Report on Effects of Irradiation on Material IG-110 - Prepared for Toyo Tanso Co., Ltd.
This joint program between Oak Ridge National Laboratory (ORNL) and Toyo Tanso Co., Ltd., began in 2010 with the final objective being the creation of qualification data of graphite grade IG-110 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-Toyo Tanso Japan ” [1]. The second segment of this program included the irradiation of the graphite and the measurement of the changes to a set of pre-defined physical, mechanical, and thermal properties. The third segment of this program studies the irradiation-induced creep due to an applied compression stress.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 1483188
- Report Number(s):
- ORNL/TM-2017/705
- Country of Publication:
- United States
- Language:
- English
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