Open AccessUse of tungsten material for the ITER divertor
Author(s) -
Takeshi Hirai,
S. Panayotis,
V. Barabash,
C. Amzallag,
F. Escourbiac,
A. Durocher,
M. Merola,
J. Linke,
Th. Loewenhoff,
G. Pintsuk,
M. Wirtz,
I. Uytdenhouwen
Publication year - 2016
Publication title -
nuclear materials and energy
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 1.324
H-Index - 25
ISSN - 2352-1791
DOI - 10.1016/j.nme.2016.07.003
Subject(s) - divertor , tungsten , materials science , high heat , creep , nuclear engineering , recrystallization (geology) , heat sink , armour , composite material , metallurgy , plasma , tokamak , nuclear physics , mechanical engineering , geology , engineering , physics , paleontology , layer (electronics)
ince the ITER divertor design includes tungsten monoblocks in the vertical target where heat loads are maximal, the design to protect leading edges as well as technology R&D for high performance armor-heat sink joint were necessary to be implemented. In the R&D, the availability of the technology was demonstrated by high heat flux test of tungsten monoblock components. Not systematically but frequently macro-cracks appeared at the middle of monoblocks after 20MW/m2 loading. The initiation of such macro-cracks was considered to be due to cyclic exposure to high temperature, ∼2000°C, where creep, recrystallization and low cycle fatigue were concerned. To understand correlation between the macro-crack appearance and mechanical properties and possible update of acceptance criteria in the material specification, an activity to characterize the tungsten monoblocks was launched
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