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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719 Matching Results
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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.
Date:
May 1, 1960
Creator:
Curtiss-Wright Corporation
System:
The UNT Digital Library
Boiling Water Reactor Study [Part 4]: 100 Mw Boiling Water Reactor Conceptual Design
From introduction: This report sets forth the results of a study of a 100-mw dual cycle boiling water reactor, nuclear power plant.
Date:
February 1960
Creator:
Ebasco Services Incorporated
System:
The UNT Digital Library
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.
Date:
March 1, 1960
Creator:
Walter, J. H.; Leirich, J. F. & Calkins, G. D.
System:
The UNT Digital Library
Reactivity Absorbed by Xenon-135 in the SRE
Abstract: The measurement and calculation of the reactivity absorbed by Xe135 as functions of time after shutdown for the SRE are described.
Date:
January 28, 1960
Creator:
Woodruff, R. W.
System:
The UNT Digital Library
Wind Tunnel Study of the Influence of Orifice Geometry and Flow Rates on the Measured Pressure Error of a Static Pressure Probe at Mach 3
Abstract: Tests were conducted in the Jet Propulsion Laboratory's 20-inch Supersonic Wind Tunnel to determine the effect of hole-spacing geometry on the measured pressure error due to "breathing" for a pressure-sensing probe at Mach 3.01.
Date:
November 1960
Creator:
Zumwalt, Glen W.
System:
The UNT Digital Library
A Confidence Limit Computer
Introduction: Confidence limits as a mathematical tool are applicable to many development engineering and production engineering situations. In order to make confidence limits readily available to engineers, a computer was designed which will approximate certain confidence limits.
Date:
April 1960
Creator:
Muench, Joseph O.
System:
The UNT Digital Library
A Transistorized Reactivity Measurement System
An all-transistor system has been developed to be used in measuring the reactivity of the reactor in the Sandia Engineering Reactor Facility. In operation, the system triggers a pulsed neutron source (PNS) in the reactor and counts the resulting neutron flux, thus giving a measure of the time constant of the reactor. The counting is done in eleven time-sequenced counting channels. The reactor time constant is a measure of the reactor reactivity.
Date:
July 6, 1960
Creator:
Ehrman, Leonard
System:
The UNT Digital Library
Vapor Pressures of the Rare Earths
Abstract: This report presents the vapor pressures versus temperature data graphically for the rare earth elements, yttrium and scandium.
Date:
August 2, 1960
Creator:
Beavis, L. C.
System:
The UNT Digital Library
An Aid to Printed Circuit Layouts Using the IBM-704 Computer
Abstract: This memorandum presents the possible applications and instructions for using REDCROSS, an IBM-704 computer program.
Date:
June 1960
Creator:
Stearns, Samuel D. & O'Connell, R. A.
System:
The UNT Digital Library
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.
Date:
May 1, 1960
Creator:
Corporales, G. W. & Benson, P. R.
System:
The UNT Digital Library
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.
Date:
May 1, 1960
Creator:
Sudar, S.
System:
The UNT Digital Library
P-V-T Relationships of BF₃ Gas
Abstract: A generalized equation of state developed by Gouq-Jen Su and Chien-Hou Chang is used for predicting P-V-T behavior of BF3 at high gas densities.
Date:
July 30, 1960
Creator:
Smith, C. R. F.
System:
The UNT Digital Library
Prediction of Shock Response
Abstract: A method is presented of predicting the shock response of a friction-damped vibratory system.
Date:
November 1960
Creator:
Barba, Peter M.
System:
The UNT Digital Library
Plutonium: Enriched OMR Cores
Abstract: The influence of plutonium on the nuclear characteristics of organic moderated cores is studied.
Date:
May 1, 1960
Creator:
Connolly, T. J.
System:
The UNT Digital Library
A High-Voltage Pulse Generator for Testing Dielectric Samples
Abstract: The purpose of this report is to describe the problems inherent to general dielectric strength measurements, and to act as a guide in establishing a method for pulse dielectric strength measurements.
Date:
July 13, 1960
Creator:
Kelly, R. D.
System:
The UNT Digital Library
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.
Date:
June 1, 1960
Creator:
Ballif, J. L.; Hayward, B. R. & Walter, J. W.
System:
The UNT Digital Library
Valve Stem Freeze Seal for High-Temperature Sodium
Abstract: An experimental study of valve stem freeze seals was undertaken as part of the effort to develop components for high temperature service in advanced sodium-cooled reactor systems.
Date:
July 30, 1960
Creator:
McDonald, J. S.
System:
The UNT Digital Library
High Velocity Shock Testing, Equipment and Methods
The need for special high velocity shock testing is pointed out and equipment that has been developed to meet these needs is discussed. The concept of velocity-change and its importance in shock-testing technology is brought out. The three types of equipment discussed are: accelerated drop testers, pneumatic actuators, and air guns. Examples of each type and their capabilities and limitations are presented.
Date:
July 11, 1960
Creator:
Walker, Walter W.
System:
The UNT Digital Library
Vapor Pressures of the Rare Earths
Abstract: This report presents the vapor pressures versus temperature data graphically for the rare earth elements, yttrium and scandium.
Date:
December 23, 1960
Creator:
Beavis, L. C.
System:
The UNT Digital Library
Piqua Prototype Handling System
Abstract: Equipment has been developed to handle the fuel elements and control rods for the Piqua (OMR) reactor.With the handling machine, which consists of a shielded cask mounted on a gantry, a fuel element can be replaced in the core in about 27 minutes.
Date:
May 1960
Creator:
Nadler, H.
System:
The UNT Digital Library
An Advanced Sodium-Graphite Reactor Nuclear Power Plant
Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Date:
March 15, 1960
Creator:
Churchill, J. R. & Renard, J.
System:
The UNT Digital Library
A Multichannel Digital Recording System
Abstract: This report is a description of a 200 channel digital recording system used to record high temperature strain gage outputs and associated temperatures.
Date:
September 15, 1960
Creator:
Truitt, R. W.
System:
The UNT Digital Library
Fabrication of Yankee Core I Prototype Fuel Element
Introduction: Development of a process for manufacturing fuel elements for the Yankee reactor and fabrication and testing of a prototype assembly is reported.
Date:
May 1960
Creator:
D'Amore, M.
System:
The UNT Digital Library
Heavy Water Moderated Power Reactor Plants [Part 1]: Design Study
From preface: This report is one of a series covering a design study of heavy water moderated power reactor plants with the objective of selection and recommendation of a conceptual design for providing optimum economics with slight fuel enrichment.
Date:
February 1960
Creator:
unknown
System:
The UNT Digital Library