TY - GEN
T1 - A Comparison of the irradiation creep behavior of several graphites
AU - Burchell, Timothy D.
AU - Windes, William E.
PY - 2016
Y1 - 2016
N2 - 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.
AB - 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.
UR - http://www.scopus.com/inward/record.url?scp=85026329464&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:85026329464
T3 - International Topical Meeting on High Temperature Reactor Technology, HTR 2016
SP - 276
EP - 286
BT - International Topical Meeting on High Temperature Reactor Technology, HTR 2016
PB - American Nuclear Society
T2 - 8th International Topical Meeting on High Temperature Reactor Technology, HTR 2016
Y2 - 6 November 2016 through 10 November 2016
ER -