Impact of ceramic coating deposition on the tritium permeation in the Japanese ITER-TBM

Nakamichi, Masaru; Nakamura, Hirofumi; Hayashi, K.; Takagi, Ikuji

doi:10.1016/j.jnucmat.2008.12.282

Cited by 10 publications

(6 citation statements)

References 17 publications

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“…Using the obtained experimental diffusion properties, a preliminary tritium permeation analysis was conducted for TBM using the tritium migration analysis program (TMAP) code [9]. The results yielded by these analyses of the concentration of the bred tritium into the cooling water are portrayed in figure 9 as a function of the elapsed time from the start of the plasma burning and the sweep gas flow [10]. The calculation results indicate that the tritium permeation through the F82H cooling pipe with the CDC coating will be four orders of magnitude less than that without the coating.…”

Section: Tritium Permeation Analysismentioning

confidence: 99%

R&D of a Li₂TiO₃ pebble bed for a test blanket module in JAEA

Hoshino¹,

Kawamura²,

Nakamichi³

et al. 2009

Nucl. Fusion

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At JAEA, a test blanket module (TBM) with a water-cooled solid breeder is being developed. This paper presents recent achievements of research activities for the TBM, particularly addressing the pebble bed of the tritium breeder materials and tritium behaviour. For the breeder material, the chemical stability of Li2TiO3 was improved using Li2O additives. To analyse the pebble bed behaviour, thermomechanical properties of the Li2TiO3 pebble bed were assessed experimentally. To verify the pebble bed's nuclear properties, the activation foil method was proposed and a preliminary experiment was conducted. To reduce the tritium permeation, the chemical densified coating method was developed and the coating was attached to F82H steel. For tritium behaviour, the tritium recovery system was modified in consideration of the design change of the TBM.

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Section: Tritium Permeation Analysismentioning

confidence: 99%

R&D of a Li₂TiO₃ pebble bed for a test blanket module in JAEA

Hoshino¹,

Kawamura²,

Nakamichi³

et al. 2009

Nucl. Fusion

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“…In order to mitigate tritium permeation and LLE corrosion issues, the fusion community relies on coatings as the most promising route available. Ideally, oxide coatings should tackle LLE corrosion and achieve a tritium permeation reduction factor (PRF) as high as 1000 in the gas phase [7][8][9][10][11][12][13][14][15][16][17][18][19][20].…”

Section: Introductionmentioning

confidence: 99%

Efficient hydrogen and deuterium permeation reduction in Al₂O₃ coatings with enhanced radiation tolerance and corrosion resistance

et al. 2018

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One of the major bottlenecks in the development of the breeding blanket of the DEMO fusion reactor is the suppression of tritium permeation through structural steels as well as their protection against dissolution-corrosion by interaction with high temperature heavy liquid metals. Reduction of tritium permeation and corrosion of structural steels are crucial issues in order to enhance reactor safety and avoid operational implications. As a solution to these two daunting challenges, we developed multifunctional alumina coatings capable to tackle, at the same time, tritium permeation and Pb-Li corrosion. The coatings are deposited by pulsed laser deposition and are essentially amorphous, with nanocrystalline inclusions. By optimizing the deposition process, we provide experimental evidence that PLD-grown alumina yields a permeation reduction factor for hydrogen and deuterium well above 10 4 , even after electron irradiation, and a suitable protection against corrosion by the Pb-16Li eutectic. Given these results, the multifunctional, PLD-grown alumina coatings stand out as a viable solution to some of the long-lasting issues related to fusion technologies.

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“…Chromia is also present in mixed oxides in chemical densified coatings, which help to give reduction factors of four orders of magnitude [162].…”

Section: Barrier Materials 4116331 Oxidesmentioning

confidence: 99%

Tritium Barriers and Tritium Diffusion in Fusion Reactors

Causey

Karnesky

Marchi

2012

Comprehensive Nuclear Materials

127

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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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Impact of ceramic coating deposition on the tritium permeation in the Japanese ITER-TBM

Cited by 10 publications

References 17 publications

R&D of a Li₂TiO₃ pebble bed for a test blanket module in JAEA

R&D of a Li₂TiO₃ pebble bed for a test blanket module in JAEA

Efficient hydrogen and deuterium permeation reduction in Al₂O₃ coatings with enhanced radiation tolerance and corrosion resistance

Tritium Barriers and Tritium Diffusion in Fusion Reactors

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Impact of ceramic coating deposition on the tritium permeation in the Japanese ITER-TBM

Cited by 10 publications

References 17 publications

R&D of a Li2TiO3 pebble bed for a test blanket module in JAEA

R&D of a Li2TiO3 pebble bed for a test blanket module in JAEA

Efficient hydrogen and deuterium permeation reduction in Al2O3 coatings with enhanced radiation tolerance and corrosion resistance

Tritium Barriers and Tritium Diffusion in Fusion Reactors

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Product

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R&D of a Li₂TiO₃ pebble bed for a test blanket module in JAEA

R&D of a Li₂TiO₃ pebble bed for a test blanket module in JAEA

Efficient hydrogen and deuterium permeation reduction in Al₂O₃ coatings with enhanced radiation tolerance and corrosion resistance