Dust generation in fusion facilities and recycling of these valuable wastes

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F23%3AN0000168" target="_blank" >RIV/26722445:_____/23:N0000168 - isvavai.cz</a>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Dust generation in fusion facilities and recycling of these valuable wastes

Popis výsledku v původním jazyce

In addressing the energy future of the world, one of the envisaged options is to produce energy through the process of nuclear fusion of deuterium and tritium, isotopes of hydrogen. In doing so, the product is non-radioactive waste helium. In the process, a high-temperature plasma is formed. All this takes place in a toroidal magnetic field and is further isolated from the surroundings by an assembly of heat and mechanically very resistant materials forming an armor. In particular, tungsten and, to a lesser extent, various types of steel represent the largest volume in the armor assembly. In the fusion device, various processes can take place to release solid particles from the armor, ranging in size from atoms to clusters. Dust particles often carry radioactivity, the carrier of which is trapped tritium. The proposed recycling processes can separate the solid components from the tritium. The tritium gas or oxidized to tritiated water is returned to the fusion processes. Tritiated tungsten dust using MSO (molten salt oxidation) technology can be separated and reprocessed. The tungsten then remains in the molten salt and all the tritium is released as tritiated water into the gas phase. Using induction heating, under vacuum or in an inert atmosphere, the tritiated material can be heated to temperatures where the tritium escapes from the material as a gas, but the tungsten is not oxidized. In doing so, tungsten can be compacted by sintering. Presented at 49th International conference of Slovak Society of Chemical Engineering – SSCHE 2023.

Název v anglickém jazyce

Dust generation in fusion facilities and recycling of these valuable wastes

Popis výsledku anglicky

In addressing the energy future of the world, one of the envisaged options is to produce energy through the process of nuclear fusion of deuterium and tritium, isotopes of hydrogen. In doing so, the product is non-radioactive waste helium. In the process, a high-temperature plasma is formed. All this takes place in a toroidal magnetic field and is further isolated from the surroundings by an assembly of heat and mechanically very resistant materials forming an armor. In particular, tungsten and, to a lesser extent, various types of steel represent the largest volume in the armor assembly. In the fusion device, various processes can take place to release solid particles from the armor, ranging in size from atoms to clusters. Dust particles often carry radioactivity, the carrier of which is trapped tritium. The proposed recycling processes can separate the solid components from the tritium. The tritium gas or oxidized to tritiated water is returned to the fusion processes. Tritiated tungsten dust using MSO (molten salt oxidation) technology can be separated and reprocessed. The tungsten then remains in the molten salt and all the tritium is released as tritiated water into the gas phase. Using induction heating, under vacuum or in an inert atmosphere, the tritiated material can be heated to temperatures where the tritium escapes from the material as a gas, but the tungsten is not oxidized. In doing so, tungsten can be compacted by sintering. Presented at 49th International conference of Slovak Society of Chemical Engineering – SSCHE 2023.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

10305 - Fluids and plasma physics (including surface physics)

Projekt

<a href="/cs/project/9D22001" target="_blank" >9D22001: Implementation of activities described in the Roadmap to Fusion during Horizon Europe through a joint programme of the members of the EUROfusion consortium</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2023

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název statě ve sborníku

Proceedings 49th International Conference of the Slovak Society of Chemical Engineering SSCHE 2023

ISBN

978-808208-101-8

ISSN

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e-ISSN

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Počet stran výsledku

13

Strana od-do

1-13

Název nakladatele

Faculty of Chemical and Food Technology STU in Bratislava

Místo vydání

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Místo konání akce

Tatranské Matliare

Datum konání akce

15. 5. 2023

Typ akce podle státní příslušnosti

EUR - Evropská akce

Kód UT WoS článku

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