Report on Effects of Irradiation on Material IG-110 - Prepared for Toyo Tanso Co., Ltd.

Research output: Book/ReportCommissioned report

Abstract

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.
Original languageEnglish
Place of PublicationUnited States
DOIs
StatePublished - 2017

Keywords

  • 36 MATERIALS SCIENCE

Fingerprint

Dive into the research topics of 'Report on Effects of Irradiation on Material IG-110 - Prepared for Toyo Tanso Co., Ltd.'. Together they form a unique fingerprint.

Cite this