Self-heating of irradiated graphite in nuclear reactor

V.Ogorodnikov
 

I. M. Frantsevich Institute for Problems of Materials Science of the NAS of Ukraine, Krzhizhanovsky str., 3, Kyiv, 03142, Ukraine
Mathematical Models and Computing Experiment in Material Science - Kiev: Frantsevich Institute for Problems of Materials Science NASU, 2012, #14
http://www.materials.kiev.ua/article/608

Abstract

Detailed calculations of thermal effects in irradiated graphite are carried out. The characteristics of radiation-induced defects — the activation energy and thermal stability threshold — are determined. The kinetic equations of accumulation and annealing of defects, the release of stored Wigner energy and the self-heating of the irradiated graphite are solved and calculated. The effective heat capacity of irradiated graphite is determined and a comparison of heating of the irradiated and unirradiated graphite under identical heat input is made. Temperature intervals of lightweight heat and self-heating of gra-phite are defined. An expression for temperature-doze dependence of stored energy in graphite during irradiation in a reactor is obtained.


GRAPHITE, IRRADIATION, NUCLEAR REACTOR, RADIATION DEFECTS, SELF-HEATING, TEMPERATURE EFFECTS COMPUTATION, WIGNER ENERGY