Erosion and morphology changes of F82H steel under simultaneous hydrogen and helium irradiation

Yakushiji, Kazuyuki; Lee, H.T.; Oya, Masakazu; Tokitani, M.; Sagara, A.; Hamaji, Y.; Uenishi, Koji; Ibano, Kenzo; Ueda, Y.

doi:10.1016/j.fusengdes.2017.03.045

Cited by 6 publications

(5 citation statements)

References 4 publications

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“…A Tandem Accelerator of 1 MeV terminal voltage, which is capable of producing H and He ions, has been used for surface analyses such as RBS (Rutherford Backscattering Spectrometry), ERD (Elastic Recoil Detection), and PIXE (Particle Induced X-ray Emission). An example of the results was reported for surface W layer analysis of ion irradiated RAFM by RBS 33 . Some other general materials test facilities are available in NIFS.…”

Section: Ii-b Major Fusion Engineering Facilities In Nifs and Their C...mentioning

confidence: 99%

“…High Heat Flux Test (ACT2) 30 Ion Beam Surface Analysis 33 High heat flux test of W/Cu-alloy joints 31 Properties of re-solidified W 32 RBS for ion-implanted RAFM 33 Tritium Control of low level tritium…”

Section: Research Subjects Major Emphases Key Facilities In Nifs Exam...mentioning

confidence: 99%

“…78 High flux ion implantation facility (Osaka U.) 33 Tritium Tritium laboratory (U. Toyama/Kyushu U.) 84,87 Ion implantation and analysis (Shizuoka U.)…”

Section: Research Subjects Major Emphases Key Facilities In Nifs Exam...mentioning

confidence: 99%

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Overview of Fusion Engineering Research in Japan Focusing on Activities in NIFS and Universities

Muroga

Fukada

Hayashi

2019

Fusion Science and Technology

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This paper provides an overview of Japanese fusion engineering research activities focusing on those being carried out by NIFS and Japanese universities (Universities). NIFS is promoting the Fusion Engineering Research Project as one of the three research projects. The majority of the activity in the project is being carried out by collaboration with Universities. Utilizing core facilities installed in NIFS and the unique infrastructures of Universities, collaboration between NIFS and Universities is performed in superconducting magnet, liquid breeder blanket, advanced materials, high heat flux components, and tritium safety. NIFS also carries out international collaboration programs, such as Japan-China, Japan-USA, and IEA-based collaborations, promoting participation of University researchers. Responsibility division with QST, and contributions to ITER-BA and "Action Plan toward DEMO Development" are also reported.

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Section: Ii-b Major Fusion Engineering Facilities In Nifs and Their C...mentioning

confidence: 99%

Section: Research Subjects Major Emphases Key Facilities In Nifs Exam...mentioning

confidence: 99%

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Overview of Fusion Engineering Research in Japan Focusing on Activities in NIFS and Universities

Muroga

Fukada

Hayashi

2019

Fusion Science and Technology

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“…Previous studies have demonstrated that He ion exposure can result in various microstructures, such as blister [7], nanostructures [7,8], element enrichment [7][8][9] and bubbles [8,[10][11][12]. These microstructure changes not only degrade the mechanical properties but also affect the hydrogen isotope retention and permeation behavior.…”

Section: Introductionmentioning

confidence: 99%

The effect of He-induced surface microstructure on D plasma-driven permeation through RAFM steel

Wang¹,

Zhou²,

Liu³

et al. 2022

Nucl. Fusion

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The effect of helium (He)-induced surface microstructure on D plasma-driven permeation through a reduced activation ferritic/martensitic (RAFM) steel CLF-1 has been studied. The CLF-1 steel is pre-exposed by He plasma with ion fluence of 1022-1024 He m-2 and an incident energy of 100 eV at 708 K. The following D plasma driven permeation (PDP) experiment is performed at 693 K. Steady-state D permeation flux decreases with the increase of He ion fluence. D diffusion coefficient is found not to be significantly affected by He pre-damage, while D reflection coefficient increases with the enhance of He ion fluence. Scanning electron microscope (SEM) and transmission electron microscope (TEM) analyses clearly reveal the evolutions of surface roughness and the He bubbles layer after He exposures. Elastic recoil detection (ERD) is used to identify He concentration depth profiles in the samples. Both the surface microstructure modification and the He bubble layer formation contribute to the reduction of D permeation.

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“…Vanadium-based alloys have been developed for possible use in the structure of fusion power reactors because of their potential for low activation and their attractive high-temperature properties [ 1 ]. However, hydrogen (H) and helium (He) produced by nuclear transmutation reaction in fusion reactor would influence the microstructure and mechanical properties greatly [ 2 ]. On the basis of atom, He with low solubility affects greatly.…”

Section: Introductionmentioning

confidence: 99%

Effect of Annealing on Microstructures and Hardening of Helium-Hydrogen-Implanted Sequentially Vanadium Alloys

Jiang

Wang

2018

Nanoscale Res Lett

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The effect of post-irradiation annealing on the microstructures and mechanical properties of V-4Cr-4Ti alloys was studied. Helium-hydrogen-irradiated sequentially V-4Cr-4Ti alloys at room temperature (RT) were undergone post-irradiation annealing at 450 °C over periods of up to 30 h. These samples were carried out by high-resolution transmission electron microscopy (HRTEM) observation and nanoindentation test. With the holding time, large amounts of point defects produced during irradiation at RT accumulated into large dislocation loops and then dislocation nets which promoted the irradiation hardening. Meanwhile, bubbles appeared. As annealing time extended, these bubbles grew up and merged, and finally broke up. In the process, the size of bubbles increased and the number density decreased. Microstructural changes due to post-irradiation annealing corresponded to the change of hardening. Dislocations and bubbles are co-contributed to irradiation hardening. With the holding time up to 30 h, the recovery of hardening is not obvious. The phenomenon was discussed by dispersed barrier hardening model and Friedel-Kroupa-Hirsch relationship.

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Erosion and morphology changes of F82H steel under simultaneous hydrogen and helium irradiation

Cited by 6 publications

References 4 publications

Overview of Fusion Engineering Research in Japan Focusing on Activities in NIFS and Universities

Overview of Fusion Engineering Research in Japan Focusing on Activities in NIFS and Universities

The effect of He-induced surface microstructure on D plasma-driven permeation through RAFM steel

Effect of Annealing on Microstructures and Hardening of Helium-Hydrogen-Implanted Sequentially Vanadium Alloys

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