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Melting of Fe and Gd oxide loaded geopolymers with nuclear fuel for ex-vessel core catcher systems

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F61388980%3A_____%2F25%3A00637295" target="_blank" >RIV/61388980:_____/25:00637295 - isvavai.cz</a>

  • Alternative codes found

    RIV/26722445:_____/25:N0000069 RIV/00216208:11310/25:10499743

  • Result on the web

    <a href="https://www.sciencedirect.com/science/article/pii/S0306454925004190" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0306454925004190</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.anucene.2025.111602" target="_blank" >10.1016/j.anucene.2025.111602</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    Melting of Fe and Gd oxide loaded geopolymers with nuclear fuel for ex-vessel core catcher systems

  • Original language description

    Geopolymers have demonstrated a significant potential in various fields of the nuclear industry. They can serve as enhanced sacrificial materials offering increased safety and mitigating consequences in a hypothetical severe nuclear accident. Additionally, geopolymers show potential use as immobilization matrixes for radioactive waste disposal due to their advantageous properties and polymeric structures. Their properties, including high gamma radiation resistance, low water content, and the ability to incorporate various elements and species to customize their physico-chemical properties, suggest that geopolymers may be applied for various systems, e.g. sacrificial materials for core catchers of current or future plant concepts. However, further research is required to fully understand the interaction between geopolymers and corium melts, to describe their physico-chemical properties at extreme temperatures, high-temperature phase behaviour, etc. In present manuscript, we focused on geopolymers with embedded Gd<inf>2</inf>O<inf>3</inf> and Fe<inf>2</inf>O<inf>3</inf> as neutron absorber and functional melt modifier, respectively. Such composite could be a convenient sacrificial material for ex-vessel core catcher systems. We conducted two midscale melting experiments of geopolymer mixtures with prototypic corium to estimate the solidus and liquidus of the mixture and asses the phase behaviour. The mixture of geopolymer and prototypic corium showed similarities to previously described corium-concrete systems with solidus temperature around 1500 °C and liquidus around 1900 °C. A miscibility gap was present in the system between the oxide and iron melt. Iron melt solidified into a large block, but to microdroplets as well. Three distinct phases (silicate-rich, uranium-rich and metallic) were observed in the ingots. The geopolymer materials appeared to have prospective properties from melting and phase point of view, thus deserve further attention in the severe accident R&D.

  • 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/TK01030130" target="_blank" >TK01030130: New inorganic material for the nuclear industry</a><br>

  • Continuities

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

Others

  • Publication year

    2025

  • Confidentiality

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

Data specific for result type

  • Name of the periodical

    Annals of Nuclear Energy

  • ISSN

    0306-4549

  • e-ISSN

    1873-2100

  • Volume of the periodical

    223

  • Issue of the periodical within the volume

    DEC

  • Country of publishing house

    GB - UNITED KINGDOM

  • Number of pages

    11

  • Pages from-to

    111602

  • UT code for WoS article

    001525611200003

  • EID of the result in the Scopus database

    2-s2.0-105008826404