Abstract
Thick plate, unalloyed W was neutron irradiated in the High Flux Isotope Reactor (HFIR) at 550 °C to a fast fluence of 1.24 × 1025 n m-2 E > 0.1 MeV (∼0.24 dpa). Unirradiated and irradiated specimens of the material were high heat flux (HHF) tested in the Plasma Arc Lamp (PAL) facility. The PAL uses a high-power photon source to provide a broad and even heat distribution on the sample surface. To simulate on/off cycling of normal operating plasma, the samples were exposed to approximately 800 cycles at 4.73 MW m-2 absorbed heat flux (incident heat fluxes of 10.95 MW m-2). After PAL exposure, slight changes were observed on the surfaces of the samples with SEM. The samples showed some annealing in the near surface polished region, but they were all below the damage threshold for cracking or other destructive features. The PAL has a large parameter space for future testing. The use of the HFIR and PAL to sequentially expose neutron irradiated samples to HHF will be a powerful tool for understanding materials behavior in a fusion-like environment.
Original language | English |
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Article number | 014077 |
Journal | Physica Scripta |
Volume | 2020 |
Issue number | T171 |
DOIs | |
State | Published - Jan 1 2020 |
Event | 17th International Conference on Plasma-Facing Materials and Components for Fusion Applications, PFMC 2019 - Eindhoven, Netherlands Duration: May 20 2019 → May 24 2019 |
Funding
This manuscript has been authored in part by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE 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). The work was performed as a part of the US-Japan PHENIX Cooperation Project on Technological Assessment of Plasma Facing Components for DEMO Reactors, supported by the US Department of Energy, Office of Science, Fusion Energy Sciences and Ministry of Education, Culture, Sports, Science and Technology, Japan. This manuscript has been authored by UT-Battelle, LLC, under Contract No. DE-AC05-00OR22725 with the US DOE. This research used resources at the High Flux Isotope Reactor, a DOE Office of Science User Facility operated by ORNL.
Funders | Funder number |
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US Department of Energy | |
U.S. Department of Energy | |
Office of Science | |
Fusion Energy Sciences | |
Ministry of Education, Culture, Sports, Science and Technology |
Keywords
- fusion materials
- high heat flux
- neutron irradiation
- plasma facing component
- tungsten