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

Kód výsledku v 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>

Výsledek na webu

<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>

Jazyk výsledku

angličtina

Název v původním jazyce

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

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

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

Popis výsledku anglicky

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.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

20501 - Materials engineering

Projekt

—

Návaznosti

V - Vyzkumna aktivita podporovana z jinych verejnych zdroju

Rok uplatnění

2022

Kód důvěrnosti údajů

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

Název periodika

Annals of Nuclear Energy

ISSN

0306-4549

e-ISSN

1873-2100

Svazek periodika

172

Číslo periodika v rámci svazku

July

Stát vydavatele periodika

GB - Spojené království Velké Británie a Severního Irska

Počet stran výsledku

12

Strana od-do

—

Kód UT WoS článku

000806174600012

EID výsledku v databázi Scopus

2-s2.0-85126048104