Advanced, graphite-matrix, dispersion-type fuel systems. First annual report, April 1, 1962--March 31, 1963

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Declassified 4 Sep 1973. A hot-working device for compression of graphite bodies was used to deform cylindrical specimens of matrix graphite containing ZrC or UC-ZrC particles to strains of the order of 30% at temperatures of 2400 to 2900 deg C. The graphite bodies containing ZrC particles (chosen as representative carbide particles) were found to be more plastic near 2500 deg C than similar bodies containing no carbide particles. Microradiographic techniques were used to determine diffusion coefficients of U and Th on actual coated particles by nondestructive means. A tentative energy of activation for the migration of uranium from UC/sub ... continued below

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Pages: 42

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Goeddel, W.V.; Sandefur, N.L. & White, J.L. May 1, 1963.

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Description

Declassified 4 Sep 1973. A hot-working device for compression of graphite bodies was used to deform cylindrical specimens of matrix graphite containing ZrC or UC-ZrC particles to strains of the order of 30% at temperatures of 2400 to 2900 deg C. The graphite bodies containing ZrC particles (chosen as representative carbide particles) were found to be more plastic near 2500 deg C than similar bodies containing no carbide particles. Microradiographic techniques were used to determine diffusion coefficients of U and Th on actual coated particles by nondestructive means. A tentative energy of activation for the migration of uranium from UC/sub 2/ particles into PyC coatings was determined over the temperature range 1850 to 2300 deg C. The penetration of U into the coatings is not uniform but occurs radially in localized positions, and then spreads circumferentially, creating a banded structure. These results show the importance of the structure of PyC in regard to the diffusion of both fuel and fission-product materials. It was also observed that the diffusion of U is considerably more rapid in the direction parallel to the layer planes in the PyC than it is in the perpendicular direction. Tests with PyC-coated (U, Zr)C particles in graphite-matrix compacts showed that the addition of Zr to the uranium carbide greatly improves the thermal stability. In general, the coatings on these particles retained their integrity for several hours at 2300 and 2500 deg C. (29 figs) (DLC)

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Pages: 42

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Dep. NTIS

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  • Other Information: Declassified 4 Sep 1973. Orig. Receipt Date: 30-JUN-74

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  • Report No.: GA--4022(Pt.2)
  • Grant Number: AT(04-3)-167
  • DOI: 10.2172/4310927 | External Link
  • Office of Scientific & Technical Information Report Number: 4310927
  • Archival Resource Key: ark:/67531/metadc1020034

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • May 1, 1963

Added to The UNT Digital Library

  • Oct. 15, 2017, 10:09 p.m.

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  • Oct. 19, 2017, 12:35 p.m.

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Goeddel, W.V.; Sandefur, N.L. & White, J.L. Advanced, graphite-matrix, dispersion-type fuel systems. First annual report, April 1, 1962--March 31, 1963, report, May 1, 1963; United States. (digital.library.unt.edu/ark:/67531/metadc1020034/: accessed January 16, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.