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THE DEVELOPMENT AND EVALUATION OF GRAPHITE-MATRIX FUEL COMPACTS FOR THE HTGR.

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Published: 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.).

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

Author: Walter V. Goeddel

Publisher:

Published: 1961

Total Pages: 106

ISBN-13:

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Development and Evaluation of B4C-graphite Control-rod Materials for the HTGR

Author: W. V. Goeddel

Publisher:

Published: 1962

Total Pages: 28

ISBN-13:

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The High-temperature Gas-cooled Reactor (HTGR) is a helium-cooled, graphite-moderated, solid-homogeneous fueled type of reactor, in which the high-temperature potentialities of gas cooling with high power density are combined with a fuel capable of high burnup. The HTGR prototype plant is being designed to produce 1000°F steam at 1450 psi and to have a net capacity of 40 Mw(e). A summary of the development and evaluation of graphite-matrix fuel compacts for the HTGR has been presented in earlier publications. This report describes the development and evaluation of the boron-carbide-graphite control-rod material for the HTGR.