The Development and Evaluation of Graphite-Matrix Fuel Compacts for the HTGR

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>A summary of development and evaluation of graphitematrix fuel compacts for the high-temperature gas-cooled reactor is presented. The fuel compacts consist of Th-- U dicarbide particles dispersed in a high-density graphite matrix and are produced by a hot-pressing process. Compacts prepared from Th--U oxide, Th-- U silicide, and Th--U dicarbide coated with pyrolytic C were subjected to radiation and fission-product-retention testing. Results of these tests are included and are discussed in detail. (J.R.D.)

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103 pages

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Goeddel, Walter V. August 1961.

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>A summary of development and evaluation of graphitematrix fuel compacts for the high-temperature gas-cooled reactor is presented. The fuel compacts consist of Th-- U dicarbide particles dispersed in a high-density graphite matrix and are produced by a hot-pressing process. Compacts prepared from Th--U oxide, Th-- U silicide, and Th--U dicarbide coated with pyrolytic C were subjected to radiation and fission-product-retention testing. Results of these tests are included and are discussed in detail. (J.R.D.)

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103 pages

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Other Information: Orig. Receipt Date: 31-DEC-62

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Office of Scientific & Technical Information Technical Reports

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  • August 1961

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  • Jan. 22, 2018, 7:23 a.m.

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  • Nov. 23, 2024, 2:38 a.m.

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Goeddel, Walter V. The Development and Evaluation of Graphite-Matrix Fuel Compacts for the HTGR, report, August 1961; San Diego, California. (https://digital.library.unt.edu/ark:/67531/metadc1059342/: accessed May 22, 2025), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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