Abstract
Constraint loss adjustments, based on finite element (FE) stress analysis and local critical stress, σ*, critical stressed volume, V*, cleavage criteria were applied to fracture toughness data from small pre-cracked bend bars of the IEA heat of F82H irradiated to 6.6 dpa at 300 °C in the High Flux Isotope Reactor. The 100 MPa√m master curve method reference temperature shifts were evaluated based on both the measured toughness (ΔTm) and after size-adjusting the toughness to small-scale yielding conditions at reference specimen size (ΔTo) with values of ≈142 and 205 °C, respectively. The model based prediction ΔTo = CoΔσfl〉, where Co ≈ 0.68 and Δσfl〉 is the change in the average flow stress over 0-10% strain is in excellent agreement with ΔTo. The FE analyses also demonstrates an upper-bound K Jc that can be measured with these small bend bars for irradiated alloys that suffer severe loss of strain hardening.
Original language | English |
---|---|
Pages (from-to) | 115-119 |
Number of pages | 5 |
Journal | Journal of Nuclear Materials |
Volume | 417 |
Issue number | 1-3 |
DOIs | |
State | Published - Oct 1 2011 |
Funding
Experimental data used in this study were obtained in collaboration with Oak Ridge National Laboratory, Pacific Northwest National Laboratory and Japan Atomic Energy Agency. The authors are grateful to Drs. Steve Zinkle, Roger Stoller, Shiro Jitsukawa, Hiroyasu Tanigawa and other researchers involved in the US-JAEA collaboration. The research performed at University of California, Santa Barbara was supported by the US Department of Energy, Office of Fusion Science Grant #DE-FG03-94ER54275.
Funders | Funder number |
---|---|
Office of Fusion Science | -FG03-94ER54275 |
US Department of Energy | |
University of California, Santa Barbara |