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GAS-COOLED REACTOR PROGRAM. QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JUNE 30, 1961

Description: Activities are discussed for research in design investigations, and materials development and testing conducted in connection with the development of the EGCR. The discussions are given in terms of: reactor physics; reactor design studies; heat transfer and fluid now investigations; materials development; in- pile and out-of-pile testing of components and materials; and development of test loops and components. (B.O.G.)
Date: August 28, 1961
Partner: UNT Libraries Government Documents Department
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Post irradiation examination of self support elements with severe in-reactor cladding corrosion (RM425)

Description: Three self support, natural uranium, I & E production fuel elements, which exhibited serious in-reactor cladding corrosion were selected from several tubes of discharged pieces from PT-IP-272-A-FP. The elements were transferred to the Radiometallurgy Laboratory for detailed examination to determine thickness of the remaining cladding and measure any irradiation induced dimensional changes in the fuel cores. Each element had four support tabs attached to each end and was from Parent Lot KT.009. … more
Date: August 28, 1961
Creator: Gruber, W. J.
Partner: UNT Libraries Government Documents Department
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Post irradiation examination of transverse cracked rupture from 2986 DR (Rm 427)

Description: An O III N, I and E dingot element exhibited several transverse cracks when it failed in tube 2986 DR. Detailed examination in the Radiometallurgy Laboratory was requested to determine the cause of failure and obtain the ingot number. The element was so badly damaged that it was impossible to determine the exact cause of failure. Reaction between the coolant and fuel occurred at the internal surface around the spire over the total length of the element. Reaction was the greatest near the midpoi… more
Date: August 28, 1961
Creator: Gruber, W. J.
Partner: UNT Libraries Government Documents Department
open access

A PROGRAM OF RESEARCH AND CALCULATIONS OF RESONANCE ABSORPTION. Final Report

Description: A direct numerical integration of the integral equation for the average collision density in the absorber was previously suggested in a discussion of resonance absorption. The implementation of this program is considered. The method of calculation, comparison with experimental data, and the computer code developed are described. The method of integration, computation of cross sections, selection of mesh size, integration interval, outside correction, the Dancoff correction, and unresolved reson… more
Date: August 28, 1961
Creator: Nordheim, L.W.
Partner: UNT Libraries Government Documents Department
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