HTGR Knowledge Base

Conference Article: The statistical characterization of tensile strengths for a nuclear-type graphite

Kennedy, C.R.; Eatherly, W.P. (Oak Ridge National Lab., TN (USA))

Abstract

A data set of tensile strengths comprising over 1200 experimental points has been analyzed statistically in conformance with the observed phenomenon of background and disparate flaws. The data are consistent with a bimodal normal distribution. If corrections are made for strength dependence on density, the background mode is Weibull. It is proposed the disparate mode can be represented by a combination of binomial and order statistics. The resultant bimodal model would show a strong dependence on stress volume.

view the full text of this article (6 pages, format: PDF, size= 380kB)

key words: brittleness; defects; flexural strength; graphite; htgr type reactors; reactor cores; statistics; tensile properties; carbon; elements; gas cooled reactors; graphite moderated reactors; mathematics; mechanical properties; reactor components
Reference:
Specialists' meeting on graphite component structural design, JAERI Tokai (Japan), September 8-11, 1986
International Atomic Energy Agency, Vienna (Austria). International Working Group on Gas-Cooled Reactors
IWGGCR--11, pp:63-68