Treatment of spent decontamination solutions based on citric acid with composite polyacrylonitrile: transient metal oxidic nanoparticles sorbents

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F29372259%3A_____%2F22%3AN0000030" target="_blank" >RIV/29372259:_____/22:N0000030 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21340/23:00360616

Výsledek na webu

<a href="https://link.springer.com/article/10.1007/s10967-022-08598-2" target="_blank" >https://link.springer.com/article/10.1007/s10967-022-08598-2</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1007/s10967-022-08598-2" target="_blank" >10.1007/s10967-022-08598-2</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Treatment of spent decontamination solutions based on citric acid with composite polyacrylonitrile: transient metal oxidic nanoparticles sorbents

Popis výsledku v původním jazyce

Composite sorbents based on the nanoparticles of NiO, NiO–TiO2 and ZrO2–TiO2 embedded in polyacrylonitrile were chosen for the treatment of spent decontamination solutions based on citric acid. Active oxidic materials were prepared by photoinduced synthesis (NiO, NiO–TiO2) or hydrolytic method (ZrO2–TiO2). Weight distribution ratios for radionuclides 241Am, 60Co, 137Cs and 90Sr/90Y were investigated during the experiments performed in pH range 2–12. High sorption capacities up to 9 mmol g–1 for 137Cs were found by sorption isotherm experiments. Dynamic experiments were carried out with simulated spent decontamination solutions containing citric acid. Elution of > 85% radionuclide waste with mineral acids or complexing agents was in 5–6 times lower volume compared to treated spent solution.

Název v anglickém jazyce

Treatment of spent decontamination solutions based on citric acid with composite polyacrylonitrile: transient metal oxidic nanoparticles sorbents

Popis výsledku anglicky

Composite sorbents based on the nanoparticles of NiO, NiO–TiO2 and ZrO2–TiO2 embedded in polyacrylonitrile were chosen for the treatment of spent decontamination solutions based on citric acid. Active oxidic materials were prepared by photoinduced synthesis (NiO, NiO–TiO2) or hydrolytic method (ZrO2–TiO2). Weight distribution ratios for radionuclides 241Am, 60Co, 137Cs and 90Sr/90Y were investigated during the experiments performed in pH range 2–12. High sorption capacities up to 9 mmol g–1 for 137Cs were found by sorption isotherm experiments. Dynamic experiments were carried out with simulated spent decontamination solutions containing citric acid. Elution of > 85% radionuclide waste with mineral acids or complexing agents was in 5–6 times lower volume compared to treated spent solution.

Druh

J_ost - Ostatní články v recenzovaných periodicích

CEP obor

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OECD FORD obor

10402 - Inorganic and nuclear chemistry

Projekt

<a href="/cs/project/VI20172020106" target="_blank" >VI20172020106: Kompozitní filtry pro čištění radioaktivních oplachových roztoků</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2022

Kód důvěrnosti údajů

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

Název periodika

Journal of Radioanalytical and Nuclear Chemistry

ISSN

0236-5731

e-ISSN

1588-2780

Svazek periodika

—

Číslo periodika v rámci svazku

332

Stát vydavatele periodika

NL - Nizozemsko

Počet stran výsledku

7

Strana od-do

1541–1547

Kód UT WoS článku

—

EID výsledku v databázi Scopus

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