117. High temperature radiation induced creep in graphite

Blackstone, R.; Graham, L.W.; Everett, M.R.

doi:10.1016/0008-6223(69)90646-0

Cited by 2 publications

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“…In general, AGC-2 creep coefficients agree remarkably well with the AGC-1 coefficients even with the large temperature variations between AGC-1 specimens. AGC-2 creep coefficients are compared to previous values calculated from historical creep studies 37,38,39,40,41,42,43,44,45 (Figure 27). This comparison demonstrates the AGC-2 creep coefficients are well within the historical values determined for the irradiation temperatures and dose levels of the AGC-2 test train.…”

Section: Creep and Creep Coefficient Analysis By Gradementioning

confidence: 99%

AGC-3 Irradiation Creep Strain Data Analysis

Windes

Rohrbaugh

Swank

2019

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This report documents the analysis of the creep strain data from the Advanced Graphite Creep (AGC)-2 graphite creep specimens. This is the second of a series of six irradiation test trains planned as part of the AGC experiment to fully characterize the neutron irradiation effects and radiation creep behavior of current nuclear graphite grades. The AGC-2 capsule was irradiated in the Idaho National Laboratory Advanced Test Reactor at a nominal temperature of 600°C, beginning with irradiation Cycle 149A on April 12, 2011 and ending with Cycle 151B on May 5, 2012, with a total received dose range of 1.3-4.7 dpa.AGC-2 was designed to provide irradiation conditions similar to AGC-1 (i.e, the same graphite grades, a nominal irradiation temperature of 600°C, and the same applied mechanical stress levels) but was irradiated for a shorter period of time to provide material property values for the graphite samples at lower dose levels than achieved in AGC-1. Material property and dimensional strain measurements were conducted on specimens from 15 nuclear graphite grades using a similar specimen assembly configuration as the first AGC capsule (AGC-1) to provide easy comparison between the two capsules. However, AGC-2 contained an increased number of specimens (i.e., 487 total specimens irradiated) and replaced specimens of the minor grade 2020 with the newer grade 2114.Significant modifications were made to the AGC-2 irradiation capsule to improve the specimen temperature issues that were encountered with AGC-1. While the AGC-2 irradiation temperature range (399-704°C) was much narrower than AGC-1 the range is still considered less than optimal. The centrally located creep specimens (specimens under an applied mechanical stress of 13.8, 17.2, or 20.7 MPa) and control specimens (specimens with no applied stress) were irradiated over even a narrower temperature range of 541-681°C with dose levels from 2.0-4.7 dpa.The data reported include specimen dimensions and hence the dimensional strain change upon irradiation. This allowed a comparison of these data for specimen-matched pairs yielding the dimensional and volumetric creep strain. The AGC-2 creep strain analysis methodology is similar to the AGC-1 analysis and the irradiation strain results from both capsules compare well for all grades. The derived creep coefficients have been calculated for each grade and are found to compare well to literature data, despite the larger than desired spread in specimen temperatures.

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