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Title: AGC 2 Irradiated Material Properties Analysis

Abstract

The Advanced Reactor Technologies Graphite Research and Development Program is conducting an extensive graphite irradiation experiment to provide data for licensing of a high temperature reactor (HTR) design. In past applications, graphite has been used effectively as a structural and moderator material in both research and commercial high temperature gas cooled reactor designs. , Nuclear graphite H 451, used previously in the United States for nuclear reactor graphite components, is no longer available. New nuclear graphite grades have been developed and are considered suitable candidates for new HTR reactor designs. To support the design and licensing of HTR core components within a commercial reactor, a complete properties database must be developed for these current grades of graphite. Quantitative data on in service material performance are required for the physical, mechanical, and thermal properties of each graphite grade, with a specific emphasis on data accounting for the life limiting effects of irradiation creep on key physical properties of the HTR candidate graphite grades. Further details on the research and development activities and associated rationale required to qualify nuclear grade graphite for use within the HTR are documented in the graphite technology research and development plan.

Authors:
 [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1369362
Report Number(s):
INL/EXT-17-41165
TRN: US1701969
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; GRAPHITE; REACTOR DESIGN; HTR REACTOR; THERMODYNAMIC PROPERTIES; HTGR TYPE REACTORS; IRRADIATION; REACTOR TECHNOLOGY; Advanced Graphite Creep; high temperature reactor; post irradiation examination

Citation Formats

Rohrbaugh, David Thomas. AGC 2 Irradiated Material Properties Analysis. United States: N. p., 2017. Web. doi:10.2172/1369362.
Rohrbaugh, David Thomas. AGC 2 Irradiated Material Properties Analysis. United States. doi:10.2172/1369362.
Rohrbaugh, David Thomas. Mon . "AGC 2 Irradiated Material Properties Analysis". United States. doi:10.2172/1369362. https://www.osti.gov/servlets/purl/1369362.
@article{osti_1369362,
title = {AGC 2 Irradiated Material Properties Analysis},
author = {Rohrbaugh, David Thomas},
abstractNote = {The Advanced Reactor Technologies Graphite Research and Development Program is conducting an extensive graphite irradiation experiment to provide data for licensing of a high temperature reactor (HTR) design. In past applications, graphite has been used effectively as a structural and moderator material in both research and commercial high temperature gas cooled reactor designs. , Nuclear graphite H 451, used previously in the United States for nuclear reactor graphite components, is no longer available. New nuclear graphite grades have been developed and are considered suitable candidates for new HTR reactor designs. To support the design and licensing of HTR core components within a commercial reactor, a complete properties database must be developed for these current grades of graphite. Quantitative data on in service material performance are required for the physical, mechanical, and thermal properties of each graphite grade, with a specific emphasis on data accounting for the life limiting effects of irradiation creep on key physical properties of the HTR candidate graphite grades. Further details on the research and development activities and associated rationale required to qualify nuclear grade graphite for use within the HTR are documented in the graphite technology research and development plan.},
doi = {10.2172/1369362},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon May 01 00:00:00 EDT 2017},
month = {Mon May 01 00:00:00 EDT 2017}
}

Technical Report:

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