Effects of Irradiation on Material G347A: Prepared for Tokai Carbon Co., Ltd. (Final Report)

This joint program between Oak Ridge National Laboratory (ORNL) and Tokai Carbon Co., Ltd., began in 2009 with the final objective being the preliminary qualification of graphite grade G347A as a candidate material for use in the Generation-IV high temperature gas-cooled nuclear reactor (HTGR). The first segment of this program involved the planning and design of the irradiation program, and the investigation of the feasibility of using specimens smaller than recommended in the pertinent American Society for Testing and Materials (ASTM) International test standards. The results from the first segment were provided to the program sponsor in the document titled “Graphite Pre-Irradiation Specimen Size Validation and Testing Program – Results – Tokai Carbon Japan” [1]. The second segment of this program included the irradiation of the graphite and the measurement of the changes to a set of predefined physical, mechanical, and thermal properties.