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Serial/Series Title
Atomic Energy Commission Reports
208
AEC research and development report
122
TID
88
UC (Series)
48
Oak Ridge National Laboratory Reports
47
General Electric Company Atomic Power Reports
44
ORNL (Series)
43
GEAP (Series)
42
United States Geological Survey Reports
35
Office of Saline Water Reports
33
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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.
Date:
May 1964
Creator:
Sarkissian, M. Der
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
January 7, 1964
Creator:
Goodzeit, C. L.
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
January 7, 1964
Creator:
Goodzeit, C. L.
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
January 3, 1964
Creator:
Rau, R. R.
Object Type:
Report
System:
The UNT Digital Library
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."
Date:
February 14, 1964
Creator:
General Electric Company
Object Type:
Report
System:
The UNT Digital Library
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."
Date:
February 14, 1964
Creator:
General Electric Company
Object Type:
Report
System:
The UNT Digital Library
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."
Date:
February 14, 1964
Creator:
General Electric Company
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
September 1964
Creator:
Walker, R. A. & Russell, J. T.
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
1964
Creator:
Ueda, Shoichi; Russell, Walter J. & Yano, Katsuhiko
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
March 1, 1964
Creator:
Rider, B. F.; Peterson, J. P., Jr.; Ruiz, C. P. & Smith, F. R.
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
1964
Creator:
Finch, Stuart C.
Object Type:
Report
System:
The UNT Digital Library
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."
Date:
January 1964
Creator:
Croft, M. W.
Object Type:
Report
System:
The UNT Digital Library
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."
Date:
February 1964
Creator:
Pickett, R. T., III
Object Type:
Report
System:
The UNT Digital Library
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."
Date:
January 1964
Creator:
Turner, Robert A.
Object Type:
Report
System:
The UNT Digital Library
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 …
Date:
March 1964
Creator:
Ogawa, S. Y.
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
March 1964
Creator:
MacKallor, Jules A.
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
March 1964
Creator:
MacLachlan, M. E.
Object Type:
Report
System:
The UNT Digital Library
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).
Date:
September 1964
Creator:
Benham, R. D. & Wilburn, N. P.
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
June 15, 1964
Creator:
Dunsmore, C. L.
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
September 1, 1964
Creator:
Swanson, C. D.; Coughren, K. D.; Dionne, P. J. & Thieme, G. G.
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
October 15, 1964
Creator:
Anderson, W. F.
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
August 13, 1964
Creator:
Scott, Charles D.
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
1964-12~
Creator:
Oak Ridge National Laboratory. Analytical Chemistry Division.
Object Type:
Report
System:
The UNT Digital Library
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.
Date:
March 1964
Creator:
United States. Task Group on Nuclear Power and Saline Water Conversion.
Object Type:
Report
System:
The UNT Digital Library