Study of Reprocessing of MSR - FUJI Spent Fuel - Electrochemical Part

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F23%3AN0000213" target="_blank" >RIV/26722445:_____/23:N0000213 - 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

Study of Reprocessing of MSR - FUJI Spent Fuel - Electrochemical Part

Popis výsledku v původním jazyce

The study was realized under the contract between the Thorium Tech Solution Inc. (TTS), Japan and the Research Centre Řež (CVR), Czech Republic. The main purpose of the study is to evaluate the possibility to apply the off-line reprocessing technology based on fluoride methods within the Molten Salt Reactor fuel cycle with the emphasis to incinerate the reactor grade plutonium, to identify the capabilities and deficiencies of already tested and verified technologies and to preliminary establish a development plan of MSR off-line fluoride reprocessing. Additional purpose of the study is to assess the possibility of the technology to enable to process plutonium coming from the fuel-debris from Fukushima Daiichi NPP. The study is mainly focused on the electrochemical separation part of off-line reprocessing and follows two previous studies carried out in 2021 and 2022. Report CVR-4737.

Název v anglickém jazyce

Study of Reprocessing of MSR - FUJI Spent Fuel - Electrochemical Part

Popis výsledku anglicky

The study was realized under the contract between the Thorium Tech Solution Inc. (TTS), Japan and the Research Centre Řež (CVR), Czech Republic. The main purpose of the study is to evaluate the possibility to apply the off-line reprocessing technology based on fluoride methods within the Molten Salt Reactor fuel cycle with the emphasis to incinerate the reactor grade plutonium, to identify the capabilities and deficiencies of already tested and verified technologies and to preliminary establish a development plan of MSR off-line fluoride reprocessing. Additional purpose of the study is to assess the possibility of the technology to enable to process plutonium coming from the fuel-debris from Fukushima Daiichi NPP. The study is mainly focused on the electrochemical separation part of off-line reprocessing and follows two previous studies carried out in 2021 and 2022. Report CVR-4737.

Druh

O - Ostatní výsledky

CEP obor

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OECD FORD obor

10402 - Inorganic and nuclear chemistry

Projekt

<a href="/cs/project/LM2023041" target="_blank" >LM2023041: České mezinárodní centrum výzkumných reaktorů</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