Tritium release and retention in beryllium and titanium beryllide after neutron irradiation up to damage doses of 23-38 dpa

Chakin, V.; Rolli, R.; Gaisin, Ramil; Hoeppener-Kramar, U.; Nakamichi, Masaru; Zmítko, M.

doi:10.1016/j.fusengdes.2020.111938

Cited by 21 publications

(11 citation statements)

References 32 publications

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“…Such hydrides seem to be stabilized above their normal decomposition temperature by the large amounts of helium in the bubble interior. These findings can be used to explain the high tritium release temperature of T ≥ 1100 °C in TPD experiments 17 – 19 . The necessity of heating the pebbles to such high temperatures raises serious problems that have not yet been solved, among others because the surrounding structural materials are not designed for these temperatures 49 .…”

Section: Resultsmentioning

confidence: 79%

Hydrogen and helium trapping in hcp beryllium

et al. 2023

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Even though hydrogen-metal surface interactions play an important role in energy technologies and metal corrosion, a thorough understanding of these interactions at the nanoscale remains elusive due to obstructive detection limits in instrumentation and the volatility of pure hydrogen. In the present paper we use analytical spectroscopy in TEM to show that hydrogen adsorbs directly at the (0001) surfaces of hexagonal helium bubbles within neutron irradiated beryllium. In addition to hydrogen, we also found Al, Si and Mg at the beryllium-bubble interfaces. The strong attraction of these elements to (0001) surfaces is underlined with ab-initio calculations. In situ TEM heating experiments reveal that hydrogen can desorb from the bubble walls at T ≥ 400 °C if the helium content is reduced by opening the bubbles. Based on our results we suggest the formation of a complex hydride consisting of up to five elements with a remarkably high decomposition temperature. These results therefore promise novel insights into metal-hydrogen interaction behavior and are invaluable for the safety of future fusion power plants.

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Section: Resultsmentioning

confidence: 79%

Hydrogen and helium trapping in hcp beryllium

et al. 2023

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“…Over the past two decades, extensive research has been conducted on the tritium release and retention properties of the neutron-irradiated beryllium [14][15][16][17][18][19], establishing the primary features of tritium behavior at fusion-relevant temperatures of 630-1040 K. There are no publications dedicated to investigating the tritium release properties of beryllium irradiated at lower parameters, such as the operating temperatures of material testing reactors with water coolant. The aim of this study is to investigate the tritium release properties of beryllium exposed in the BR2 reactor at a temperature of 323 K, up to a high neutron dose and, accordingly, high tritium and helium productions under irradiation.…”

Section: Introductionmentioning

confidence: 99%

Tritium Desorption Behavior and Microstructure Evolution of Beryllium Irradiated at Low Temperature Up to High Neutron Dose in BR2 Reactor

Chakin

Rolli

Gaisin

et al. 2023

JNE

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The present study investigated the release of tritium from beryllium irradiated at 323 K to a neutron fluence of 4.67 × 1026 m−2 (E > 1 MeV), corresponding up to 22,000 appm helium and 2000 appm tritium productions. The TPD tests revealed a single tritium release peak during thermal desorption tests, irrespective of the heating mode employed. The tritium release peaks occurred at temperatures ranging from 1031–1136 K, depending on the heating mode, with a desorption energy of 1.6 eV. Additionally, the effective tritium diffusion coefficient was found to vary from 1.2 × 10−12 m2/s at 873 K to 1.8 × 10−10 m2/s at 1073 K. The evolution of beryllium microstructure was found to be dependent on the annealing temperature. No discernible differences were observed between the as-received state and after annealing at 473–773 K for 5 h, with a corresponding porosity range of 1–2%. The annealing at temperatures of 873–1373 K for 5 h resulted in the formation of large bubbles, with porosity increasing sharply above 873 K and reaching 30–60%.

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“…From a standpoint of neutron activation, Ti is a suitable element to be used in transition materials for fusion reactors [102], which makes it a potential candidate fusion reactor material [151]. However, some concerns remain due to tritium sequestration in Ti alloys resulting from high hydrogen solubility, and these should be taken into account for design considerations of fusion reactors [152].…”

Section: Titanium Interlayermentioning

confidence: 99%

Evaluation of Tungsten—Steel Solid-State Bonding: Options and the Role of CALPHAD to Screen Diffusion Bonding Interlayers

Robin

Gräning

Yang

et al. 2023

Metals

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Critical aspects of innovative design in engineering disciplines like infrastructure, transportation, and medical applications require the joining of dissimilar materials. This study investigates the literature on solid-state bonding techniques, with a particular focus on diffusion bonding, as an effective method for establishing engineering bonds. Welding and brazing, while widely used, may pose challenges when joining materials with large differences in melting temperature and can lead to mechanical property degradation. In contrast, diffusion bonding offers a lower temperature process that relies on solid-state interactions to develop bond strength. The joining of tungsten and steel, especially for fusion reactors, presents a unique challenge due to the significant disparity in melting temperatures and the propensity to form brittle intermetallics. Here, diffusion characteristics of tungsten–steel interfaces are examined and the influence of bonding parameters on mechanical properties are investigated. Additionally, CALPHAD modeling is employed to explore joining parameters, thermal stability, and diffusion kinetics. The insights from this research can be extended to join numerous dissimilar materials for specific applications such as aerospace, automobile industry, power plants, etc., enabling advanced and robust design with high efficiency.

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Tritium release and retention in beryllium and titanium beryllide after neutron irradiation up to damage doses of 23-38 dpa

Cited by 21 publications

References 32 publications

Hydrogen and helium trapping in hcp beryllium

Hydrogen and helium trapping in hcp beryllium

Tritium Desorption Behavior and Microstructure Evolution of Beryllium Irradiated at Low Temperature Up to High Neutron Dose in BR2 Reactor

Evaluation of Tungsten—Steel Solid-State Bonding: Options and the Role of CALPHAD to Screen Diffusion Bonding Interlayers

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