Author:
Antók Csenge,Czifrus Szabolcs,Giusti Valerio
Funder
Horizon 2020 Framework Programme
Karlsruhe Institute of Technology
Euratom Research and Training Programme
Reference15 articles.
1. Revealing the oxidation mechanism of 310S stainless steel in supercritical water via high-resolution characterization;Chen;Corros. Sci.,2022
2. ECC-SMART project website. (accessed 28.04.2024).
3. M. Griffiths, R. Boothby, Radiation Effects in Nickel-Based Alloys, in R.J.M. Konings, R.E. Stoller (Eds.), Comprehensive Nuclear Materials, Second Edition, vol. 3, Elsevier, Oxford, 2020, 334-371, doi:10.1016/B978-0-12-803581-8.11705-9.
4. Supercritical water-cooled reactor materials – Summary of research and open issues;Guzonas;Progr. Nucl. Energy,2014
5. Gy. Csom, Atomerőművek üzemtana II. kötet: Az energetikai atomreaktorok üzemtana 1. rész (Operation of nuclear power plants II.: Operation of power reactors 1.), Műegyetem Kiadó, Budapest, 2005 (Chapter 8) (in Hungarian).