Stress Corrosion Cracking Behavior of Stainless Steel 310S in Supercritical Water

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F23%3AN0000085" target="_blank" >RIV/26722445:_____/23:N0000085 - isvavai.cz</a>
Result on the web
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DOI - Digital Object Identifier
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Result language
angličtina
Original language name
Stress Corrosion Cracking Behavior of Stainless Steel 310S in Supercritical Water
Original language description
Recent interest in nuclear power technologies is directed to small modular reactors (SMR). The possible and believed option is the one cooled by supercritical water (SCW-SMR). The main objectives of the project ECC-SMART, which is based on SCW technology, are to define the design requirements for the future SCW-SMR, to develop the pre-licensing study and guidelines for the demonstration of safety in the further development stages of the SCW-SMR concept. Based on the scientific results, the stainless steel 310S and other alloys have been selected as the most promising commercially produced materials for application as the cladding material in SCW-SMR. Slow strain rate tests in combination with scanning electron microscopy were used to evaluate the stress corrosion cracking (SCC) susceptibility in SCW. Presented at Nuclear Energy for New Europe, NENE 2023, Portorož, Slovenia.
Czech name
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Czech description
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Publication year
2023
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

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