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
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Czech description
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Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
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OECD FORD branch
20501 - Materials engineering
Result continuities
Project
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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
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UT code for WoS article
000806174600012
EID of the result in the Scopus database
2-s2.0-85126048104