Resource Type
Serial/Series Title
Atomic Energy Commission Reports
264
University of California Radiation Laboratory Reports
112
HW (Series)
110
Hanford Works Reports
103
AEC research and development report
91
Oak Ridge National Laboratory Reports
76
TID
60
NYO (Series) (New York)
49
Report (U.S. Atomic Energy Commission)
43
UC (Series)
29
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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
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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
Object Type:
Report
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
Object Type:
Report
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
Object Type:
Report
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).
Object Type:
Report
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).
Object Type:
Report
System:
The UNT Digital Library
Intermediate Heat Exchanger and Steam Generator Final Design. Volume 2. Chemical & Stress Analysis
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 maintain the integrity of the steam generator vessel under maximum leak conditions. The method of sizing relief valves for each unit under varying leak rates is presented in this text and operation of the unit for the various leak rates is resented in the Operation and Maintenance volume. The stress analysis section covers those thermal transients which would be physically possible with this intermediate heat exchanger and steam generator design. Attention has been given to methods of operation which would minimize the magnitude and frequency of thermal shocks. Certain areas have been studied in detail where thermal stresses appear high. This report also includes a structural design basis for handling stress analysis of combined mechanical, hydrostatic and thermal stresses and conditions …
Date:
September 30, 1960
Creator:
Alco Products (Firm).
Object Type:
Report
System:
The UNT Digital Library
Intermediate Heat Exchanger and Steam Generator Final Design. Volume 3. Specifications
Introduction: Sodium Components Material Specifications. Twenty-three material, inspection and welding specification are presented for the various parts of both the intermediate heat exchanger and steam generator. Tables indicate the applicable parts and assemblies to which these specifications shall apply. For other parts, where the material requirements are not severe, the ASTM or other indicated specifications shall apply.
Date:
September 30, 1960
Creator:
Alco Products (Firm).
Object Type:
Report
System:
The UNT Digital Library
Intermediate Heat Exchanger and Steam Generator Final Design. Volume 4. Operation & Maintenance
This technical report contains the operation and maintenance specifications for the intermediate heat exchanger and the steam generator. The report contains eight sections: (1) General Information, (2) Shipping and Installation, (3) Operation Procedures, (4) Scram and Casualty Shutdowns, (5) Leaks, (6) Instrumentation and Control, (7) Maintenance, and (8) four Appendixes (a) Boiler Water Chemistry Recommendations, (b) Final Concept Drawings, (c) Industrial Nucleonics Literature on Liquid Level Detector, and (d) Sodium Purity Control Recommendations.
Date:
September 30, 1960
Creator:
Alco Products (Firm).
Object Type:
Report
System:
The UNT Digital Library
Scale "Up or Down" Analysis for Prototype Test
Introduction: In conjunction with the final design and development of a 70 MW sodium intermediate heat exchanger and a sodium steam generator, an analysis is required which can be used as a basis for a determination to scale up or scale down the designs. Included in this analysis are those considerations leading to the recommendation of the best prototype test unit and to some of the limits imposed on scaling up or down when considering future applications of designs other than those actually tested. In addition, these considerations include aspects required to accurately predict the performance, operation, mechanical reliability, and feasibility of fabrication of the 70 MW design.
Date:
May 1, 1960
Creator:
Alco Products (Firm).
Object Type:
Report
System:
The UNT Digital Library
State of Matter at High Pressure
Abstract. The region where exact thermodynamic description of the state of matter at high pressure and high temperature is possible is located. In the remaining region various approximate theories and empirical relations are discussed. These considerations are applied to hydrogen to locate the density and pressure at which the diatomic bond collapses. Also the approximate conditions are determined at which no bound electron states exist.
Date:
March 31, 1960
Creator:
Alder, Berni J.
Object Type:
Report
System:
The UNT Digital Library
A Study of the Effects of Some Spray Column Variables on Radiant-Heat Transfer in Spray Calcination
Calcination of liquid radioactive wastes, the process of converting metal nitrates and sulfates to oxides by heat, is under development at Hanford as a means of reducing these liquids to a dry powder or solid which can be stored safely. Radiant-heat spray calcination, one of the methods under study, was first investigated at the Oak Ridge K-25 Plant (1) as a possible method of calcining uranyl nitrate to uranium trioxide. The process has also been under extensive development at the Pulp and Paper Research Institute of Canada (2) and is designated by them as the Atomized Suspension Technique.
Date:
April 28, 1960
Creator:
Allemann, Rudolph Theodore
Object Type:
Report
System:
The UNT Digital Library
Completion Report An Automatic Fuel Element Stamping Machine
This document will be concerned with the design, operation and maintenance of an automatic fuel element stamping machine. In order to take advantage of automatic unloading and length checking at the Acme-Gridley lathes in the 313 Building, automatic stamping of fuel elements is desirable. This, along with the need for a permanent canning line identification, resulted in a request for a machine to automatically stamp HAPO fuel elements on a production basis.
Date:
January 12, 1960
Creator:
Allen, C. H.
Object Type:
Report
System:
The UNT Digital Library
The Interactions Of Strange Particles
This report is a corrected copy of the authors "rapporteur talk" at the 1959 Kiev Conference on High Energy Physics. It contains data on the rapporteur system and on interactions of strange particles with protons and neutrons, using data from bubble chambers, counters, and emulsions.
Date:
August 11, 1960
Creator:
Alvarez, Luis W.
Object Type:
Report
System:
The UNT Digital Library
Density and Hydrogen Content of Uranium Oxide Cakes and Slurries
The work described was undertaken to provide data for nuclear safety studies concerning NPF reprocessing equipment. The original objective was to determine the uranium density and water (hydrogen) content of UO2-H2O mixtures ranging from compact centrifuge cakes to dilute slurries. The scope was later expanded to include mixtures of UO2 with hydrocarbon oil and mixtures of UO3-H2O.
Date:
March 22, 1960
Creator:
Amos, L. C.
Object Type:
Report
System:
The UNT Digital Library
Semi Works Studies for the Reduction of Corrosion-Product Impurities in UR-Plant UO3
This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).
Date:
June 14, 1960
Creator:
Amos, L. C.; Kirkendall, B. E. & Adler, K. L.
Object Type:
Report
System:
The UNT Digital Library
LRL-Nevada Drill Hole Survey Technique
The demands of the scientific programs of the Lawrence Radiation Laboratory at the Nevada Test Site have necessitated the development of special drill hole survey techniques. These techniques, in general, have made possible the attainment of greater survey accuracies than are ordinarily obtained by the drilling industry in the course of normal survey work. For drill holes requiring a moderately high degree of location accuracy, standard survey equipment, manufactured by Eastman Oil Well Survey Company was adapted by LRL to meet this need. Where an extremely high degree of survey accuracy and control of drilling effort is necessary, such as in the drilling and survey of line-of-sight holes, special optical equipment was developed. The modifications of equipment, refinements in procedures, and special techniques necessary to adapt this equipment to meet the more demanding accuracy requirements of scientific programs are discussed. The overall techniques of survey, equipment used, and the accuracies obtained together with results of completed surveys showing a comparison with standard land survey methods are also discussed and illustrated in some detail.
Date:
December 1960
Creator:
Anderson, Arthur L.; Skousen, Lester P. & Bennett, Walter P.
Object Type:
Report
System:
The UNT Digital Library
Preliminary petrographic study of rock from Nevada Test Site - Basalt Mesa
Discussing photographs of rocks from Basalt Mesa
Date:
May 6, 1960
Creator:
Anderson, E. E.
Object Type:
Report
System:
The UNT Digital Library