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Gas-Cooled Reactor Project Semiannual Progress Report: March 1964
Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project. From summary: "A study was made of the effect of the energy of extraneous source neutrons on the amplitudes of higher modes in the flux distribution of a subcritical reactor."
Date:
July 1964
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
The Design of a Dynamic Corrosion and Chemical Control Test Loop and Preliminary Out-of-Pile Test Results
From abstract: "This report describes the overall loop design and the means by which this design was developed. These include critical facility measurements, analog computer calculations, hydraulic and heat transfer computations, and the construction and operation of an out-of-pile mock-up loop to determine the dynamic characteristics of the loop."
Date:
July 12, 1963
Creator:
Zelezny, W. F.
System:
The UNT Digital Library
EDP Procedures in Technical Library Operations
Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.
Date:
July 30, 1963
Creator:
Griffin, Hillis L.
System:
The UNT Digital Library
Evaluation of Thorium Fuels for the Heavy Water Organic Cooled Reactor
From abstract: "A summary of work done by The Babcock & Wilcox Company to evaluate thorium fuels for the Heavy Water Organic Cooled Reactor (HWOCR)."
Date:
July 1966
Creator:
unknown
System:
The UNT Digital Library
Experimental Radiation Measurements in Conventional Structures: Part 1, Radiation Measurements in Two Two-Story and Three One-Story Typical Residential Structures Before and After Modification
Report discussing the methods, data, and analysis of results for "An experimental study designed to provide a basis for estimating protection against fallout radiation " (p. v) using one- and two-story structures with basements.
Date:
July 1966
Creator:
Burson, Z. G.
System:
The UNT Digital Library
Fabrication of Fuel Rods by Tandem Rolling
From introduction: "The purpose of this report is to present the details of the exploratory and developmental work on tandem rolling, and the subsequent fabrication of tandem rolled fuel rods for irradiation testing in the Vallecitos Boiling Water Reactor."
Date:
July 1961
Creator:
Lingafelter, J. W.
System:
The UNT Digital Library
Fundamentals in the Operation of Nuclear Test Reactors: Volume 3 Engineering Test Design and Operation
Engineering test reactor design and operation.
Date:
July 1964
Creator:
unknown
System:
The UNT Digital Library
An Investigation of a "Dynamic" Theory for Mass Transfer
A new theory is proposed to evaluate individual mass-transfer coefficients without actual experiment.
Date:
July 18, 1960
Creator:
Schappel, Richard B.
System:
The UNT Digital Library
Materials for Superheated Fuel Sheaths: Relative Performance of Alloys in Superheated Steam Environments
From abstract: "Study of radiation effects upon the tensile properties of the alloys, corrosion behavior in the absence and presence of stress, effect of prolonged, high temperature exposures upon structure sensitive properties of the alloys, and physical metallurgical changes as a function of exposure in a superheat environment.
Date:
July 1963
Creator:
Comprelli, F. A.; MacMillan, D. F. & Spalaris, C. N.
System:
The UNT Digital Library
Numerical Results for EGCR Moderator-Element Stress Problems
From introduction: "A recent report describes the development of a general program for the IBM Type 7090 electronic computer for calculating plane thermal stresses."
Date:
July 3, 1961
Creator:
Hulbert, Lewis E. & Redmond, Robert F.
System:
The UNT Digital Library
Power Distributions for Type 3 Replacement Cores for SM-1, SM-1A and PM-2A
Abstract: The most adverse power distribution and power peaking factors have been developed for Type 3 replacement cores for SM-1, SM-1A, and PM-2A. Also included is the 37 element Type 3 core for SM-1, which is known as SM-1 Core III and is a prototype of a Type 3 core for PM-2A. The power distributions were compared with measured distributions obtained on type 3 fuel elements in SM-1, SM-1A and PM-2A core configurations. Using the measured data as a standard, correction factors were obtained and applied to the analytical predictions of the most adverse power distribution.
Date:
July 25, 1962
Creator:
Oggerino, J. P.
System:
The UNT Digital Library
SM-2 Full Scale Flow Studies Termination Report
Abstract: Hydrodynamic flow studies were conducted on a full scale model of the SM-2 reactor vessel and core. Test fluid was water at 200 psi and 200 degree F. Test facilities, model, and instrumentation design are discussed. Flow distribution in the stationary fuel elements, lattices, and control rods of the second pass was investigated. Pressure losses through the various core components were measured and are compared with calculated values. Observed over-all pressure drop was 71 feet of water at 200 degree F, 31% higher than predicted, part of which was due to presence of instrument leads. Element to element flow distribution varied approximately +-8% from pass average. Channel-to-channel stationary element flow distribution varied approximately +-10% from element average and control rod flow distribution varied from +-8.9% to +-6.4 and -11.6% depending upon rod locations. These variations exceed the original goals of a +-10% and +-12% combined deviation for stationary and control rod elements respectively, but are satisfactory in relation to thermal design. There was no indication of unsatisfactory structural performance of any components under hydrodynamic loadings up to 130% of design values. The test program was terminated after determining flow distribution in the reference core design, omitting any work on …
Date:
July 30, 1961
Creator:
Christenson, J. A.; Richards, W. M. S. & Davidson, S. L.
System:
The UNT Digital Library
Standardization and Evaluation of Grain Size Test for Uranium Fuel
Report that "describes the selection of "standard fuel cores for calibrating an ultrasonic tester designated UT-2C" (p. 3) at Hanford Laboratories.
Date:
July 1964
Creator:
Spice, R. D.
System:
The UNT Digital Library
Transistorized Pulse Counting Equipment
This instrument was designed primarily to meet the need for radiation monitoring equipment in chemical process areas where corrosive vapors exist.
Date:
July 26, 1960
Creator:
Henry, John J.
System:
The UNT Digital Library
X-Ray Fluorescence Tables: Program Description
Report discussing the mechanics of X-Ray and COMBO computer programs.
Date:
July 20, 1964
Creator:
Amsbury, W. P.; Lee, W. W.; Rowan, J. H. & Walden, G. E.
System:
The UNT Digital Library