Development and Evaluation of B4C-graphite Control-rod Materials for the HTGR
Author: W. V. Goeddel
Publisher:
Published: 1962
Total Pages: 28
ISBN-13:
DOWNLOAD EBOOKThe 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.