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Progress in experimental development of MSR fuel cycle technology

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F19%3AN0000090" target="_blank" >RIV/26722445:_____/19:N0000090 - isvavai.cz</a>

  • Result on the web

  • DOI - Digital Object Identifier

Alternative languages

  • Result language

    angličtina

  • Original language name

    Progress in experimental development of MSR fuel cycle technology

  • Original language description

    The paper describes the existing and present activities in the area of R&D of fresh thorium – uranium liquid fuel processing, experimental studies of electrochemical separation applicable for on-line reprocessing and the theoretical studies of the mutual link between the MSR reactor physics and chemical reprocessing technology. First part describes the preparation of UF4 and ThF4 by the hydrofluorination of uranium and thorium dioxides and final preparation of liquid MSR fuel for the experimental neutronics and irradiation tests done in the research reactors LR-0 and LVR-15. Second part is devoted to the investigation and studies of the electrochemical separation processes in fluoride media suitable for utilization within the MSR on-line reprocessing technology. Final part is focused on the evaluation of the technologies discussed above and on the mutual link between the MSR physics and the reprocessing technology to reach the optimized removal of neutronic poisons and maximal breeding of new fissile material. A conceptual design of the on-line reprocessing technology of the MSR – thorium breeder system and the non-proliferation aspects are discussed as well.

  • 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

    2019

  • Confidentiality

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

Data specific for result type

  • Article name in the collection

    Global/Top Fuel 2019 Seattle, WA, September 22-2, 2019

  • ISBN

    978-0-89448-771-2

  • ISSN

  • e-ISSN

  • Number of pages

    4

  • Pages from-to

    275-278

  • Publisher name

    American Nuclear Society

  • Place of publication

  • Event location

    Seattle, USA

  • Event date

    Sep 22, 2019

  • Type of event by nationality

    WRD - Celosvětová akce

  • UT code for WoS article