On the Posibility of Quantitative Electrochemical Separation of Uranium from Gadolinium in Fluoride Melts

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F18%3AN0000087" target="_blank" >RIV/26722445:_____/18:N0000087 - isvavai.cz</a>

Výsledek na webu

<a href="https://ans.org/pubs/transactions/a_43585" target="_blank" >https://ans.org/pubs/transactions/a_43585</a>

DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

On the Posibility of Quantitative Electrochemical Separation of Uranium from Gadolinium in Fluoride Melts

Popis výsledku v původním jazyce

The Molten Salt Reactor (MSR) is a non-classical (liquid fuel) system which can be operated as a breeder within the 232Th-233U fuel cycle with the very interesting breeding factor. The necessary precondition for its proper functionality is the on-line reprocessing within the MSR´s fuel cycle. Therefore, a lot of effort is given to the development of the on-line pyrochemical reprocessing technology. Among the processes considered to be suitable for this process, the electrochemical separations are highlighted. Within this context, it is necessary to study electrochemical behavior of both fissile material and fission products in the molten salt systems and to develop the processes of their extraction from the system at various stages of the whole cycle. More details about MSR on-line reprocessing technology and also its connection to nonproliferation aspects can be found here.1 In this contribution, continuation of the study of the electrochemical separation of U from Gd in the LiF-CaF2 molten system by the modulated current electrolysis is presented.

Název v anglickém jazyce

On the Posibility of Quantitative Electrochemical Separation of Uranium from Gadolinium in Fluoride Melts

Popis výsledku anglicky

The Molten Salt Reactor (MSR) is a non-classical (liquid fuel) system which can be operated as a breeder within the 232Th-233U fuel cycle with the very interesting breeding factor. The necessary precondition for its proper functionality is the on-line reprocessing within the MSR´s fuel cycle. Therefore, a lot of effort is given to the development of the on-line pyrochemical reprocessing technology. Among the processes considered to be suitable for this process, the electrochemical separations are highlighted. Within this context, it is necessary to study electrochemical behavior of both fissile material and fission products in the molten salt systems and to develop the processes of their extraction from the system at various stages of the whole cycle. More details about MSR on-line reprocessing technology and also its connection to nonproliferation aspects can be found here.1 In this contribution, continuation of the study of the electrochemical separation of U from Gd in the LiF-CaF2 molten system by the modulated current electrolysis is presented.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

<a href="/cs/project/TH02020113" target="_blank" >TH02020113: Výzkum a vývoj technologie jaderných reaktorů chlazených fluoridovými solemi</a><br>

Návaznosti

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

Rok uplatnění

2018

Kód důvěrnosti údajů

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

Název statě ve sborníku

Transactions of the American Nuclear Society

ISBN

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ISSN

0003-018X

e-ISSN

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Počet stran výsledku

2

Strana od-do

118-119

Název nakladatele

American Nuclear Society

Místo vydání

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Místo konání akce

Philladelphia, USA

Datum konání akce

17. 6. 2018

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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