Abstract
Up to four irradiation tensile creep tests are planned for the target region of the high flux isotope reactor on two graphite grades: PCEA and NBG-18. The initial experiment is designed for an irradiation temperature of 600 °C and at fluences between 1 × 1022 n/cm2 and 1.4 × 1022 n/cm2 (E > 50 keV).
Original language | English |
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Pages (from-to) | 119-123 |
Number of pages | 5 |
Journal | Journal of Nuclear Materials |
Volume | 381 |
Issue number | 1-2 |
DOIs | |
State | Published - Oct 31 2008 |
Externally published | Yes |
Funding
This work is sponsored by the U.S. Department of Energy, Office of Nuclear Energy Science and Technology under contract DE-AC05-00OR22725 with Oak Ridge National Laboratory, managed by UT-Battelle, LLC.