86. Properties of graphitic materials for spherical fuel elements for HTGR and results of neutron exposure

✍ Scribed by W.W. Delle; R.E. Schulze; B. Heinrich; A. Kleine-Tebbe; W. Heit; W. Rind

• Publisher: Elsevier Science
• Year: 1976
• Tongue: English
• Weight: 149 KB
• Volume: 14
• Category: Article
• ISSN: 0008-6223
• DOI: 10.1016/0008-6223(76)90219-0

✦ Synopsis

Abstracts 301 and the critical crack length of several glassy carbons were determined. 78. The irradiation induced in graphites H.T.R. applications Veringa (Reactor Centrum Nederland, Petten, The Netherlands). Over the past three years, a large series of radiation creep experiements on a variety of nuclear graphites utilizing the restrained shrinkage method have been performed in the H.F.R. at Petten, The Netherlands, in the framework of the cooperative Dragon-K.F.A.-R.C.N. graphite irradiations. The interpretation of the experimental results, as well as a description of the creep process by a basal plan dislocation pinning-unpinning model, have shown that the Young's modulus, the irradiation temperature and the neutron flux density are important factors determining the radiation creep coefficient. In this paper the most likely models to explain creep will be outlined breifly and our experimental results in comparison with other results will be summarized. 79. Fast neutron irradiation of carbon carbon composites E. J. Walker, L. Pain and P. B. Roscoe (MOD(PE),