Open AccessH-451 graphite irradiation creep design model; Revision 1
Publication year - 1988
Language(s) - English
Resource type - Reports
DOI - 10.2172/714683
Subject(s) - nuclear engineering , graphite , quality assurance , creep , component (thermodynamics) , nuclear reactor , materials science , structural material , nuclear material , mechanical engineering , structural engineering , engineering , nuclear physics , composite material , physics , external quality assessment , thermodynamics , operations management
Available irradiation creep data on H-451 graphite area analyzed and fitted to the proposed creep model in a standard linear solid (a linear viscoelastic model). A creep equation is obtained and recommended for preliminary design use. It is found that the regression is significant and the creep equation is a good predictor. The standard error (SE) of the estimate is smaller than that used in the core graphite criteria development. This smaller SE shall be used in all future work related to criteria development. The creep coefficient and/or model can be further improved if additional creep data can be obtained. For this purpose several creep experiments are recommended. The immediate one is to capsule 87M-2A currently under design