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

Technical Report · Tue Dec 01 04:00:00 EST 2015

DOI:https://doi.org/10.2172/2301667· OSTI ID:2301667

Campbell, Anne A. ^[1]; Kato, Yutai ^[1]; Snead, Mary A. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

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.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 2301667
• Report Number(s): ORNL/TM--2015/665
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE