Verification of Reverse Osmosis Technology for Treating Primary Coolant in Temelín Nuclear Power Plant

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F24%3AN0000056" target="_blank" >RIV/26722445:_____/24:N0000056 - isvavai.cz</a>

Výsledek na webu

<a href="https://www.msrjournal.com/article_711360.html" target="_blank" >https://www.msrjournal.com/article_711360.html</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.22079/jmsr.2024.2006986.1619" target="_blank" >10.22079/jmsr.2024.2006986.1619</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Verification of Reverse Osmosis Technology for Treating Primary Coolant in Temelín Nuclear Power Plant

Popis výsledku v původním jazyce

Drained primary coolant from nuclear power plants containing boric acid is currently treated in the system of evaporators and by ion exchangers. Their operation is expensive, therefore other alternatives are examined, e.g. reverse osmosis. Using reverse osmosis, the feed primary coolant is separated into two output streams: retentate and permeate. Retentate stream consists of concentrated boric acid solution together with other components, while permeate stream consists of purified water. A pilot-plant unit of reverse osmosis was tested in Temelin nuclear power plant. It was installed in the Special Purification System SVO-6 for the regeneration of boric acid. Three experimental tests with real primary coolant of various composition and total radioactivity were performed across a wide range of feed primary coolant pH and with various total flows through the membrane modulus and recoveries (ratio of permeate flow rate to feed flow rate). During the tests, samples of output streams were taken and analysed for chemical parameters (conductivity and H3BO3, NH3, K and Li concentrations) and radioactivity parameters (total radioactivity and radioactivity and concentration of Cs-134 and Cs-137 isotopes). The aim of the tests performed in Temelin nuclear power plant was to verify possible use of reverse osmosis for the treatment of primary coolant, i.e. to obtain a concentrated solution of boric acid in the retentate stream and permeate stream pure of boric acid.

Název v anglickém jazyce

Verification of Reverse Osmosis Technology for Treating Primary Coolant in Temelín Nuclear Power Plant

Popis výsledku anglicky

Drained primary coolant from nuclear power plants containing boric acid is currently treated in the system of evaporators and by ion exchangers. Their operation is expensive, therefore other alternatives are examined, e.g. reverse osmosis. Using reverse osmosis, the feed primary coolant is separated into two output streams: retentate and permeate. Retentate stream consists of concentrated boric acid solution together with other components, while permeate stream consists of purified water. A pilot-plant unit of reverse osmosis was tested in Temelin nuclear power plant. It was installed in the Special Purification System SVO-6 for the regeneration of boric acid. Three experimental tests with real primary coolant of various composition and total radioactivity were performed across a wide range of feed primary coolant pH and with various total flows through the membrane modulus and recoveries (ratio of permeate flow rate to feed flow rate). During the tests, samples of output streams were taken and analysed for chemical parameters (conductivity and H3BO3, NH3, K and Li concentrations) and radioactivity parameters (total radioactivity and radioactivity and concentration of Cs-134 and Cs-137 isotopes). The aim of the tests performed in Temelin nuclear power plant was to verify possible use of reverse osmosis for the treatment of primary coolant, i.e. to obtain a concentrated solution of boric acid in the retentate stream and permeate stream pure of boric acid.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

10402 - Inorganic and nuclear chemistry

Projekt

<a href="/cs/project/LM2023041" target="_blank" >LM2023041: České mezinárodní centrum výzkumných reaktorů</a><br>

Návaznosti

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

Rok uplatnění

2024

Kód důvěrnosti údajů

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

Název periodika

Journal of Membrane Science and Research

ISSN

2476-5406

e-ISSN

—

Svazek periodika

10

Číslo periodika v rámci svazku

3

Stát vydavatele periodika

IR - Íránská islámská republika

Počet stran výsledku

6

Strana od-do

1-6

Kód UT WoS článku

000579333500067

EID výsledku v databázi Scopus

2-s2.0-85199573878