Surface morphology of Tungsten-F82H after high-heat flux testing using plasma-arc lamps

K. Ibano, A. S. Sabau, K. Tokunaga, M. Akiyoshi, J. O. Kiggans, C. R. Schaich, Y. Katoh, Y. Ueda

Research output: Contribution to journalArticlepeer-review

4 Scopus citations

Abstract

F82H reduced activation steel coated with vacuum plasma sprayed (VPS) tungsten is a candidate as a plasma facing material for main chamber components in future fusion reactors. Due to different coefficients of thermal expansion (CTE), significant thermal stresses are expected in these bimetallic materials. Thus, a major uncertainty in the performance of W/F82H components during the operation under high-heat fluxes is the effect of CTE mismatch. In this study, a high intensity plasma-arc lamp was used for high-heat flux cycling tests of W/F82H specimens. While no surface damage was observed for specimens tested for 100–200 cycles at a heat flux of 1.4 MW/m2 pulse when the backside surface temperature was maintained below 550 °C, significant cracking occurred at higher temperatures. A simple analytical model for bimetallic materials indicated that the stress in the VPS-W layer is likely to exceed its failure stress solely due to the bilayer thermal stress. A finite element analysis of the state of stress and deformation confirmed that a significant stress also would occur at the W surface due to the rigid-body like constraint imposed by the clamp, which can be the main cause of the cracking.

Original languageEnglish
Pages (from-to)128-132
Number of pages5
JournalNuclear Materials and Energy
Volume16
DOIs
StatePublished - Aug 2018

Funding

Notice: This submission was sponsored by a contractor of the United States Government under contract DE-AC05-00OR22725 with the United States 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, world-wide 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 work was partly supported by Japan / U. S. Cooperation (PHENIX) in Fusion Research and Development. Research sponsored by the Office of Fusion Energy Sciences, U.S. Department of Energy , under contract DE-AC05-00OR22725 with UT-Battelle, LLC and “Technological Assessment of Plasma Facing Components for DEMO Reactors” Japan/U.S.A. Fusion Research joint project.

FundersFunder number
PHENIX
U. S. Cooperation
U.S. Department of EnergyDE-AC05-00OR22725
Fusion Energy Sciences
Japan Society for the Promotion of Science17H01367

    Keywords

    • Bimetallic
    • High-heat flux testing
    • Reduced activation steel
    • Thermal stress
    • Tungsten

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