Tritium permeation barriers in contact with liquid lithium-lead eutectic (Pb17Li)

Forcey, K.S.; Perujo, A.

doi:10.1016/0022-3115(94)00434-x

Cited by 13 publications

(3 citation statements)

References 6 publications

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“…Besides the corrosion protection purpose they also provide tritium permeation reduction properties due to the formation of Fe-Al phases and Al 2 O 3 on the surface [4]. Therefore, different coating techniques such as chemical vapor deposition (CVD) [5][6][7], pack-aluminizing [7,8], vacuum plasma spraying (VPS) [6] and hot-dip aluminization (HDA) [9] were under investigation to produce aluminum-based tritium permeation barriers on different steels in the past.…”

Section: Introductionmentioning

confidence: 99%

Corrosion barriers processed by Al electroplating and their resistance against flowing Pb–15.7Li

Krauß

Konys

Wulf

2014

Journal of Nuclear Materials

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Test samples after 10000 h exposure to Pb-15.7Li Reduced activation ferritic-martensitic steels (RAFM) are considered as main structural material in future fusion systems, e.g. envisaged in the He-cooled liquid lead (HCLL) design. Thereby, these steels will be in direct contact with the breeding material Pb-15.7Li, which lead to strong corrosion attack of the structural material. Aluminum rich Fe-Al scales on RAFM steels are considered as promising corrosion barriers, which also offer T permeation reduction properties. Scales produced by Hot-dipping aluminization (HDA) exhibited some disadvantages in the past, and therefore electrochemical processes (ECA, ECX) were introduced, but have lack concerning corrosion protection data in flowing Pb-15.7Li. MotivationCorrosion barriers processed by Al-electroplating and their resistance against flowing Pb-15.7Li

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Section: Introductionmentioning

confidence: 99%

Corrosion barriers processed by Al electroplating and their resistance against flowing Pb–15.7Li

Krauß

Konys

Wulf

2014

Journal of Nuclear Materials

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“…Sedano et al [8] evaluated tritium permeation and extraction for the LIBRETTO-3 experiment (irradiation of LLE capsules coated with different permeation barriers). Tritium permeation barriers in contact with liquid LLE in stainless steel tubes was estudied by Forcey et al [9], and Nakamichi et al [10] conducted several in-pile experiments on tritium permeation with ceramic coatings at the research reactor IGV. 1 M, in Kazakhstan, using liquid LLE alloys as the T source.…”

Section: Introductionmentioning

confidence: 99%

Impact of nuclear irradiation on helium bubble nucleation at interfaces in liquid metals coupled to permeation through stainless steels

Fradera

Cuesta‐López

2014

Fusion Engineering and Design

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The impact of nucleating gas bubbles in the form of a dispersed gas phase on hydrogen isotope permeation at interfaces between liquid metals, like LLE , and structural materials, like stainless steel, has been studied. Liquid metal to structural material interfaces involving surfaces, may lower the nucleation barrier promoting bubble nucleation at active sites. Hence, hydrogen isotope absorption into gas bubbles modelling and control at interfaces may have a capital importance regarding design, operation and safety.He bubbles as a permeation barrier principle is analysed showing a significant impact on hydrogen isotope permeation, which may have a significant effect on liquid metal systems, e.g., tritium extraction systems. Liquid metals like LLE under nuclear irradiation in, e.g., breeding blankets of a nuclear fusion reactor would generate tritium which is to be extracted and recirculated as fuel. At the same time that tritium is bred, helium is also generated and may precipitate in the form of nano bubbles.Phenomena modelling is exposed and implemented in OpenFOAM R CFD tool for 0D to 3D simulations. Results for a 1D case show the impact of a He dispersed phase of nano bubbles on hydrogen isotopes permeation at an interface. In addition, a simple permeator simulation, consisting in a straight 3D pipe is exposed showing the effect of a He dispersed gas phase on hydrogen isotope permeation through different stainless steels. Results show the permeation reduction as a function of the interface area covered by He bubbles.Our work highlights the effect of gas bubble nucleation at interfaces and the importance of controlling these phenomena in nuclear technology applications.

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“…In the case of self-cooled liquid metal blanket concepts, such coatings must, in addition, satisfy the requirements of high electrical resistivity and corrosion resistance. Al 2 O 3 can be employed for T control [2][3][4][5], Er 2 O 3 could even show sufficient corrosion resistance in contact with liquid lithium [6].…”

Section: Introductionmentioning

confidence: 99%

Crystallization behavior of arc-deposited ceramic barrier coatings

Koch

Brill

Maier

et al. 2004

Journal of Nuclear Materials

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Tritium permeation barriers in contact with liquid lithium-lead eutectic (Pb17Li)

Cited by 13 publications

References 6 publications

Corrosion barriers processed by Al electroplating and their resistance against flowing Pb–15.7Li

Corrosion barriers processed by Al electroplating and their resistance against flowing Pb–15.7Li

Impact of nuclear irradiation on helium bubble nucleation at interfaces in liquid metals coupled to permeation through stainless steels

Crystallization behavior of arc-deposited ceramic barrier coatings

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