Abstract
The HT9 ferritic/martensitic steel with a nominal chemistry of Fe(bal.)12%Cr1%MoVW has been used as a primary core material for fast fission reactors such as FFTF because of its high resistance to radiation-induced swelling and embrittlement. Both static and dynamic fracture test results have shown that the HT9 steel can become brittle when it is exposed to high dose irradiation at a relatively low temperature (<430 °C). This article aims at a comprehensive discussion on the thermal annealing recovery of fracture toughness in the HT9 steel after irradiation up to 3148 dpa at 378504 °C. A specimen reuse technique has been established and applied to this study: the fracture specimens were tested Charpy specimens or broken halves of Charpy bars (13 × 3 × 4 mm). The post-anneal fracture test results indicated that much of the radiation-induced damage can be recovered by a simple thermal annealing schedule: the fracture toughness was incompletely recovered by 550 °C annealing, while nearly complete or complete recovery occurred after 650 °C annealing. This indicates that thermal annealing is a feasible damage mitigation technique for the reactor components made of HT9 steel. The partial recovery is probably due to the non-removable microstructural damages such as void or gas bubble formation, elemental segregation and precipitation.
Original language | English |
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Pages (from-to) | 263-272 |
Number of pages | 10 |
Journal | Journal of Nuclear Materials |
Volume | 449 |
Issue number | 1-3 |
DOIs | |
State | Published - Jun 2014 |
Funding
This research was part of Fuel Cycle R&D Program/Core Materials sponsored by US Department of Energy, Office of Nuclear Energy under Contract DE-AC05-00OR22725 with UT-Battelle, LLC. The authors would like to express special thanks to Dr. R.K. Nanstad for his technical review and thoughtful comments.
Funders | Funder number |
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US Department of Energy | |
Office of Nuclear Energy | DE-AC05-00OR22725 |