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Criticality Calculations for Hydrogen Moderated Reactors From Microscopic Data

Description: From abstract: "The probability for a fission neutron to escape fast leakage from bare, hydrogen moderated reactors is calculated by a method utilizing only the microscopic cross section of the materials. These results can be employed to determine the effectiveness of other substances in preventing fast neutron leakage. These calculations are carried out for aluminum and iron."
Date: November 29, 1951
Creator: Shapiro, Mathew; Preiser, Stanley & Young, Gale
Partner: UNT Libraries Government Documents Department
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Solid State Division Quarterly Progress Report for Period Ending May 10, 1952

Description: From introduction: "This report covers work performed in the Solid State Division for the quarter ending May 10, 1952." Topics covered include radiation metallurgy, engineering properties, solid state reactions, crystal physics, and special projects.
Date: December 29, 1952
Creator: Billington, D. S., (Douglas S.) & Howe, J. T.
Partner: UNT Libraries Government Documents Department
open access

Homogeneous Reactor Project Quarterly Progress Report: November 1959-January 1960

Description: From Summary: "The major objective of the run was the investigation of fuel stability. The reactor operated for long periods at the design power of 5 Mw with none of the usual indications of instability while the system pressure was kept at 1250 psig. Run 21 ended on January 22, so that the reason for an abrupt change in the mixing rate of fuel between the core and blanket could be investigated and a reactor steam-system valve could be repaired."
Date: April 29, 1960
Creator: Briggs, R. B.
Partner: UNT Libraries Government Documents Department
open access

Description and Vibrational Analysis of the Molecular Spectrum of Polonium

Description: Report issued by the Oak Ridge National Laboratory discussing the vibrational analysis of the molecular spectrum of polonium. Experimental procedures, results, and analysis are presented. This report includes tables, illustrations, and photographs.
Date: January 29, 1957
Creator: Charles, G. W.; Hunt, D. J.; Pish, G. & Timma, D. L.
Partner: UNT Libraries Government Documents Department
open access

A Fluoride Fuel In-Pile Loop Experiment

Description: An inconel loop circulating fluoride fuel (62 1/2 make [unintelligible] NaF, 12 1/2 make [unintelligible] ZrF4, 25 make [unintelligible] UF4, 92 [unintelligible] enriched) was operated at 1485°F with a temperature difference of about 35°F in the Low Intensity Test Reactor for 645 hr. For 475 hr of this time the reactor was at full power, and fission power generation in the loop was 2.7 kw, with a max length power density of 0.4 kw/cc. The total volume of fuel was 1290 cc (5.o kg [unintelligible… more
Date: January 29, 1957
Creator: Sisman, Q; Brundage, W. E.; Parkinson, W. W.; Boumann, C. D.; Correll, R. M; Morgen, J. G. et al.
Partner: UNT Libraries Government Documents Department
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