Next generation nuclear reactors (graphite moderated) affected by creep of graphite, because it is design for very long time period. Could someone please explain this to me or recommend literature?
"Graphite is a widely used material in nuclear reactors, especially in high temperature gas-cooled reactors (HTRs), in which it plays three main roles: moderator, reflector and structure material. Irradiation induced creep has a significant impact on the behavior of nuclear graphite as graphite is used in high temperature and neutron irradiation environments. Thus the creep coefficient becomes a key factor in stress analysis and lifetime prediction of nuclear graphite"
the above is an excerpt from the abstract; The various creep models for irradiation behavior of nuclear graphite by Xiang Fanga, Haitao Wanga, Suyuan Yua,∗, Chenfeng Li.The journal is attached below. I sure hope it helps.