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In-situ testing of Czech bentonite for radioactive waste disposal in Mock-up Josef experiment

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21110%2F22%3A00356527" target="_blank" >RIV/68407700:21110/22:00356527 - isvavai.cz</a>

  • Result on the web

    <a href="https://doi.org/10.1016/j.anucene.2022.109059" target="_blank" >https://doi.org/10.1016/j.anucene.2022.109059</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.anucene.2022.109059" target="_blank" >10.1016/j.anucene.2022.109059</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    In-situ testing of Czech bentonite for radioactive waste disposal in Mock-up Josef experiment

  • Original language description

    The Mock-up Josef experiment is an in-situ physical model aimed at studying Czech Ca-Mg bentonite heated to 90 °C. The main objectives of the experiment were in-situ demonstration of a system for safe disposal of spent nuclear fuel, study the behavior of a bentonite barrier under repository conditions (loading of bentonite by temperature and by saturation of water) and obtaining data for mathematical modelling. In order to monitor the various ongoing processes, temperature, pressure and relative humidity sensors were installed within the whole experiment. And it is clear from the data provided by the sensors to date that a most of the processes in bentonite (saturation, temperature evolution) and in surrounding rock mass (temperature evolution) have been mostly stabilised after 8 years. During the experiment, bentonite samples were collected and analysed to determine possible changes in bentonite barrier properties. From the laboratory analyses of the samples a slight change in swelling pressure and hydraulic conductivity was evident, which does not indicate the bentonite degradation.

  • Czech name

  • Czech description

Classification

  • Type

    J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database

  • CEP classification

  • OECD FORD branch

    20501 - Materials engineering

Result continuities

  • Project

  • Continuities

    V - Vyzkumna aktivita podporovana z jinych verejnych zdroju

Others

  • Publication year

    2022

  • Confidentiality

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

Data specific for result type

  • Name of the periodical

    Annals of Nuclear Energy

  • ISSN

    0306-4549

  • e-ISSN

    1873-2100

  • Volume of the periodical

    172

  • Issue of the periodical within the volume

    July

  • Country of publishing house

    GB - UNITED KINGDOM

  • Number of pages

    12

  • Pages from-to

  • UT code for WoS article

    000806174600012

  • EID of the result in the Scopus database

    2-s2.0-85126048104