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Accelerator Beam Pulsing System With Extremely Wide Range of Pulse Lengths and Pulse Repetition Rates
The following document describes the usage and results of sending pulsed beams of electrically charged particles with electrically wide range of pulse lengths and pulse repetition rates.
Date:
June 28, 1960
Creator:
Aaland, Kristian
System:
The UNT Digital Library
Aircraft Reactor Test Removal and Disassembly
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.
System:
The UNT Digital Library
Isotopic Analysis of Boron as Trimethyl Borate
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 the mass spectrum of trimethyl borate are discussed. Other applications of the method are suggested. (auth)
Date:
January 28, 1960
Creator:
Abernathey, R. M.
System:
The UNT Digital Library
Abilene Fire Department Annual Report: 1960
Annual report of the Abilene Fire Department describing the organization and administration, with updates on goals, activities, and accomplishments during fiscal year 1960.
Date:
1960
Creator:
Abilene (Tex.). Fire Department.
System:
The Portal to Texas History
Temperature-Induced Stresses in Solids of Elementary Shape
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 temperature-distribution tables independently provide a useful means for the ready estimation of temperature gradients.
Date:
June 21, 1960
Creator:
Adams, Leason H. & Waxler, Roy M.
System:
The UNT Digital Library
Development test IP-342-AG increase of bulk outlet water temperature 105-DR
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, outage time, hazards, standards, and responsibilities are discussed in this document.
Date:
July 14, 1960
Creator:
Adams, O. E. Jr.; Hedges, J. W. & Jones, S. S.
System:
The UNT Digital Library
Evaluation of Experiment Off-gas System for the EGCR-LITR Capsule Experiment
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 iodine vapor adsorber to the off-gas system, which presently includes an absolute filter, reduces the atmospheric dose to the thyroid from 510 mr to 1.4mr. The total body dose is also reduced from 2.2 to 1.3 mr. The total body dose can be further reduced to 0.7 mr if a large krypton-xenon adsorber is included. Basd upon these calculated atmospheric radiation doses it is concluded that the addition of an activated charcoal iodine vapor adsorber will reduce the atmospheric hazard to an acceptable level.
Date:
September 2, 1960
Creator:
Adams, R. E. & Browning, W. E.
System:
The UNT Digital Library
Removal of Radioiodine from Air-Steam Mixtures
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 a temperature of 105°C and with gas velocity of 290 ft/min indicated that the iodine removal efficiency was reduced to 99.54%. Activated charcoal exhibits a high efficiency for iodine vapor removal under these test conditions and appears suitable for application in the decontamination of air-steam mixtures.
Date:
November 14, 1960
Creator:
Adams, R. E. & Browning, W. E. Jr.
System:
The UNT Digital Library
Removal of Radioiodine From Air Streams by Activated Charcoal
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 criterion for selecting an iodine removal material was developed based on efficiency and resistance to air flow. The iodine vapor adsorption efficiency of a commercial charcoal filter was measured. Various materials were considered for possible application in the emergency exhaust system of the building housing the 5-Mw swimming pool reactor at the Puerto Rico Nuclear Center. Based upon its high adsorption efficiency and retention properties, it is proposed that activated charcoal be utllized for iodine vapor adsorption. (auth)
Date:
April 1, 1960
Creator:
Adams, R. E. & Browning, W. E., Jr.
System:
The UNT Digital Library
Comments on meeting with the seismic Working Group on Explosions on 15 June 1960 in Washington [with the Seismic Working Group on Explosions]
None
Date:
June 29, 1960
Creator:
Adams, W. M.
System:
The UNT Digital Library
Project Cowboy : Final Report : Seismic Decoupling for Explosions in Spherical Cavities
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 km and covered the frequency range from 0.05 to 100 cps. The experiments confirmed that decoupling does occur. For explosions that produce an average cavity pressure up to one-fifth and possible more of the lithostatic overburden pressure, seismic waves were decoupled by the 100, i.e., two order of magnitude. Even for explosions producing an average cavity pressure of six times the lithostatic overburden pressure, the seismic waves were decoupled by 20 -- more than a full order of magnitude. Minimum decoupling factors as a function of frequency are presented.
Date:
August 1960
Creator:
Adams, William M. & Allen, DeWitt C.
System:
The UNT Digital Library
Seismic Decoupling for Explosions in Spherical Cavities
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 made out to 100 km and covered the frequency range from 0.05 to 100 cpa. The experiment confirmed that decoupling does occur. The actual decoupling factor as a function of frequency is presented and compared with the Latter theory.
Date:
September 30, 1960
Creator:
Adams, William M. & Carder, Dean S.
System:
The UNT Digital Library
Final Report on the Pinot Experiment
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, 946 lb of nitromethane was fired in shot hole No. 1. There was no visible damage to the mine adit or to any stnucture associated with the workings. Gas samples collected from sampling holes near the shot hole were analyzed for Kr/sup 85/, which had been included with the nitromethane as a tracer. It appeared that the Kr/sup 85/ concentration in the samples out to 50 ft was more or less independent of space and time between +2 and +50 hr. Relativsly little Kr/sup 85/ was detected at 125 ft and none beyond. About (20 plus or minus 10)% of the Kr/sup 85/ escaped into ths adit. The results of …
Date:
December 27, 1960
Creator:
Adelman, F. L.; Bacigalupi, C. M. & Momyer, F. F.
System:
The UNT Digital Library
Technical Feasibility and Economic Potential of the Variable Moderator Reactor: Final Report
Foreword: This report covering the technical feasibility and economic potential of the VMR completes the requirements of Phases II and III of the program outlined in American-Standard Proposal No. P-470A.
Date:
December 15, 1960
Creator:
Advanced Technology Laboratories
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1959
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
February 15, 1960
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
July 31, 1960
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
July 31, 1960
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
[Final Grade Report for Douglas M. Herrera, Fall 1960, Agricultural and Mechanical College of Texas]
Final Grade Report for Douglas M. Herrera for the Fall 1960 semester at the Agricultural and Mechanical College of Texas (Texas A. & M.). It is addressed to John J. Herrera in Houston, Texas.
Date:
1960
Creator:
Agricultural and Mechanical College of Texas
System:
The Portal to Texas History
Theoretical Feedback Analysis in Boiling Water Reactors
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 forms were simplified and single time-constant transfer functions were obtained. The error involved in the lumped time-constant approximation was shown to be as large as 4 db in amplitude in certain feedback mechanisms. Theoretical results were applied to the experimental power-void transfer function obtained at Ramo-Wooldridge Research Laboratory, and to the EBWR transfer function. In the former case, the agreement was found to be reasonably good, but yet more systematic experimental data were needed to reach a definite conclusion as to the validity of the proposed model, which assumes a time lag associated with steam formation and a steam perturbation speed greater than the steady-state steam velocity. In the second application, the agreement between the experimental and calculated reactor responses was proved to be better than 5 db in amplitude and …
Date:
October 1, 1960
Creator:
Akcasu, A. Ziya
System:
The UNT Digital Library
The Diffusion of Hydrogen in Zirconium Hydride
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) = 599 exp (-34,800/RT). (auth)
Date:
March 1, 1960
Creator:
Albrecht, W. M. & Goode, W. D., Jr.
System:
The UNT Digital Library
The Decay of Neptunium-238
>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 of the 943-kev transition to the (0+.0) state of the beta vibrational band is discussed. In addition, the weak 885-kev transition from the 2+ state of the gamma -vibrational band to the 4+ state of the ground band was seen and its relative intensity determined. Comparisons were made of the experimental relative transition intensities of the three photons depopulating this band with those predicted from the rules of Alaga et al.; only fair agreement was noted. A discussion is given of the beta decay branchings and log ft values of Np/sup 238/ decay in terms of the postulated characters of the Pu/sup 238/ states and the measured spin of Np/sup 238/. (auth)
Date:
December 1, 1960
Creator:
Albridge, R. G. & Hollander, J. M.
System:
The UNT Digital Library
Evaluation of Buried Conduits as Personnel Shelters
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 radiations, protection is afforded by use of such conduits of various configurations. Measurements were made of free-field overpressure at the ground surface above the structure; pressure inside the structures; acceleration of each structure; deflection of each structure; dust inside each structure; fragmentary missiles inside the concrete structures; and gamma and neutron radiation dose inside each structure. All buried conduit sections tested provided adequate Class I protection for the conditions under which the conduits were tested. Standard 8-foot concrete sewer pipe withstood 126-psi overpressure without significant damage, minor tension cracks observed; standard 10-gage corrugated-steel 8-foot circular conduit sections withstood 126- psi overpressure without significant damage; and standard 10-gage corrugated- steel cattle-pass conduits withstood 149-psi overpressure without significant damage. Durations of positive pressure were from 206 to …
Date:
July 14, 1960
Creator:
Albright, G. H.; LeDoux, J. C. & Mitchell, R. A.
System:
The UNT Digital Library
Control and Dynamics Performance of a Sodium Cooled Reactor Power System
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, the nuclear reactor had been the major focus of attention, the development of the sodium cooled reactor and sodium pumps for this application are thought to need the less development than the heat exchanger equipment. Consequently, parallel design studies of the reactor, pumps, and other system components have not yet been initiated.
Date:
1960
Creator:
Alco Products (Firm).
System:
The UNT Digital Library
Intermediate Heat Exchanger and Steam Generator Final Design. Volume 1. Thermal & Mechanical Design
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 enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shutdown it will be necessary to allow time for radioactive decay before the unit will be accessible to personnel. Because of inaccessibility and possible long periods allowed for decay time, it is imperative that the unit give trouble free operation. During periods of shutdown, the internals should have easy access for inspection and repair if necessary so that down time is held to a minimum. The steam generator is designed to generate superheated steam using liquid sodium from the intermediate heat exchanger as the heat source. Its basic design is a shell and tube unit made up of three difference sections: (1) a …
Date:
September 30, 1960
Creator:
Alco Products (Firm).
System:
The UNT Digital Library