weighting function, and steam velocity distribution. Specific forms were derived in the case of a first power flux weighting, a uniform steam velocity distribution, and a sinusoidal flux distribution with an adjustable wave length. These form… more
Date: October 1, 1960
Creator: Akcasu, A. Ziya
Partner: UNT Libraries Government Documents Department
open access

The Diffusion of Hydrogen in Zirconium Hydride

Description: The diffusion of hydrogen in zirconium hydride was studied using permeation techniques. The rate of permeation of hydrogen through zirconium hydride disks was measured for small concentration gradients. Data were obtained at 61 to 65 at.% hydrogen and 500 to 750 ction prod- C. The diffusion coefficients were determined by the time-lag method. Ho variation of the diffusion coefficients with hydrogen concentration was observed. The diffusion coefficients can be expressed by D (cm/sup 2/ per sec) … more
Date: March 1, 1960
Creator: Albrecht, W. M. & Goode, W. D., Jr.
Partner: UNT Libraries Government Documents Department
open access

The Decay of Neptunium-238

Description: >A study was made of the energy levels of Pu/sup 238/ which are populated by Np/sup 238/ beta decay, by an examination of the Np/sup 238/ conversion electron spectrum in high-resolution beta spectrographs. The general features of the level scheme as previously given were unchanged but several new transitions were observed, with energies of 119.8, 871, 943, 989, and 1034 kev. Two new levels are postulated at 915 and 1034 kev which accommodate all but the 943-kev transition. A possible assignment… more
Date: December 1, 1960
Creator: Albridge, R. G. & Hollander, J. M.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Buried Conduits as Personnel Shelters

Description: Supersedes ITR-1421. Twelve large-diameter buried conduit sections of various shapes were tested in the 60- to l49-psi overpressure region of Burst Priscilla to make an empirical determination of the degree of personnel protection afforded by commercially available steel and concrete conduits at depths of burial of 5, 7.5, and 10 feet below grade. Essentially, it was desired to assure that Repartment of Defense Class I, 100psi and comparable radiations, and Class II, 50-psi and comparable radia… more
Date: July 14, 1960
Creator: Albright, G. H.; LeDoux, J. C. & Mitchell, R. A.
Partner: UNT Libraries Government Documents Department
open access

Control and Dynamics Performance of a Sodium Cooled Reactor Power System

Description: Introduction: Objectives and Method of Approach. High plant efficiencies can be realized without excessively high core temperatures and high coolant pressures by the use of liquid metal coolant. In an attempt to prove the feasibility of liquid sodium as a reactor coolant ALCO Products, Inc., under sponsorship of the Atomic Energy Commission, is undertaking a design study of three vital system components: the intermediate exchanger, the boiler, and the superheater. Since, in the past programs,… more
Date: 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
open access

Intermediate Heat Exchanger and Steam Generator Final Design. Volume 1. Thermal & Mechanical Design

Description: This technical report represents the final design for a sodium to sodium intermediate heat exchanger and a sodium to water steam generator. The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming fro the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to the steam generator. Because of radioactivity the unit will be encl… more
Date: September 30, 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
open access

Intermediate Heat Exchanger and Steam Generator Final Design. Volume 2. Chemical & Stress Analysis

Description: Introduction: This volume deals principally with the chemical analysis and the stress analysis for a sodium to sodium intermediate heat exchanger and a sodium to water steam generator. The work presented is an extension and modification of the analysis presented in the preliminary design report. The chemical analysis covers the sodium cover gas system and the effects of sodium-water reactions in the event of a leak in the steam generator. Considerable design work was done in an effort to mainta… more
Date: September 30, 1960
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
Back to Top of Screen