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Title: INL/JOU-17-41026-Rev000

Abstract

Graphite creep strain data from the irradiation creep capsule Advanced Graphite Creep-1 (AGC-1) are reported. This capsule was the first (prototype) of a series of five or six capsules planned as part of the AGC experiment, which was designed to fully characterize the effects of neutron irradiation and the radiation creep behavior of current nuclear graphite. The creep strain data and analysis are reported for the six graphite grades incorporated in the capsule. The AGC-1 capsule was irradiated in the Advanced Test Reactor at Idaho National Laboratory (INL) at approximately 700°C and to a peak dose of 7 dpa (displacements per atom). The specimen’s final dose, temperature, and stress conditions have been reported by INL and were used during this analysis. The derived creep coefficients (K) were calculated for each grade and were found to compare well to literature data for the creep coefficient, even under the wide range of AGC-1 specimen temperatures. Comparisons were made between AGC-1 data and historical grade data for creep coefficients.

Authors:
 [1];  [2]
  1. Oak Ridge National Laboratory
  2. Idaho National Laboratory
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
work for others
OSTI Identifier:
1465814
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Conference: HTR 2016, Las Vegas, NV, 11/06/2016 - 11/06/2016
Country of Publication:
United States
Language:
English
Subject:
36 - MATERIALS SCIENCE; AGC; nuclear graphite; Irradiation; irradiation creep

Citation Formats

Burchell, Timothy D, and Windes, William E. INL/JOU-17-41026-Rev000. United States: N. p., 2018. Web.
Burchell, Timothy D, & Windes, William E. INL/JOU-17-41026-Rev000. United States.
Burchell, Timothy D, and Windes, William E. Wed . "INL/JOU-17-41026-Rev000". United States. https://www.osti.gov/servlets/purl/1465814.
@article{osti_1465814,
title = {INL/JOU-17-41026-Rev000},
author = {Burchell, Timothy D and Windes, William E},
abstractNote = {Graphite creep strain data from the irradiation creep capsule Advanced Graphite Creep-1 (AGC-1) are reported. This capsule was the first (prototype) of a series of five or six capsules planned as part of the AGC experiment, which was designed to fully characterize the effects of neutron irradiation and the radiation creep behavior of current nuclear graphite. The creep strain data and analysis are reported for the six graphite grades incorporated in the capsule. The AGC-1 capsule was irradiated in the Advanced Test Reactor at Idaho National Laboratory (INL) at approximately 700°C and to a peak dose of 7 dpa (displacements per atom). The specimen’s final dose, temperature, and stress conditions have been reported by INL and were used during this analysis. The derived creep coefficients (K) were calculated for each grade and were found to compare well to literature data for the creep coefficient, even under the wide range of AGC-1 specimen temperatures. Comparisons were made between AGC-1 data and historical grade data for creep coefficients.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {8}
}

Conference:
Other availability
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