Applicability of anion exchange resin used at nuclear power plants for separating iodides from solutions containing boric acid 

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F25%3AN0000023" target="_blank" >RIV/26722445:_____/25:N0000023 - isvavai.cz</a>

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/pii/S1738573325000294" target="_blank" >https://www.sciencedirect.com/science/article/pii/S1738573325000294</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.net.2025.103461" target="_blank" >10.1016/j.net.2025.103461</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Applicability of anion exchange resin used at nuclear power plants for separating iodides from solutions containing boric acid 

Popis výsledku v původním jazyce

At nuclear power plants, boric acid is used as a moderator of nuclear reactions, and iodine species are formed as products of fission reactions in the fuel rods. If many fuel rods were broken during the reactor operation or in the case of a nuclear accident, an increase of radioactivity associated with an increase of iodides concentration in the primary coolant could endanger reactor operation. Therefore, we examined the applicability and efficiency of the ion exchange resin DuPontTM AmberliteTM IRN78 OH, which is already in use at Czech nuclear power plants, for the separation of iodides from solutions containing boric acid. We performed a set of experiments with various iodides and boric acid concentrations, with two different ion exchange resin loads, and at two different temperatures. Sorption isotherm experiments were used to evaluate the removal efficiency of the ion exchanger for iodides and for boric acid, as well as to fit the Langmuir isotherm. Kinetic experiments were used to study the kinetics of the adsorption on the ion exchanger, as well as to investigate the mechanism of iodides adsorption on the ion exchange resin - pseudo-first order, pseudo-second order, and intra-particle diffusion models were applied to the experimental data.

Název v anglickém jazyce

Applicability of anion exchange resin used at nuclear power plants for separating iodides from solutions containing boric acid 

Popis výsledku anglicky

At nuclear power plants, boric acid is used as a moderator of nuclear reactions, and iodine species are formed as products of fission reactions in the fuel rods. If many fuel rods were broken during the reactor operation or in the case of a nuclear accident, an increase of radioactivity associated with an increase of iodides concentration in the primary coolant could endanger reactor operation. Therefore, we examined the applicability and efficiency of the ion exchange resin DuPontTM AmberliteTM IRN78 OH, which is already in use at Czech nuclear power plants, for the separation of iodides from solutions containing boric acid. We performed a set of experiments with various iodides and boric acid concentrations, with two different ion exchange resin loads, and at two different temperatures. Sorption isotherm experiments were used to evaluate the removal efficiency of the ion exchanger for iodides and for boric acid, as well as to fit the Langmuir isotherm. Kinetic experiments were used to study the kinetics of the adsorption on the ion exchanger, as well as to investigate the mechanism of iodides adsorption on the ion exchange resin - pseudo-first order, pseudo-second order, and intra-particle diffusion models were applied to the experimental data.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

10402 - Inorganic and nuclear chemistry

Projekt

—

Návaznosti

N - Vyzkumna aktivita podporovana z neverejnych zdroju

Rok uplatnění

2025

Kód důvěrnosti údajů

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

Název periodika

Nuclear Engineering and Technology

ISSN

1738-5733

e-ISSN

—

Svazek periodika

57

Číslo periodika v rámci svazku

6

Stát vydavatele periodika

KR - Korejská republika

Počet stran výsledku

8

Strana od-do

1-8

Kód UT WoS článku

001455142700001

EID výsledku v databázi Scopus

2-s2.0-85215558662