Performances of Cr 2 O 3 –hydrogen isotopes permeation barriers

Li, Qun; Mo, Liping; Wang, Jie; Kai, Yan; Tang, Tao; Rao, Yongchu; Yao, Wenqing; Cao, Jiangli

doi:10.1016/j.ijhydene.2015.03.093

Cited by 38 publications

(7 citation statements)

References 28 publications

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“…These results indicate that Al 2 O 3, SiO 2 , AlN, Si 3 N 4 , CrN and TiN are promising HPB candidates. This result is consistent with a previous study, which reported that Al 2 O 3 , TiO 2 , and TiN show a higher propensity for permeation reduction than does Cr 2 O 3 …”

Section: Resultssupporting

confidence: 94%

“…Therefore, to make wide use of hydrogen as a new green energy storage medium, there is a need to develop long lasting and low‐cost hydrogen storage tank materials that can suppress hydrogen embrittlement. Moreover, high‐temperature hydrogen isotopes exist as fuels and products in nuclear fusion reactors ,. Therefore, the embrittlement of blanket materials caused by hydrogen isotopes has to be suppressed.…”

Section: Introductionmentioning

confidence: 99%

“…In addition, ceramic materials are very stable, even under high temperature conditions. Thus, they are applicable as blanket materials for nuclear fusion reactors . Atomic vacancies and impurities in ceramic materials also affect their hydrogen permeation properties.…”

Section: Introductionmentioning

confidence: 99%

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Hydrogen Isotope Absorption in Unary Oxides and Nitrides with Anion Vacancies and Substitution

2019

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The absorption states of hydrogen isotopes in various ceramic materials were investigated by density functional theory. For pristine ceramic materials, main-group oxides do not form any bond with a hydrogen atom. However, transition metal oxides form hydroxyl groups and absorb hydrogen atoms. Main-group and transition metal nitrides form ionic bonds between a hydrogen atom and the surrounded cation. For anion-deficient ceramic materials, hydrogen atoms are negatively charged because of excess electrons induced by anion vacancies, and ionic bonds form with the surrounded cation, which stabilizes the hydrogen absorption state. N substitutional doping into oxides introduces an electron hole, while O substitutional doping into the nitrides introduces an excess of electrons. Therefore, hydrogen isotopes form covalent bonds in Nsubstituted oxides, and form hydride ions in O-substituted nitrides. Thus, Al 2 O 3 , SiO 2 , CrN, and TiN are promising materials as hydrogen permeation barriers.[a] T.

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Section: Resultssupporting

confidence: 94%

Section: Introductionmentioning

confidence: 99%

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Hydrogen Isotope Absorption in Unary Oxides and Nitrides with Anion Vacancies and Substitution

2019

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“…However, for HT3 irradiated with hydrogen ions, no oxide disappeared, but rather, only the diffraction peak intensities of some oxides changed, while the diffraction peak of BCC phase became slightly stronger ( Figure 10 b), indicating that there was a certain degree of hydrogen reduction, albeit not as significant as that observed with HT1. This may have been due to the presence of Cr 2 O 3 in HT3, as Cr 2 O 3 has good hydrogen permeation resistance properties [ 42 ]. Therefore, it can be considered that the oxides on the surface of HT3 were more stable and had better hydrogen permeation resistance than those on the surface of HT1.…”

Section: Resultsmentioning

confidence: 99%

Investigation of the Oxidation Behavior of Cr20Mn17Fe18Ta23W22 and Microdefects Evolution Induced by Hydrogen Ions before and after Oxidation

Zhu

Cao

et al. 2022

Materials

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The oxidation behavior of body-centered cubic (bcc) structure Cr20Mn17Fe18Ta23W22 refractory high-entropy alloy (RHEA) and the microdefects induced by hydrogen ions before and after oxidation were investigated. The results revealed that compared with oxidizing Cr20Mn17Fe18Ta23W22 at 800 °C (6.7 °C/min) for 4 h (ST3, Ar:O2 = 3:1), the heating procedure of oxidizing Cr20Mn17Fe18Ta23W22 at 300 °C (6 °C/min) for 2 h and then increased to 800 °C (5 °C/min) for 4 h is more conducive to the production of oxides without spalling on the surface, i.e., HT1 (Ar:O2 = 1:1), HT2 (Ar:O2 = 2:1) and HT3 (Ar:O2 = 3:1) samples. The oxidation of Cr20Mn17Fe18Ta23W22 RHEA is mainly controlled by the diffusion of cations instead of affinities with O. Additionally, HT1 and HT3 samples irradiated with a fluence of 3.9 × 1022 cm−2 hydrogen ions (60 eV) were found to have a better hydrogen irradiation resistance than Cr20Mn17Fe18Ta23W22 RHEA. The microdefects in irradiated Cr20Mn17Fe18Ta23W22 mainly existed as hydrogen bubbles, hydrogen-vacancy (H-V) complexes and vacancy/vacancy clusters. The microdefects in irradiated HT3 were mainly vacancies and H-V complexes, while the microdefects in irradiated HT1 mainly existed as vacancies and vacancy clusters, as large amounts of hydrogen were consumed to react with oxides on the HT1 surface. The oxides on the surface of the HT3 sample were more stable than those on HT1 under hydrogen irradiation.

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“…Excluded from this review are considerations of special surface treatments and coatings on structural materials which are likely to be used as tritium permeation barrier in some cases. [56][57][58][59][60][61][62] B. Tritium in Reactors: Implications of Using FeCrAl Alloys…”

Section: A Fecral and Hydrogenmentioning

confidence: 99%

Hydrogen Isotopes Permeation in Clean or Unoxidized FeCrAl Alloys: A Review

Garud¹,

Hoffman²,

Rebak³

2022

Metall Mater Trans A

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The US Department of Energy is working with fuel vendors to develop accident tolerant fuels (ATF) for the current fleet of light water reactors (LWRs). The ATF should be more resilient to loss of coolant accident scenarios and help extending the life of the operating LWRs. One of the proposed ATF concepts is to use iron-chromium-aluminum (FeCrAl) alloys for the cladding of the fuel. A concern in using ferritic FeCrAl is that this type of cladding may result in an increase in the concentration of tritium in the coolant. The objective of the current critical review is to collect and assess information from the literature regarding diffusion or permeation of hydrogen (H) and its isotopes deuterium (D) and Tritium (T) across industrial alloys (including FeCrAl) used or intended for the nuclear industry. Over a hundred years of data reviewed shows that the solubility of hydrogen in ferritic alloys is lower than in austenitic alloys but hydrogen permeates faster through a ferritic material than through austenitic materials. The tritium permeation rates in FeCrAl alloys are between those in austenitic stainless steels and in ferritic FeCr steels. The activation energy for hydrogen permeation is approximately 30 pct higher in the austenitic alloys compared with the ferritic (typically ∼ 50 kJ/mol in ferritic vs. ∼ 65 kJ/mol in the austenitic). None of the major elements in FeCrAl alloys react with hydrogen to form detrimental hydride phases. The effect of surface oxides on FeCrAl delaying hydrogen entrance into FeCrAl alloy is not part of this review.

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Performances of Cr 2 O 3 –hydrogen isotopes permeation barriers

Cited by 38 publications

References 28 publications

Hydrogen Isotope Absorption in Unary Oxides and Nitrides with Anion Vacancies and Substitution

Hydrogen Isotope Absorption in Unary Oxides and Nitrides with Anion Vacancies and Substitution

Investigation of the Oxidation Behavior of Cr20Mn17Fe18Ta23W22 and Microdefects Evolution Induced by Hydrogen Ions before and after Oxidation

Hydrogen Isotopes Permeation in Clean or Unoxidized FeCrAl Alloys: A Review

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