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

The result's identifiers

  • Result code in 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>

  • Result on the web

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

  • DOI - Digital Object Identifier

Alternative languages

  • Result language

    angličtina

  • Original language name

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

  • Original language description

    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.

  • Czech name

  • Czech description

Classification

  • Type

    D - Article in proceedings

  • CEP classification

  • OECD FORD branch

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

Result continuities

  • Project

    <a href="/en/project/TH02020113" target="_blank" >TH02020113: Research and development of fluoride salt-cooled nuclear reactor systems</a><br>

  • Continuities

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

Others

  • Publication year

    2018

  • Confidentiality

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

Data specific for result type

  • Article name in the collection

    Transactions of the American Nuclear Society

  • ISBN

  • ISSN

    0003-018X

  • e-ISSN

  • Number of pages

    2

  • Pages from-to

    118-119

  • Publisher name

    American Nuclear Society

  • Place of publication

  • Event location

    Philladelphia, USA

  • Event date

    Jun 17, 2018

  • Type of event by nationality

    WRD - Celosvětová akce

  • UT code for WoS article