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7 Matching Results
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Experimental Breeder Reactor-II (EBR-II) Shield Design
Report describing the EBR-II shield and the methods employed in arriving at the final design. The major shield design problems for that reactor are enumerated and discussed.
Date:
September 1962
Creator:
Grotenhuis, M.; McArthy, A. E. & Rossin, A. D.
System:
The UNT Digital Library
Design Summary Report on the Juggernaut Reactor
Report issued by the Argonne National Laboratory over design studies conducted on the Juggernaut reactor. Design processes, and methods are presented and discussed. This report includes tables, illustrations, and photographs.
Date:
September 1962
Creator:
Folkrod, J. R.; Ember, G.; Kolb, W.; Saluja, J. & Moon, D. P.
System:
The UNT Digital Library
Breeding-Gain Specimens for EBR-I Core IV
Report issued by the Argonne National Laboratory over studies conducted on uranium and plutonium specimens used in fuel rods. The results are presented and discussed. This report includes tables, illustrations, and photographs.
Date:
September 1963
Creator:
Shuck, A. B.; Hins, A. G.; Burt, W. R. & Beatty, R. A.
System:
The UNT Digital Library
The Graetz Problem in Cocurrent-Flow, Double-Pipe, Heat Exchangers
Report showing "that the Graetz Problem pertaining to the cocurrent-flow, double-pipe, heat exchanger can be studied analytically by extensions of familiar mathematical techniques" (p. 7).
Date:
September 1964
Creator:
Stein, Ralph P.
System:
The UNT Digital Library
The Mass Transfer of Single, Solid Uranium Spheres to Flowing Molten Cadmium in Laminar and Turbulent Flow
From Summary and Abstract: "In this study, a 1/2-inch diameter uranium sphere was used and molten cadmium was pumped past the test spheres at different flow rates. Mass transfer coefficients were determined from weight losses of the test spheres."
Date:
September 1965
Creator:
Traylor, E. Dean
System:
The UNT Digital Library
A Hybrid-Computer Program for Transient Temperature Calculations on TREAT Fast Reactor Safety Experiments
Report issued by the Argonne National Laboratory discussing a computer program used for fast reactor safety experiments. As stated in the summary, "this report gives a detailed description of a hybrid-computer program for calculating temperatures in a multi-region, axisymmetric, cylindrical configuration consisting of solid materials bounded by flowing coolant. Included is an explanation of the mathematical methods, together with a discussion of special features, input-output descriptions, and several sample problems" (p. 7). This report includes tables, and illustrations.
Date:
September 1967
Creator:
Bryant, Lawrence T.; Amiot, Lawrence W.; Dickerman, Charles E. & Stephany, William P.
System:
The UNT Digital Library
Flow-Regime Transitions at Elevated Pressures in Vertical Two-Phase Flow
Two-phase flow-regime transitions at elevated pressures for a single-component, trichloromonofluoromethane, were investigated for forced-circulation, upward flow in a vertical, rectangular conduit with internal dimensions of 0.380 by 1.050 inches.
Date:
September 1965
Creator:
Baker, James L. L.
System:
The UNT Digital Library