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Evaluation of long-term exposure of 310S and 800H under conditions of SCW-SMR

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F26%3AN0000003" target="_blank" >RIV/26722445:_____/26:N0000003 - isvavai.cz</a>

  • Result on the web

    <a href="https://www.sciencedirect.com/science/article/pii/S0029549325008684" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0029549325008684</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.nucengdes.2025.114691" target="_blank" >10.1016/j.nucengdes.2025.114691</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    Evaluation of long-term exposure of 310S and 800H under conditions of SCW-SMR

  • Original language description

    Austenitic stainless steels 310S and Alloy 800H are considered promising candidates for fuel cladding in Small Modular Reactors cooled by Supercritical Water due to their high corrosion resistance and favourable mechanical properties. To evaluate their long-term behaviour in supercritical water environments, full-length tube samples were exposed to supercritical water at 500 °C, 25 MPa, and 150 ppb dissolved oxygen for up to 10,000 h. Weight gain measurements revealed a decelerating oxidation rate over time, with low cumulative mass increases indicative of excellent corrosion resistance. Conservative extrapolation suggests that the wall penetration depth is projected to remain below 5 μm after 30,000 h for both alloys, supporting the expectation of long-term structural integrity. Surface roughness measurements corroborated these trends: 310S showed a gradual increase from 0.18 μm (as received) to 0.29 μm after 10,000 h, whereas 800H exhibited minimal change, attributed to its initially higher surface roughness. Post-exposure characterization by Scanning Electron Microscope with Energy-Dispersive X-ray Spectroscopy and Transmission Electron Microscope confirmed the formation of compact, chromium-rich oxide layers (Cr₂O₃) on both materials, with underlying Cr-depleted zones. Microstructural analysis revealed that 310S developed thicker oxide layer with larger grains and Cr-Ni-rich phases, whereas 800H exhibited finer oxide grains in a thinner layer, with occasional localized corrosion – nodules. These differences underscore the role of alloy composition in oxidation behaviour under supercritical water conditions. Overall, both 310S and 800H demonstrate excellent oxidation resistance and microstructural stability, reinforcing their applicability as fuel cladding materials in Small Modular Reactors cooled by Supercritical Water designs.

  • 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

    20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Result continuities

  • Project

  • Continuities

    I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Others

  • Publication year

    2026

  • Confidentiality

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

Data specific for result type

  • Name of the periodical

    Nuclear Engineering and Design

  • ISSN

    0029-5493

  • e-ISSN

    1872-759X

  • Volume of the periodical

    448

  • Issue of the periodical within the volume

    March

  • Country of publishing house

    CH - SWITZERLAND

  • Number of pages

    12

  • Pages from-to

    1-12

  • UT code for WoS article

    001653860700001

  • EID of the result in the Scopus database

    2-s2.0-105025665095