Heavy hydrogen isotopes penetration through austenitic and martensitic steels

Dolinski, Yu.; Lyasota, I.A.; Shestakov, Alexander; Repritsev, Yu.; Zouev, Yu.N.

doi:10.1016/s0022-3115(00)00314-7

Cited by 10 publications

(3 citation statements)

References 4 publications

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“…On the basis of the known permeation coefficients for hydrogen in stainless steel the uptake of tritium by this metal will be very slow at room temperature [22,23]. Hirabayashi and Saeki [17], on the other hand, have shown that during an exposure over 35 days to 13.3 kPa tritium at 293 K this gas penetrates into the bulk of SS316 up to a depth of 50 lm with a diffusion constant of 6.4 · 10 À17 m 2 /s.…”

Section: Mechanism Of Tritium Releasementioning

confidence: 99%

Detritiation of type 316 stainless steel by treatment with liquids at ambient temperature

Penzhorn

Torikai

Matsuyama

et al. 2006

Journal of Nuclear Materials

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Section: Mechanism Of Tritium Releasementioning

confidence: 99%

Detritiation of type 316 stainless steel by treatment with liquids at ambient temperature

Penzhorn

Torikai

Matsuyama

et al. 2006

Journal of Nuclear Materials

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“…Figure 13. Solubility of hydrogen in RAFM steels from gas permeation studies that confirmed diffusion-limited transport [7,19,105,106,108,226,227]. The bold line represents an approximate relationship estimated from the plotted data.…”

Section: Why Barriers Are Needed For Fusion Reactorsmentioning

confidence: 86%

Tritium Barriers and Tritium Diffusion in Fusion Reactors

Causey

Karnesky

Marchi

2012

Comprehensive Nuclear Materials

129

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Tritium and deuterium induce radiation in reactor materials and some radioactive tritium gas may be released. Most of the materials used in fusion reactors are metals that have relatively high permeabilities for tritium. The fusion community has been working on barriers to minimize tritium release. Unfortunately, most barrier materials work very well during laboratory experiments, but fail to meet requirements when placed in radiation environments.This chapter presents tritium permeation characteristics of various materials used in fusion reactors, including plasma-facing, structural, and barrier materials. The necessary parameters for tritium release calculations for various regions of a fusion reactor are given.

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“…In Chinese‐designed reactors, China low activation martensitic (CLAM) steel is used as a structural material in these DFLL‐TBMs . However, tritium can readily diffuse through this structural CLAM layer, and a significant magneto‐hydrodynamic pressure drop can be caused by the effect of the magnetic field on the metallic coolant . Therefore, the use of an electrically insulating ceramic coating with a large tritium permeation reduction factor (PRF) on CLAM steel is needed to adequately segregate the structural walls from the contained liquid.…”

Section: Introductionmentioning

confidence: 99%

Fabrication, morphology and mechanical properties of Al₂O₃–Al graded coatings on China low activation martensitic steel substrates

Song

Chen

et al. 2011

Surface & Interface Analysis

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graded coatings were fabricated on China low activation martensitic steel and silicon substrates by RF magnetron sputtering. The coating composition and cross-section morphologies were investigated using X-ray photoelectron spectroscopy, Auger electron spectroscopy and field-emission scanning electron microscopy. The mechanical properties of the coatings were studied using nanoindentation, wafer-curvature measurements and microscratch tests. The results show that usable Al 2 O 3 -Al graded coatings could be fabricated. With a more continuous compositional gradient, the interface zone was more compact. The hardness and elastic modulus of Al 2 O 3 -Al graded coatings were less than those of Al 2 O 3 coatings, but greater than those of Al 2 O 3 /Al coatings. After annealing at 773 K for 3 h, the hardness of Al 2 O 3 -Al graded coating showed a small increase. The residual stresses in Al 2 O 3 -Al graded coatings declined to about 0.3 GPa, compared with the 6.6 GPa for Al 2 O 3 coating. The adhesion of Al 2 O 3 was improved by deposition of Al or Al compositional gradient oxide layers.

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Heavy hydrogen isotopes penetration through austenitic and martensitic steels

Cited by 10 publications

References 4 publications

Detritiation of type 316 stainless steel by treatment with liquids at ambient temperature

Detritiation of type 316 stainless steel by treatment with liquids at ambient temperature

Tritium Barriers and Tritium Diffusion in Fusion Reactors

Fabrication, morphology and mechanical properties of Al₂O₃–Al graded coatings on China low activation martensitic steel substrates

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Heavy hydrogen isotopes penetration through austenitic and martensitic steels

Cited by 10 publications

References 4 publications

Detritiation of type 316 stainless steel by treatment with liquids at ambient temperature

Detritiation of type 316 stainless steel by treatment with liquids at ambient temperature

Tritium Barriers and Tritium Diffusion in Fusion Reactors

Fabrication, morphology and mechanical properties of Al2O3–Al graded coatings on China low activation martensitic steel substrates

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Product

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Fabrication, morphology and mechanical properties of Al₂O₃–Al graded coatings on China low activation martensitic steel substrates