Graphite corrosion in high-temperature reactors

Automatic translation: In the field of graphite corrosion in high-temperature reactors a great deal of knowledge is already available. In the very extensive literature on the topic mentioned However, almost exclusively the corrosion behavior during regular operating status of an HTR; that is against it Behavior under accident conditions is only partially known. The R&D program of the Institute for Nuclear Safety Research includes, among other things: the investigation of the safety behavior of HTR under extreme accident conditions. In this context In particular, accidents involving water and/or air intrusion are intended here in the primary system are addressed, as these relate to graphite corrosion are of particular importance. A literature search was carried out in order to gain precise knowledge of reaction-determining parameters to uncover any remaining knowledge gaps.