Development and characterization of advanced neutron multiplier materials

Vladimirov, P.; Chakin, V.; Dürrschnabel, Michael; Gaisin, Ramil; Goraieb, A.; Gonzalez, Francisco Alberto Hernández; Klimenkov, M.; Rieth, M.; Rolli, R.; Zimber, N.; Udartsev, Sergey; Kolmakov, Maxim; Vechkutov, Anatoly; Frants, Evgeniy

doi:10.1016/j.jnucmat.2020.152593

Cited by 18 publications

(10 citation statements)

References 33 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: 78%

“…Therefore, it is essential to gain an in-depth understanding of where and, more importantly, why tritium is trapped within the material. It is generally assumed that both, helium and hydrogen are located directly inside bubbles since both elements are released simultaneously when bulk samples are heated to temperatures ≥ 1100 °C after irradiation 17 – 20 .…”

Section: Introductionmentioning

confidence: 99%

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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: 78%

Section: Introductionmentioning

confidence: 99%

Hydrogen and helium trapping in hcp beryllium

et al. 2023

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“…Beryllides on the other hand are more stable against oxidation, however, to our knowledge, no study exists that deals with the reaction of Li with a beryllide compound. Further beneficial points for beryllide materials are their neutron multiplication characteristics as well as their recent availability on an industrial scale [54,55]. Hence, beryllides are a good starting point for the development of an EUROFER diffusion protection layer.…”

Section: Discussionmentioning

confidence: 99%

Nanoscale insights into the corrosion of EUROFER by lithium ceramics

et al. 2022

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“…In the following, some selective reasons for the mentioned design update are given. In pure beryllium, a significant fraction of generated tritium (up to 100% below 500°C) is trapped within helium bubbles (relevant temperature of beryllium in HCPB BB) [19] which is a safety concern. The use of pure beryllium poses also a risk in the case of a postulated accidental scenario involving water ingress (from failed water-cooled divertors and/or limiters) or air ingress into a failed blanket box exposing beryllium material.…”

Section: Design Evolutionmentioning

confidence: 99%

The European DEMO HCPB Breeding Blanket: Design Status at the End of Pre-Concept Design Phase

Zhou¹,

Hernández²,

Pereslavtsev³

et al. 2023

Preprint

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Significant design efforts were undertaken during the Pre-Concept Design (PCD) phase of the European DEMO programme to optimize the Helium Cooled Pebble Bed (HCPB) breeding blanket. A Gate Review was conducted for the entire European DEMO programme at the conclusion of the PCD phase. This article presents a summary of the design evolution and the rationale behind the HCPB breeding blanket concept for the European DEMO. The main performance metrics, including nuclear, thermal hydraulics, thermal mechanical, and tritium permeation behaviors, are reported. These figures demonstrate that the HCPB breeding blanket is a highly effective tritium-breeding and robust driver blanket concept for the European DEMO. In addition, three alternative concepts of interest were explored. Furthermore, this article outlines the upcoming design and R&D activities for the HCPB breeding blanket during the Concept Design phase (2021-2027).

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Development and characterization of advanced neutron multiplier materials

Cited by 18 publications

References 33 publications

Hydrogen and helium trapping in hcp beryllium

Hydrogen and helium trapping in hcp beryllium

Nanoscale insights into the corrosion of EUROFER by lithium ceramics

The European DEMO HCPB Breeding Blanket: Design Status at the End of Pre-Concept Design Phase

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