Serial/Series Title
13 Matching Results
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13
Process Waste Water Treatment Plant: Preliminary Report
Preliminary report on waste water treatment plant to treat the low level radioactive liquid waste from the various laboratory processes.
Date:
February 1957
Creator:
unknown
System:
The UNT Digital Library
Preliminary Investigations for an Advanced Engineering Test Reactor
Study carried out to determine a suitable reactor system or systems for the testing of water, gas, and liquid-metal cooled fuel assemblies.
Date:
February 22, 1957
Creator:
Elgert, O. J.; Leyse, C. F. & Ott, D. G.
System:
The UNT Digital Library
Preliminary Investigations for an Advanced Engineering Test Reactor: Addendum
More detailed study of an advanced engineering test reactor.
Date:
April 16, 1957
Creator:
Leyse, C. F. & Leonard, B. H., Jr.
System:
The UNT Digital Library
Subcritical and Critical Flow Through Straight-Through, Elbow, and Tee "AN" Fittings and Sharp-Edged Orifices at Elevated Temperatures
Investigation of the flow through straight-through , elbow, and tee "AN" fittings at negligible approach velocity with approach temperatures up to 1100 degrees F.
Date:
March 6, 1957
Creator:
Ducoffe, Arnold L.; Bennett, John R. & Ray, C. Gable
System:
The UNT Digital Library
Safeguard Report: Livermore Pool Type Reactor
Safety measures of the Livermore Pool Type Reactor in reaction to certain meteorological conditions and following the improbable rupture of the reactor building.
Date:
January 17, 1957
Creator:
Detterman, Robert L.
System:
The UNT Digital Library
Liquid Metal Fuel Reactor Experiment, Quarterly Technical Report: May 1957 - September 1957
Quarterly technical report discussing progress and activities of the Liquid Metal Fuel Reactor Experiment.
Date:
May 1957
Creator:
Babcock & Wilcox Company
System:
The UNT Digital Library
The Purex process : a Solvent Extraction Reprocessing Method for Irradiated Uranium
Purex process which utilizes solvent extraction to separate and purify uranium and plutonium from each other and from fission products contained in irradiated uranium fuel elements.
Date:
April 8, 1957
Creator:
Irish, E. R. & Reas, W. H.
System:
The UNT Digital Library
A Martensitic Reaction for Uranium
Series of isothermal transformation studies for improvement in fabrication and reactor performance of uranium fuel elements.
Date:
June 25, 1957
Creator:
Bement, A. L. & Wallace, W. P.
System:
The UNT Digital Library
Plating Thickness Tester
An electromagnetic eddy current instrument is described that is capable of measuring copper and nickel plating 1 to 8 mils thick plated on bismuth mandrils of various sizes and shapes.
Date:
November 15, 1957
Creator:
Fitch, C. E., Jr.
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
APPR-1: Design, Construction and Operation
"This document includes papers covering technical problems involved in the design, construction and operation of the APPR-1" (p. 4).
Date:
November 20, 1957
Creator:
unknown
System:
The UNT Digital Library
Initial Operation and Testing of the Army Package Power Reactor APPR-1
Startup and initial operation of the APPR-1 and summary of the results of the test program on the reactor.
Date:
August 9, 1957
Creator:
Meem, J. L.
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