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Project CGC-830 Plant Modifications for Reprocessing Non-Production Reactor Fuels Design Criteria for Metal Solution Storage (open access)

Project CGC-830 Plant Modifications for Reprocessing Non-Production Reactor Fuels Design Criteria for Metal Solution Storage

Facilities shall be provided in the 221-U Building for storing the metal solution product of the dissolution step in existing tankage from U, T, and B Plants until a reprocessing campaign is scheduled through Redox. This section shall provide a sampling tank for fuel accountability sampling and a pump tank from which the solution will be pumped via a cross-country pipeline to Redox for further processing.
Date: April 26, 1960
Creator: Duda, R. F.; Graf, W. A. & Kligfield, G.
System: The UNT Digital Library
Experiments With Pulsed Magnetic Cusps (open access)

Experiments With Pulsed Magnetic Cusps

Experiments with a simple pulsed magnetic field in cusped geometry are described. The plasma is generated inside the containment region rather than injected from an external source. It was found that creation of the plasma by a linear pinch discharge is most successful. Only qualitative studies have been carried out so far, using time-resolved visual observation of the plasma. Well-defined plasma bodies located in the central region between the cells were photographed. In order to make them clearly visible, a few percent of argon was added to the hydrogen.
Date: May 26, 1960
Creator: Watteau, Jean-Paul H.
System: The UNT Digital Library
Additional Miscellaneous Tools in the HRT Core (open access)

Additional Miscellaneous Tools in the HRT Core

This memorandum presents a description of several additional miscellaneous HRT core maintenance tools, not in an earlier report (1). These tools were used in the removal of the cut up diffuser plates, probing the core wall, gauging the size of the holes, and other simple tasks. Function, design, and operation are described for the following items.
Date: September 26, 1960
Creator: Holz, P. P.
System: The UNT Digital Library
Instructions for the Operation of an ORACLE Code for a Monte Carlo Solution of the Transport Problem for Gamma Rays Incident Upon a Slab (open access)

Instructions for the Operation of an ORACLE Code for a Monte Carlo Solution of the Transport Problem for Gamma Rays Incident Upon a Slab

A program has been coded for the ORACLE which will solve, using Monte Carlo technique, the transport problem for monodirectional, monoenergetic gamma radiation incident at an angle Θ, upon an infinite laminated slab of finite thickness. Each of the laminations (or regions) is itself an infinite, homogeneous slab of finite thickness. The code is designed to give estimates of energy deposition, energy flux, tissue dose rate, reflected and transmitted energy current, and the angular and energy distribution of the reflected and transmitted energy current. All the answers except for energy deposition and reflected and transmitted energy current are optional.
Date: October 26, 1960
Creator: Aulender, S. & Trubey, D. K.
System: The UNT Digital Library