Thermally induced outdiffusion studies of deuterium in ceramic breeder blanket materials after irradiation

González, M.; Carella, E.; Moroño, Á.; Kolb, M.H.H.; Knitter, Regina

doi:10.1016/j.fusengdes.2015.03.027

Cited by 12 publications

(3 citation statements)

References 8 publications

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“…The accumulated RD and RP annihilates around 423-773 K and thus it has been suggested that the main tritium release peaks could be expected in this temperature range. The pre-liminary deuterium and tritium release studies [7,30] confirm these assumptions, however additional research on the tritium release from the advanced pebbles is required to evaluate the applicability of the breeder pebbles.…”

Section: The Microstructures Of the Li4 Sio4 Pebbles With Different Cmentioning

confidence: 98%

“…The optimum content of Li2 TiO3 has yet to be evaluated; nonetheless the advanced pebbles have enhanced mechanical properties, without losing the benefit of a high lithium density and melting temperature [5]. The preliminary studies indi-cate that the change in the chemical composition of the pebbles does not significantly affect the radiation stability [6], release char-acteristics [7] and activation behaviour [8]. The re-melting and lithium re-enrichment studies [9] also revealed that the recycling of the advanced breeder pebbles, without a deterioration of the mate-rial properties, is possible using an enhanced melt-based process.…”

Section: Introductionmentioning

confidence: 99%

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Behaviour of advanced tritium breeder pebbles under simultaneous action of accelerated electrons and high temperature

Zariņš

Leys

Ķizāne

et al. 2017

Fusion Engineering and Design

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h i g h l i g h t s • Irradiation temperature affects accumulation of radiation-induced defects (RD) and radiolysis products (RP). • With an increasing content of Li2 TO3 in the advanced pebbles, the concentration of accumulated RD and RP decreases. • The accumulated RD and RP annihilates around 423-773 K. • Mechanical properties of the advanced pebbles practically do not change after irradiation. Advanced lithium orthosilicate (Li4 SiO4) pebbles with additions of lithium metatitanate (Li2 TiO3) as a secondary phase are suggested as a potential source for tritium breeding in future nuclear fusion reactors. The advanced Li4 SiO4 pebbles with different contents of Li2 TiO3 were examined before and after simultaneous action of 5 MeV accelerated electron beam (dose rate: up to 10 MGy h −1) and high temperature (up to 1120 K) in a dry argon atmosphere. The accumulated radiation-induced defects (RD) and radiolysis products (RP) were studied by electron spin resonance (ESR) spectrometry and thermally stimulated luminescence (TSL) technique. The phase transitions were studied with powder X-ray diffraction (p-XRD). The microstructure and mechanical strength of the pebbles, before and after irradiation, were investigated by scanning electron microscopy (SEM) and comprehensive crush load tests. The obtained results revealed that the irradiation temperature has a significant impact on the accumulation of RD and RP in the advanced Li4 SiO4 pebbles, and with an increasing content of Li2 TiO3 , the concentration of accumulated paramagnetic RD and RP decreases. Major changes in the mechanical strength, microstructure and phase composition of the advanced pebbles were not detected after irradiation.

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Section: The Microstructures Of the Li4 Sio4 Pebbles With Different Cmentioning

confidence: 98%

Section: Introductionmentioning

confidence: 99%

Behaviour of advanced tritium breeder pebbles under simultaneous action of accelerated electrons and high temperature

Zariņš

Leys

Ķizāne

et al. 2017

Fusion Engineering and Design

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“…Nevertheless, the shortage of relevant experimental platforms, long experimental periods and high costs have limited the development of tritium breeding materials to a certain extent. To more efficiently grasp the behavior of tritium in lithiumbased breeding ceramic, a method of injecting hydrogen isotopes (tritium or deuterium) out-of-pile is proposed [20][21][22][23]. Although this technology lacks the process of tritium generation from the crystal and migration to the surface, it still has practical significance for studying surface reactions such as tritium adsorption/desorption and isotope exchange.…”

Section: Introductionmentioning

confidence: 99%

The effect of long-term heating on the tritium adsorption and desorption behavior of advanced core–shell breeding materials

et al. 2022

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In order to efficiently grasp the tritium behavior in advanced core-shell breeding materials, this study adopts a route of injecting tritium out-of-pile to deal with the problems of fewer platforms, long periods, and high costs for traditional neutron irradiation-tritium release experiments. Here, tritium adsorption and desorption experiments were carried out with Li4TiO4-Li2TiO3 core-shell breeding materials before and after long-term heating up to 30 days. The purpose is to study whether the structural changes caused by long-term heating will affect the adsorption and desorption behavior of tritium on the sample surface. The results show that the lack of chemically adsorbed water caused by long-term heating will significantly weaken the tritium adsorption capacity of the sample, but will not affect the desorption behavior of Ar, 1%H2+Ar and water vapor on tritium, so all samples show a very low tritium retention.

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Objectives and status of EUROfusion DEMO blanket studies

Boccaccini

Aiello

Aubert

et al. 2016

Fusion Engineering and Design

179

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The design of a DEMO reactor requires the design of a blanket system suitable of reliable T production and heat extraction for electricity production. In the frame of the EUROfusion Consortium activities, the Breeding Blanket Project has been constituted in 2014 with the goal to develop concepts of Breeding Blankets for the EU PPPT DEMO; this includes an integrated design and R&D program with the goal to select after 2020 concepts on fusion plants for the engineering phase. The design activities are presently focalized around a pool of solid and liquid breeder blanket with helium, water and PbLi cooling. Development of tritium extraction and control technology, as well manufacturing and development of solid and PbLi breeders are part of the Programme.

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Thermally induced outdiffusion studies of deuterium in ceramic breeder blanket materials after irradiation

Cited by 12 publications

References 8 publications

Behaviour of advanced tritium breeder pebbles under simultaneous action of accelerated electrons and high temperature

Behaviour of advanced tritium breeder pebbles under simultaneous action of accelerated electrons and high temperature

The effect of long-term heating on the tritium adsorption and desorption behavior of advanced core–shell breeding materials

Objectives and status of EUROfusion DEMO blanket studies

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