Preliminary design of a graphite irradiation tensile creep experiment in the target region of the high flux isotope reactor
Source abstract
Abstract
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).
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Graphite, nuclear technology, radiation studies · Nuclear reactor physics and engineering · Nuclear Materials and Properties
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References (4)
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3. B.T. Kelly, A Feasibility Study for an Irradiation Creep Experiment on AGR Moderator Graphite, AEA Thermal Reactor Services, AEA TRA 5083, March 1991.
4. J.A. Vreeling et al., in: Sixth International Nuclear Graphite Specialists Meeting, Chamonix, September 2005.