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

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].

Authors:
ORCiD logo [1]; ORCiD logo [1]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1483178
Report Number(s):
ORNL/TM-2018/1040
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English

Citation Formats

Campbell, Anne A., and Katoh, Yutai. Summary Report on Effects of Irradiation on Material IG-110 - Prepared for Toyo Tanso Co., Ltd.. United States: N. p., 2018. Web. doi:10.2172/1483178.
Campbell, Anne A., & Katoh, Yutai. Summary Report on Effects of Irradiation on Material IG-110 - Prepared for Toyo Tanso Co., Ltd.. United States. doi:10.2172/1483178.
Campbell, Anne A., and Katoh, Yutai. Thu . "Summary Report on Effects of Irradiation on Material IG-110 - Prepared for Toyo Tanso Co., Ltd.". United States. doi:10.2172/1483178. https://www.osti.gov/servlets/purl/1483178.
@article{osti_1483178,
title = {Summary Report on Effects of Irradiation on Material IG-110 - Prepared for Toyo Tanso Co., Ltd.},
author = {Campbell, Anne A. and Katoh, Yutai},
abstractNote = {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].},
doi = {10.2172/1483178},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {11}
}

Technical Report:

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