Creep rupture properties of helium implanted V–4Cr–4Ti alloy NIFS-HEAT-2

Chuto, Toshinori; Yamamoto, Norikazu; Nagakawa, Yuichi; Murase, Yoshiharu

doi:10.1016/j.jnucmat.2004.04.077

Cited by 6 publications

(5 citation statements)

References 10 publications

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“…While a standard protocol for screening the durability of metal membranes has not been established, various mechanical tests can be used to assess the effect of hydrogen on metal membranes. Such useful tests include the following: delayed failure tests, fracture mechanics, slow strain-rate tensile tests, , Charpy impact tests, , creep rupture tests, stress/strain controlled fatigue tests, , and disk-pressure or disk-burst tests. , The standard test for measuring hydrogen embrittlement in steel is the incremental step loading test, which determines the onset of subcritical crack growth on a tensile or 4 point bend sample after treatment in hydrogen (e.g. through processing such as plating) .…”

Section: Metal Membrane Materials and Methodsmentioning

confidence: 99%

Developments and Design of Novel (Non-Palladium-Based) Metal Membranes for Hydrogen Separation

Phair

Donelson

2006

Ind. Eng. Chem. Res.

144

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Hydrogen separation membrane devices are attracting increasing interest for the industrial production of hydrogen. Metal membranes, in particular, are promising due to their resilience to the demands of a typical hydrogen purification process. However, the use of too much Pd within the membranes limits their wide-scale industrial use due to excessive costs. The present article reviews the design, preparation, operation, and critical performance features of novel non-Pd-based alloys. The theory behind the permeation of hydrogen through metal membranes is presented as well as the materials and methods central to their design and improvement. Crystalline, amorphous, and thin layer metal membranes are contrasted, while the advanced experimental techniques and mechanical tests for their characterization are discussed. The review considers the design of novel metal membranes from first principles and assesses catalytic and protective surface layers which may enhance their hydrogen separation capabilities.

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Section: Metal Membrane Materials and Methodsmentioning

confidence: 99%

Developments and Design of Novel (Non-Palladium-Based) Metal Membranes for Hydrogen Separation

Phair

Donelson

2006

Ind. Eng. Chem. Res.

144

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“…In this paper, a 500-keV He 2+ ion beam was used to irradiate metallic glass Ta 38 Ni 62 and study its resistance to He 2+ ion beam-induced irradiation damage. Polycrystalline W, currently the most promising plasma-facing material for fusion reactors [22], and V 87.5 Cr 4.17 Ti 4.17 Nb 4.17 alloy, an important candidate structural material for fusion reactors [23], were studied for comparison.…”

Section: Introductionmentioning

confidence: 99%

Resistance to He2+ irradiation damage in metallic glass Ta38Ni62

Hou

Mei

Zhang

et al. 2016

Applied Surface Science

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a b s t r a c tMetallic glass Ta 38 Ni 62 strips, metallic W, and V 87.5 Cr 4.17 Ti 4.17 Nb 4.17 alloy were irradiated using a 500 keV He 2+ ion beam at different fluence to compare the metallic glass resistance to irradiation. Metallic glass Ta 38 Ni 62 remained amorphous at different He 2+ irradiation fluence. Transmission electron microscopy analysis revealed the presence of helium bubbles at the end of the range of helium ions in the metallic glass. No significant damage resulted in the metallic glass surface, and the root mean square roughness increased nonlinearly with the increase in fluence. At 1 × 10 18 ions/cm 2 , metallic W appeared in larger sunken areas on the surface and V 87.5 Cr 4.17 Ti 4.17 Nb 4.17 alloy experienced multi-layer flaking. The metallic glass Ta 38 Ni 62 resistance to He 2+ ion beam irradiation was better than that of metallic W, and that of the V 87.5 Cr 4.17 Ti 4.17 Nb 4.17 alloy was the poorest.

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“…In this paper, the He 2+ ion beam with the energy of 500 KeV was used to irradiate metallic glass Fe 80 Si 7.43 B 12.57 , polycrystalline W [18], currently the most promising plasma facing material for fusion reactor, and alloy V 90.62 Cr 4.69 Ti 4.69 [19], an important candidate structural material for fusion reactor, for the research on the impact of different fluence of He 2+ irradiation on the microstructures and material properties of metallic glass Fe 80 Si 7.43 B 12.57 , polycrystalline W and alloy V 90.62 Cr 4.69 Ti 4.69 , in order to compare their resistance to He 2+ ion beam induced irradiation damage.…”

Section: Introductionmentioning

confidence: 99%