Mock-Up-Josef: Large Scale In-situ model of a Deep Repository Bentonite Based Barrier
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21110%2F11%3A00188331" target="_blank" >RIV/68407700:21110/11:00188331 - isvavai.cz</a>
Výsledek na webu
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DOI - Digital Object Identifier
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Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Mock-Up-Josef: Large Scale In-situ model of a Deep Repository Bentonite Based Barrier
Popis výsledku v původním jazyce
Mock-up-Josef can be classified as a large-scale in-situ test which represents a model of bentonite barrier of radioactive waste disposal. The experiment is located in the Josef underground laboratory (www.uef-josef.eu). The model's disposal well, whichis 2.3m deep and 0.75m in diameter, will be filled with highly-compacted blocks of montmorillonite clay - Czech bentonite B75. A cylindrically-shaped space will be retained in the centre of the bentonite blocks in which a heater will be installed the function of which will be to replicate the canister containing heat-generating radioactive waste (spent nuclear fuel). Subsequently, the bentonite barrier and the heater will be covered with additional layers of highly-compacted bentonite blocks and an extensive system for the monitoring of a number of parameters including temperature, moisture, and swelling pressure will be installed. It is planned that all the components of the experiment (blocks, heater and monitoring system) will be put
Název v anglickém jazyce
Mock-Up-Josef: Large Scale In-situ model of a Deep Repository Bentonite Based Barrier
Popis výsledku anglicky
Mock-up-Josef can be classified as a large-scale in-situ test which represents a model of bentonite barrier of radioactive waste disposal. The experiment is located in the Josef underground laboratory (www.uef-josef.eu). The model's disposal well, whichis 2.3m deep and 0.75m in diameter, will be filled with highly-compacted blocks of montmorillonite clay - Czech bentonite B75. A cylindrically-shaped space will be retained in the centre of the bentonite blocks in which a heater will be installed the function of which will be to replicate the canister containing heat-generating radioactive waste (spent nuclear fuel). Subsequently, the bentonite barrier and the heater will be covered with additional layers of highly-compacted bentonite blocks and an extensive system for the monitoring of a number of parameters including temperature, moisture, and swelling pressure will be installed. It is planned that all the components of the experiment (blocks, heater and monitoring system) will be put
Klasifikace
Druh
O - Ostatní výsledky
CEP obor
JN - Stavebnictví
OECD FORD obor
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Návaznosti výsledku
Projekt
<a href="/cs/project/FR-TI1%2F362" target="_blank" >FR-TI1/362: Výzkum vlastností materiálů pro bezpečné ukládání radioaktivních odpadů a vývoj postupů jejich hodnocení</a><br>
Návaznosti
Z - Vyzkumny zamer (s odkazem do CEZ)
Ostatní
Rok uplatnění
2011
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů