Download or read book Development and Evaluation of B4C-graphite Control-rod Materials for the HTGR written by W. V. Goeddel and published by . This book was released on 1962 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.