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Melting behaviour of simulated radioactive waste as functions of different redox iron-bearing raw materials

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F67985891%3A_____%2F22%3A00562746" target="_blank" >RIV/67985891:_____/22:00562746 - isvavai.cz</a>

  • Alternative codes found

    RIV/60461373:22310/22:43925588

  • Result on the web

    <a href="https://www.sciencedirect.com/science/article/pii/S0022311522004329" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0022311522004329</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.jnucmat.2022.153946" target="_blank" >10.1016/j.jnucmat.2022.153946</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    Melting behaviour of simulated radioactive waste as functions of different redox iron-bearing raw materials

  • Original language description

    Improved understanding of the mechanisms by which foaming occurs during vitrification of high-level radioactive waste feeds prior to operation of the Waste Treatment and Immobilization Plant at the Hanford Site, USA, will help to obviate operational issues and reduce the duration of the clean-up project by enhancing the feed-to-glass conversion. The HLW-NG-Fe2 high-iron simulated waste feed has been shown to exhibit excessive foaming, and the most recent predictive models overestimate the feed melting rate. The influence of delivering iron as a Fe2+-bearing raw material (FeC2O4 center dot 2H(2)O), rather than a Fe3+ (Fe(OH)(3)) material, was evaluated in terms of the effects on foaming during melting, to improve understanding of the mechanisms of foam production. A decrease of 50.0 +/- 10.8% maximum generated foam volume is observed using FeC2O4 center dot 2H(2)O as the iron source, compared with Fe(OH)(3). This is determined to be due to a large release of CO2 before the foam onset temperature (the temperature above which the liquid phases forming are sufficiently viscous to trap the gases) and suppression of O-2 evolution during foam collapse. Structural analyses of simulated waste feeds after different stages of melting show that the remaining Fe2+ in the modified feed is oxidised to Fe3+ at temperatures between 600 and 800 degrees C. This feed was tested in a Laboratory Scale Melter with no excessive foaming or feeding issues. Analysis of the final glass products indicates that the glasses produced using the original HLW-NG-Fe-2 feed using Fe(OH)(3) and the feed made with FeC2O4 center dot 2H(2)O are structurally similar but not identical: the difference in the structure converges when the glass is melted for 24 h, suggesting a transient structure slightly different to that of the baseline in the glass produced using the reduced raw material. (c) 2022 The Author(s). Published by Elsevier B.V. This is an open access article under the CC BY license (http://creativecommons.org/licenses/by/4.0/)

  • 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

    20504 - Ceramics

Result continuities

  • Project

  • Continuities

    I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Others

  • Publication year

    2022

  • 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 Nuclear Materials

  • ISSN

    0022-3115

  • e-ISSN

    1873-4820

  • Volume of the periodical

    569

  • Issue of the periodical within the volume

    OCT

  • Country of publishing house

    NL - THE KINGDOM OF THE NETHERLANDS

  • Number of pages

    21

  • Pages from-to

    153946

  • UT code for WoS article

    000864543400006

  • EID of the result in the Scopus database

    2-s2.0-85135302153