Bentonite sterilization methods in relation to geological disposal of radioactive waste: comparative efficiency of dry heat and gamma radiation
Jazyk angličtina Země Anglie, Velká Británie Médium print
Typ dokumentu časopisecké články, srovnávací studie
Grantová podpora
TK02010169
Technology Agency of the Czech Republic
PubMed
40042982
DOI
10.1093/jambio/lxaf051
PII: 8052799
Knihovny.cz E-zdroje
- Klíčová slova
- abiotic stress, hazardous waste, microbial diversity, radiation, sterilization,
- MeSH
- Bacteria * účinky záření MeSH
- bentonit * účinky záření MeSH
- radioaktivní odpad * MeSH
- sterilizace * metody MeSH
- vysoká teplota MeSH
- záření gama * MeSH
- Publikační typ
- časopisecké články MeSH
- srovnávací studie MeSH
- Názvy látek
- bentonit * MeSH
- radioaktivní odpad * MeSH
AIMS: This study evaluates the effectiveness of two standard sterilization methods on microorganisms in bentonite, which is proposed as a buffer around metal canisters containing long-lived radioactive waste. Bentonite, as a natural clay, contains microorganisms with enhanced resistance to harsh conditions and the ability to reactivate upon decompaction. Sterile controls are crucial in experiments estimating the impact of microorganisms on nuclear waste repositories. Yet, the effectiveness of common sterilization methods on bentonite microorganisms has not been fully evaluated. METHODS AND RESULTS: Two methods were compared: dry heat (nine cycles at 121°C for 4 h) and gamma irradiation (10-140 kGy at 147 Gy·min-1). Molecular-genetic, microscopic, and cultivation techniques were used to assess sterilization. Heat sterilization did not eliminate heat-resistant microorganisms, such as Bacillus, Paenibacillus, and Terribacillus, from bentonite powder even after nine heat cycles. However, bentonite suspended in deionized water was sterile after four heat cycles. In contrast, gamma irradiation effectively reduced microbial survivability above a dose of 10 kGy, with the highest doses (100-140 kGy) potentially degrading DNA. CONCLUSIONS: Gamma irradiation at 30 kGy effectively sterilized bentonite powder. The findings of our experiments emphasize the importance of using appropriate sterilization methods to maintain sterile controls in experiments that evaluate the microbial impacts in nuclear waste repositories. However, further assessment is needed to determine the effects of potential alterations induced by gamma radiation on bentonite properties.
Disposal Processes and Safety ÚJV Řež a s Hlavní 130 250 68 Husinec Czech Republic
Research and Development Department UJP PRAHA a s Nad Kamínkou 1345 156 00 Prague Czech Republic
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