Effect of gas atoms and displacement damage on mechanical properties and microstructures of F82H

A review of helium–hydrogen synergistic effects in radiation damage observed in fusion energy steels and an interaction model to guide future understanding

“…We remark in passing that the authors report a peak in the swelling curve at 430°C for the dual beam irradiation [20]. As we noted earlier, the width of the swelling curve for the triple beam irradiation study of Fe-12%Cr was $130°C.…”

“…There are some data reported by the TIARA group that indicates that the hydrogen has a synergistic effect on mechanical properties under triple beam irradiation conditions when compared with single beam (Fe ions to produce dpa) and dual beams (Fe + He) [20]. In Fig.…”

“…It is worthwhile to consider the series of MSIB triple beam experiments led by Eiichi Wakai that were reported over the period from 2003 to 2009 making use of the Tagasaki TIARA MSIB triple beam facility at the JAEA laboratory at Tokai in Japan [15][16][17][18][19][20]. While a complete review of these experiments is beyond the scope of this paper, a summary that highlights some of the important results can serve as a pedagogical outline for future experiments and as a motivation for future computational modeling of the helium and hydrogen synergy in the presence of atomic displacements.…”

Design plan and requirement of test module and testing items in IFMIF

“…Radiation damage of materials in a fusion reactor environment can be characterized by synergistic effects of displacement damage and nuclear transmutation products such as hydrogen and helium atoms [1][2][3][4][5][6]. These damages will induce the degradation of mechanical properties.…”

“…In order to safely operate a fusion reactor, the detailed behavior of material degradation with respect to 14 MeV neutrons dose must be known. The IEA FPCC accepted at meetings in 1993 and 1994 the technical conclusions of the Karlsruhe Workshop and the proposal of the IEA Fusion Materials Executive Committee to start a Conceptual Design of The International Fusion Materials Irradiation Facility (IFMIF), based on the D-Li stripping reaction [4]. The role which an IFMIF neutron source will pay in materials development and testing can be described by the planned use in the following research areas: * Corresponding author at: Tokai-mura, Nakagun, Ibaraki-ken 319-1195, Japan.…”