Preliminary design of a graphite irradiation tensile creep experiment in the target region of the high flux isotope reactor

J. L. McDuffee, T. D. Burchell, D. W. Heatherly, K. R. Thoms

Research output: Contribution to journalArticlepeer-review

5 Scopus citations

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 languageEnglish
Pages (from-to)119-123
Number of pages5
JournalJournal of Nuclear Materials
Volume381
Issue number1-2
DOIs
StatePublished - Oct 31 2008
Externally publishedYes

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.

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