In situ fatigue of the Eurofer 97 steel

Marmy, P.

doi:10.1016/j.jnucmat.2007.03.162

Cited by 7 publications

(5 citation statements)

References 9 publications

(14 reference statements)

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“…Alloy composition refinement has been an effective method to improve the performance the RAFM steels, such as the evolution of Eurofer 97 [9][10][11][12][13], and F82H [14][15][16][17][18]. More dramatic alloy composition adjustment has also been investi gated in CLAM steel.…”

Section: Chemical Composition Design and Fabrication Process Controlmentioning

confidence: 99%

Status and improvement of CLAM for nuclear application

Qunying

2017

Nucl. Fusion

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A program for China low activation martensitic steel (CLAM) development has been underway since 2001 to satisfy the material requirements of the test blanket module (TBM) for ITER, China fusion engineering test reactor and China fusion demonstration reactor. It has been undertaken by the Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences under wide domestic and international collaborations. Extensive work and efforts are being devoted to the R&D of CLAM, such as mechanical property evaluation before and after neutron irradiation, fabrication of scaled TBM by welding and additive manufacturing, improvement of its irradiation resistance as well as high temperature properties by precipitate strengthening to achieve its final successful application in fusion systems. The status and improvement of CLAM are introduced in this paper.

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Section: Chemical Composition Design and Fabrication Process Controlmentioning

confidence: 99%

Status and improvement of CLAM for nuclear application

Qunying

2017

Nucl. Fusion

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“…[2][3][4][5][6] Available data concerning fatigue at high temperatures where helium embrittlement may occur are still insufficient for those steels in spite of increasing research activities in the lower temperature range. [7][8][9][10] The present report covers tests with a concentration of 100 appmHe, which is roughly an order of magnitude lower than the maximum accumulation in the power reactor. The work will be extended to 1000 appmHe experiments.…”

Section: )mentioning

confidence: 99%

Fatigue Properties of Helium Injected F82H-IEA Heat Material

2009

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In order to contribute to the development of first wall/blanket structural materials in nuclear fusion reactors, we have assessed the influence of nuclear-transmutational helium, which is widely known to often induce grain boundary embrittlement at high temperatures, on fatigue properties of a candidate reduced-activation martensitic steel, IEA (International Energy Agency) version of F82H (Fe-8%Cr-2%W-0.2%V-0.04%Ta). Utilizing -particles from an accelerator, helium was introduced into specimens at 823 K to a concentration of about 100 appmHe. Through the subsequent fatigue tests at the same temperature, it has been demonstrated that both fatigue life and gauge extension to failure were not significantly deteriorated by helium. The appearance of fracture surfaces remained perfectly ductile and transgranular after helium implantation and no indication of grain boundary decohesion was detected. These results would reflect prominent resistance to the heliumembrittlement in this kind of steel and suggests their potential for future fusion applications.

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“…On the other hand, some results [48][49][50][51] seem to indicate that fatigue life can be considerably shorter than that of post-irradiated specimens when fatigue is imposed concurrently with irradiation. Post-irradiation experiments do not consider the fact that the microstructure of the material is changing during fatigue as well as during irradiation.…”

Section: Effects Of Irradiation On Fatigue Behaviourmentioning

confidence: 99%