The development of sprayed clay technology with Respect to deep repositories for radioactive waste

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21110%2F12%3A00196625" target="_blank" >RIV/68407700:21110/12:00196625 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21110/12:00196631

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

The development of sprayed clay technology with Respect to deep repositories for radioactive waste

Popis výsledku v původním jazyce

The investigation of sprayed clay technology has been underway at the Josef Underground Laboratory for a number of years. This technology was developed principally with respect to the backfilling of shafts and galleries in deep repositories providing access to disposal wells containing high-level long-lived radioactive waste. At present research is being focused on the use of this technology to fill the space between the spent fuel container and the wall of the disposal well. It is currently envisaged that the spent fuel canister will be surrounded by prefabricates made of highly-compacted bentonite; however a barrier consisting of such blocks has the disadvantage of featuring a large number of discontinuities, i.e. joints. Research suggests that the discontinuities will become sealed due to the self-healing ability of bentonite. However the possibility cannot be discounted that even following self-sealing, preferential paths will remain which might allow radionuclide migration. As par

Název v anglickém jazyce

The development of sprayed clay technology with Respect to deep repositories for radioactive waste

Popis výsledku anglicky

The investigation of sprayed clay technology has been underway at the Josef Underground Laboratory for a number of years. This technology was developed principally with respect to the backfilling of shafts and galleries in deep repositories providing access to disposal wells containing high-level long-lived radioactive waste. At present research is being focused on the use of this technology to fill the space between the spent fuel container and the wall of the disposal well. It is currently envisaged that the spent fuel canister will be surrounded by prefabricates made of highly-compacted bentonite; however a barrier consisting of such blocks has the disadvantage of featuring a large number of discontinuities, i.e. joints. Research suggests that the discontinuities will become sealed due to the self-healing ability of bentonite. However the possibility cannot be discounted that even following self-sealing, preferential paths will remain which might allow radionuclide migration. As par

Druh

O - Ostatní výsledky

CEP obor

JN - Stavebnictví

OECD FORD obor

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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

S - Specificky vyzkum na vysokych skolach

Rok uplatnění

2012

Kód důvěrnosti údajů

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