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Nomograms for the Area Analysis of Neutron Self-Indication and Transmission Measurements
Abstract: An IBM-650 computer has been used to calculate series terms required for the area analysis of Doppler-broadened neutron cross section resonances according to the formulation of G. M. Roe.
Date:
August 22, 1957
Creator:
Morgan, E. L. & Yeater, M. L.
System:
The UNT Digital Library
The Effects of Irradiation Cycling on Pressurized Water Reactor Blanket Fuel Elements
From introduction: This report details the results of the post-irradiation examination of a test involving one defected rod and one undefected rod.
Date:
March 13, 1957
Creator:
Eichenberg, John D.
System:
The UNT Digital Library
11,400 KW Nuclear Power Plant Employing an Organic Moderated Reactor: Preliminary Description
Abstract: The preliminary design is described for a small electric-power-generating plant powered by an organic moderated reactor. System and component requirements are discussed and possible design configurations and equipment are described.
Date:
1957
Creator:
Wheelock, C. W.
System:
The UNT Digital Library
Basic Chemistry of High Temperature Inorganic Systems, Semiannual Progress Report: July-December 1956
From abstract: The vapor pressure determination of solid ThF4 has been completed. Experiments to determine the heat of formation of ThF4 by studying the reaction of ThF4 with SiO2 are described.
Date:
July 15, 1957
Creator:
Yosim, S. J. & Milne, T. A.
System:
The UNT Digital Library
KEWB Program Quarterly Progress Report: July-September 1956
From abstract: The response of the reactor to forced oscillations has been investigated with the pile oscillator technique and the data are presently being analyzed.
Date:
March 1, 1957
Creator:
North American Aviation. Atomics International Division. Kinetic Experiments on Water Boilers Program.
System:
The UNT Digital Library
Organic Moderated Reactor Experiment Progress Report: October 1955-July 1956
Report describing technical progress on the design and construction of an Organic Moderated Reactor Experiment (OMRE), to be operated at the National Reactor Testing Station in Arco, Idaho. "This is the first report of the series and coves the period from the initiation of the project to July 31, 1956. Also included as an appendix to the report is a detailed description of the OMRE facility" (p. 3).
Date:
March 15, 1957
Creator:
Trilling, C. A.
System:
The UNT Digital Library
Reactor Safety Quarterly Progress Report: May-July 1956
From abstract: Impact tests on the Mark III Hanford safety element indicate that the design is mechanically adequate and does not constitute a personnel hazard.
Date:
March 15, 1957
Creator:
Miller, N. C.
System:
The UNT Digital Library
An Evaluation of the Calder Hall Type of Nuclear Power Plant
Abstract: Presented herein is the preliminary design of a natural uranium, graphite moderated, CO2-cooled reactor and power plant similar to, but larger than, the British Calder Hall plant, with a net electrical output of 130 MWE.
Date:
January 18, 1957
Creator:
Banks, William F.; Schneider, G. A.; Morgan, William T. & Ash, E. B.
System:
The UNT Digital Library
Organic Moderated Reactor Experiment Progress Report: August-October 1956
Report describing technical progress on the design and construction of an Organic Moderated Reactor Experiment (OMRE), to be operated at the National Reactor Testing Station in Arco, Idaho. "This is the second report of the series, and covers the period from August 1, 1956 through October 31, 1956" (p. 3).
Date:
November 15, 1957
Creator:
Trilling, C. A.
System:
The UNT Digital Library
A Simple Leak Detector for Tritium
From abstract: "An ionization chamber of the integrating type was built that could detect a tritium leak rate of 10[^-13] cc per second within a few minutes, after a gas-collecting period of 16 hours. Electronic circuitry was avoided by using a quartz fiber voltmeter to indicate the rate of discharge of the chamber."
Date:
January 1957
Creator:
Colvin, D. W.
System:
The UNT Digital Library
Instrumentation and Controls Division Semiannual Progress Report for Period Ending July 31, 1956
Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Instrumentation and Controls Division. Descriptions of progress and studies conducted are presented. This report includes illustrations, and photographs.
Date:
February 25, 1957
Creator:
Borkowski, C. J.
System:
The UNT Digital Library
Physics Division Semiannual Progress Report for Period Ending September 10, 1956
Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Physics Division. Descriptions of progress and studies conducted are presented. This report includes tables, and illustrations.
Date:
February 12, 1957
Creator:
Snell, A. H.; Fowler, J. L. & Wollan, E. O.
System:
The UNT Digital Library
Reactor Physics Primer
Report that describes the reactor physics of the processes used to produce plutonium at Hanford Laboratories. This includes a basic explanation of nuclear physics and the principles of the reactor process.
Date:
November 15, 1957
Creator:
Lockwood, E. H.
System:
The UNT Digital Library
Shielding of a Fast Breeder Reactor, [Part] 1: The Primary Shield
From introduction: "Report discussing the necessity for shielding of a fast breeder reactor, primary, graphite, and thermal shields, and safety considerations in the design of a primary shield."
Date:
1957
Creator:
Hungerford, H. E.
System:
The UNT Digital Library
Standard Practices for Design of MTR and ETR Safety Circuits
Report containing notes for designing safety circuits for the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR).
Date:
September 15, 1957
Creator:
Jones, L. H.
System:
The UNT Digital Library
Startup Operation of a Production Facility for Separating Barium-140 from MTR Fuel
Report describing "the startup operation of a batch production facility for separating and purifying barium-140 from short-cooled MTR fuel" (p. 3).
Date:
September 1, 1957
Creator:
Legler, Billy Mason; Fairbourne, S. F.; Kelly, P. N. & Robinson, R. A.
System:
The UNT Digital Library
Chemical Processing Instrumentation and Control Research Program
Report regarding the chemical processing instrumentation designs and problems at the Idaho Chemical Processing Plant.
Date:
September 18, 1957
Creator:
Schneider, Harry
System:
The UNT Digital Library
A Neutron Absorption Alignment Chart
From introduction: "Neutron absorption alignment chart for the measurement of neutron flux density."
Date:
July 30, 1957
Creator:
Nisle, Robert G.
System:
The UNT Digital Library
Scintillation Spectrometry : Gamma-Ray Spectrum Catalogue
Report presenting a collection of gamma spectra containing samples of the response of NaI(TI) scintillation detectors to a large number of the more frequently encountered radioactive nuclides.
Date:
July 1, 1957
Creator:
Heath, R. L.
System:
The UNT Digital Library
Summary of the Spert-I, -II, and -III reactor facilities
Report containing "[a] brief description and design data summary of each of the SPERT Reactor Facilities is presented. Engineering, operating, and physics data are tabulated for use as basic references" (p. 3)
Date:
November 1, 1957
Creator:
Montgomery, C. R.; Norberg, J. A. & Wilson, T. R.
System:
The UNT Digital Library