1000-Mwe SGR. 90% ThO₂, 10% UO₂ Alternate Fuel Core Thermal and Hydraulic Analysis (open access)

1000-Mwe SGR. 90% ThO₂, 10% UO₂ Alternate Fuel Core Thermal and Hydraulic Analysis

The thermal and hydraulic core parameters were determined using the SORTD I code for 90% ThO/sub 2/, 10% UO/sub 2/ fuel both for (1) a core containing 592 fuel elements corresponding to the UC reference core with a maximum UC temperature of 2000 deg F and (2) a core containing 784 fuel elements corresponding to a UC core with a maximum UC temperature of 1750 deg F. Eighteen rod elements with 2.5 in./sup 2/ and 3.5 in./sup 2/ fuel areas, and 30 rod elements with 4.5 in./sup 2/ and 5.5 in./sup 2/ fuel areas are analyzed for 8 cases. (auth)
Date: February 19, 1964
Creator: Imig, J. K.
System: The UNT Digital Library
DATA SIMULATION WITH AN ON-LINE COMPUTER AS A DIAGNOSTIC AND ANALYTICAL TOOL (open access)

DATA SIMULATION WITH AN ON-LINE COMPUTER AS A DIAGNOSTIC AND ANALYTICAL TOOL

A hybrid approach was adopted in the use of an on-line computer in setting up and analyzing nuclear physics experiments. In addition to the usually cited advantage of online flexibility and the ability to do off-line calculations, the general purpose computer can simulate data by preserting the results of off-line calculations to the experimenter in a format identical to that used for data display. As compared with off-line calculations at a computer center with subsequent hand or machine plotting, the use of the build-in display hardware provides a more convenient comparison of theory with experiment, as well as greater ease and speed. The advantages of on-line data transformation are preserved without accompanying limitations on the rate of data taking. The data from the experiment consisted of energy correlations in two-particle coincidence experiments. The loci of points in energy-energy space fulfilling energy and momentum conservation were calculated, displayed, and photographed before each experimental run. Interpretation of the experimertal data was assisted by modulation of the loci (of the number of counts per channel) according to the predictions of various models. (auth)
Date: February 19, 1964
Creator: Mollenauer, J.F.
System: The UNT Digital Library
Fission product formation in fuel elements (open access)

Fission product formation in fuel elements

None
Date: February 19, 1964
Creator: Shields, R. J.
System: The UNT Digital Library
Control Drum Bearings, Experiment No. 40/W004, Irradiated at Plum Brook Reactor Facility, PBRF Cycle 6 (PB No. 2W). Preliminary Data Report (open access)

Control Drum Bearings, Experiment No. 40/W004, Irradiated at Plum Brook Reactor Facility, PBRF Cycle 6 (PB No. 2W). Preliminary Data Report

Preliminary results of the irradiation of control drum bearings in a static test, conducted at the Plum Brook Reactor Facility in Sandusky, Ohio, on October 14-15, 1963, are described in this report.
Date: February 19, 1964
Creator: Stephens, A. G.
System: The UNT Digital Library