Abstract
Ten Eurofer97 steel variants, produced by non-standard fabrication-processing routes and modified alloying chemistries, were studied by neutron irradiations in the high flux isotope reactor. The irradiations were performed to ITER-TBM relevant conditions of ∼255–350 °C, 2.94–3.24 dpa. We quantified the irradiation-induced degradation of the steels using mechanical property tests. All the steels suffered from irradiation hardening, where a significant increase in Vickers microhardness and yield stress (σYS) occurred, accompanied with severe loss of tensile elongation. The extent of hardening was material dependent. For Tirr = 300±30 °C, most steels showed σYS increase in the range of ∼30% to as high as ∼66%, except for a low temperature tempered steel with σYS increase below 15%. Despite large losses in elongation, most failures were ductile. Significant post-necking ductility was retained with reduction in area (RA) between 65–75%, but <50% for low temperature tempered steels. The ultimate tensile stress to yield stress (σUTS/σYS) ratios decreased significantly after irradiation, highlighting irradiation-induced strain hardening capacity reduction. No major effect of irradiation on the plastic instability stress (σPIS) and true fracture stress of the steels was observed. By comparing the tensile stresses in true stress units and with literature, the results suggest that RAFM steel designing should target materials with a large separation between σPIS and σYS, to ensure the materials can maintain large work hardening and uniform deformation capability after irradiation. The tensile data of the steels additionally revealed a compelling evidence of an inverse trend between the change in RA and increase in σYS of the neutron irradiated Eurofer97 type steels.
Original language | English |
---|---|
Article number | 112935 |
Journal | Fusion Engineering and Design |
Volume | 173 |
DOIs | |
State | Published - Dec 2021 |
Funding
This study was supported by the U.S. Department of Energy , Office of Fusion Energy Sciences under contract DE-AC05- 00OR22725 and Karlsruhe Institute of Technology under contract NFE-16–06240 with ORNL managed by UT Battelle, LLC. A portion of this research at ORNL's High Flux Isotope Reactor was sponsored by the Scientific User Facilities Division, Office of Basic Energy Sciences, US Department of Energy. This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training program 2014–2018 and 2019–2020 under grant agreement No. 633,053. The views and opinions expressed herein do not necessarily reflect those of the European Commission. Note: This manuscript has been authored by UT-Battelle, LLC under Contract No. DE-AC05?00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).This study was supported by the U.S. Department of Energy, Office of Fusion Energy Sciences under contract DE-AC05- 00OR22725 and Karlsruhe Institute of Technology under contract NFE-16?06240 with ORNL managed by UT Battelle, LLC. A portion of this research at ORNL's High Flux Isotope Reactor was sponsored by the Scientific User Facilities Division, Office of Basic Energy Sciences, US Department of Energy. This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training program 2014?2018 and 2019?2020 under grant agreement No. 633,053. The views and opinions expressed herein do not necessarily reflect those of the European Commission.
Funders | Funder number |
---|---|
DOE Public Access Plan | |
Scientific User Facilities Division | |
United States Government | |
U.S. Department of Energy | |
Basic Energy Sciences | |
Fusion Energy Sciences | DE-AC05- 00OR22725 |
Karlsruhe Institute of Technology | NFE-16–06240 |
H2020 Euratom | 633,053 |
UT-Battelle |
Keywords
- Eurofer97 steel
- Irradiation-hardening
- Neutron irradiation
- Reduction in area
- Tensile properties
- fracture