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

The result's identifiers

  • Result code in 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>

  • Result on the web

    <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>

Alternative languages

  • Result language

    angličtina

  • Original language name

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

  • Original language description

    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.

  • Czech name

  • Czech description

Classification

  • Type

    J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database

  • CEP classification

  • OECD FORD branch

    10402 - Inorganic and nuclear chemistry

Result continuities

  • Project

    <a href="/en/project/LM2023041" target="_blank" >LM2023041: Czech International Centre of Research Reactors</a><br>

  • Continuities

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

Others

  • Publication year

    2024

  • Confidentiality

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

Data specific for result type

  • Name of the periodical

    Journal of Membrane Science and Research

  • ISSN

    2476-5406

  • e-ISSN

  • Volume of the periodical

    10

  • Issue of the periodical within the volume

    3

  • Country of publishing house

    IR - IRAN, ISLAMIC REPUBLIC OF

  • Number of pages

    6

  • Pages from-to

    1-6

  • UT code for WoS article

    000579333500067

  • EID of the result in the Scopus database

    2-s2.0-85199573878