{"status":"ok","message-type":"work","message-version":"1.0.0","message":{"indexed":{"date-parts":[[2026,1,18]],"date-time":"2026-01-18T11:12:55Z","timestamp":1768734775254,"version":"3.49.0"},"reference-count":41,"publisher":"MDPI AG","issue":"7","license":[{"start":{"date-parts":[[2023,3,24]],"date-time":"2023-03-24T00:00:00Z","timestamp":1679616000000},"content-version":"vor","delay-in-days":0,"URL":"https:\/\/creativecommons.org\/licenses\/by\/4.0\/"}],"funder":[{"name":"State Corporation \u201cRosatom\u201d","award":["N.4sch.241.09.22.1130"],"award-info":[{"award-number":["N.4sch.241.09.22.1130"]}]}],"content-domain":{"domain":[],"crossmark-restriction":false},"short-container-title":["Materials"],"abstract":"<jats:p>The supercritical water-cooled reactors (SWCR) belong to Generation IV of reactors. These reactors have a number of advantages over currently operating WWERs and PWRs. These advantages include higher thermal efficiency, a more simplified unit design, and the possibility of incorporating it into a closed fuel cycle. It is therefore necessary to identify candidate materials for the SWCR and validate the safety and effectiveness of their use. 12Cr ferritic-martensitic (F\/M) stainless steel is considered a candidate material for SWCR internals. Radiation embrittlement and corrosion cracking in the primary circuit coolant environment are the main mechanisms of F\/M steels degradation during SWCR operation. Here, the stress corrosion cracking (SCC) in supercritical water at 390 and 550 \u00b0C of 12Cr F\/M steel irradiated by neutrons to 12 dpa is investigated. Autoclave tests of specially designed disk specimens in supercritical water were performed. The tests were carried out under different constant load (CL), temperature 450 \u00b0C, and pressure in autoclave 25 MPa. The threshold stress, below which the SCC initiation of irradiated 12Cr F\/M steel does not occur, was determined.<\/jats:p>","DOI":"10.3390\/ma16072585","type":"journal-article","created":{"date-parts":[[2023,3,24]],"date-time":"2023-03-24T06:34:07Z","timestamp":1679639647000},"page":"2585","update-policy":"https:\/\/doi.org\/10.3390\/mdpi_crossmark_policy","source":"Crossref","is-referenced-by-count":3,"title":["Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment"],"prefix":"10.3390","volume":"16","author":[{"ORCID":"https:\/\/orcid.org\/0000-0002-6589-8654","authenticated-orcid":false,"given":"Boris","family":"Margolin","sequence":"first","affiliation":[{"name":"Central Research Institute of Structural Materials \u201cPrometey\u201d of National Research Center \u201cKurchatov Institute\u201d, 191015 Saint-Petersburg, Russia"}],"role":[{"role":"author","vocabulary":"crossref"}]},{"ORCID":"https:\/\/orcid.org\/0000-0003-1199-826X","authenticated-orcid":false,"given":"Natalia","family":"Pirogova","sequence":"additional","affiliation":[{"name":"Central Research Institute of Structural Materials \u201cPrometey\u201d of National Research Center \u201cKurchatov Institute\u201d, 191015 Saint-Petersburg, Russia"}],"role":[{"role":"author","vocabulary":"crossref"}]},{"given":"Alexander","family":"Sorokin","sequence":"additional","affiliation":[{"name":"Central Research Institute of Structural Materials \u201cPrometey\u201d of National Research Center \u201cKurchatov Institute\u201d, 191015 Saint-Petersburg, Russia"}],"role":[{"role":"author","vocabulary":"crossref"}]},{"given":"Vasiliy","family":"Kokhonov","sequence":"additional","affiliation":[{"name":"Central Research Institute of Structural Materials \u201cPrometey\u201d of National Research Center \u201cKurchatov Institute\u201d, 191015 Saint-Petersburg, Russia"}],"role":[{"role":"author","vocabulary":"crossref"}]},{"given":"Alexey","family":"Dub","sequence":"additional","affiliation":[{"name":"Joint-Stock Company \u201cScience and Innovations\u201d, 115035 Moscow, Russia"}],"role":[{"role":"author","vocabulary":"crossref"}]},{"given":"Ivan","family":"Safonov","sequence":"additional","affiliation":[{"name":"Joint-Stock Company \u201cScience and Innovations\u201d, 115035 Moscow, Russia"}],"role":[{"role":"author","vocabulary":"crossref"}]}],"member":"1968","published-online":{"date-parts":[[2023,3,24]]},"reference":[{"key":"ref_1","first-page":"3","article-title":"Supercritical parameters\u2014The future of water-cooled reactors and nuclear power plants","volume":"6","author":"Kirillov","year":"2001","journal-title":"At. Tekhnika Rub."},{"key":"ref_2","doi-asserted-by":"crossref","first-page":"374","DOI":"10.1023\/B:ATEN.0000038101.90666.da","article-title":"Nuclear reactors with water at supercritical pressure","volume":"96","author":"Baranaev","year":"2004","journal-title":"At. Energy"},{"key":"ref_3","doi-asserted-by":"crossref","first-page":"277","DOI":"10.1023\/A:1016597709055","article-title":"VVER Units with Supercritical Coolant Parameters","volume":"92","author":"Dolgov","year":"2002","journal-title":"At. Energy"},{"key":"ref_4","doi-asserted-by":"crossref","first-page":"176","DOI":"10.1016\/j.jnucmat.2007.05.017","article-title":"Corrosion and stress corrosion cracking in supercritical water","volume":"371","author":"Was","year":"2007","journal-title":"J. Nucl. Mater."},{"key":"ref_5","doi-asserted-by":"crossref","unstructured":"Huang, Y., Zang, J., and Leung, L.K.-H. (2021). Super-Critical Water-Cooled Reactor (SCWR), Elsevier Inc.","DOI":"10.1016\/B978-0-12-819725-7.00020-9"},{"key":"ref_6","doi-asserted-by":"crossref","first-page":"349","DOI":"10.1007\/s10512-006-0089-1","article-title":"Reactor with a fast-resonance neutron spectrum, cooled by supercritical pressure water in a two-pass coolant motion scheme","volume":"100","author":"Glebov","year":"2006","journal-title":"At. Energy"},{"key":"ref_7","doi-asserted-by":"crossref","unstructured":"Guzonas, D., Novotny, R., Pentilla, S., Toivonen, A., and Zheng, W. (2018). Materials and Water Chemistry for Supercritical Water-Cooled Reactors, Elsevier Ltd.. Woodhead Publishing Is an Imprint of Elsevier.","DOI":"10.1016\/B978-0-08-102049-4.00004-0"},{"key":"ref_8","doi-asserted-by":"crossref","first-page":"351","DOI":"10.1016\/j.anucene.2018.12.007","article-title":"Corrosion resistance of candidate cladding materials for supercritical water reactor","volume":"127","author":"Guo","year":"2019","journal-title":"Ann. Nucl. Energy"},{"key":"ref_9","doi-asserted-by":"crossref","first-page":"361","DOI":"10.1016\/j.pnucene.2014.02.008","article-title":"Supercritical water-cooled reactor materials\u2014Summary of research and open issues","volume":"77","author":"Guzonas","year":"2014","journal-title":"Prog. Nucl. Energy Vol."},{"key":"ref_10","doi-asserted-by":"crossref","first-page":"177","DOI":"10.1016\/j.jnucmat.2007.03.168","article-title":"SCC and corrosion evaluations of the F\/M steels for a supercritical water reactor","volume":"372","author":"Hwang","year":"2008","journal-title":"J. Nucl. Mater."},{"key":"ref_11","doi-asserted-by":"crossref","first-page":"2508","DOI":"10.1016\/j.corsci.2009.07.007","article-title":"Progress in corrosion resistant materials for supercritical water reactors","volume":"51","author":"Sun","year":"2009","journal-title":"Corros. Sci."},{"key":"ref_12","unstructured":"Teysseyre, S. (2023, March 13). Corrosion Issues in Supercritical Water Reactor (SCWR) Systems. Available online: https:\/\/www.researchgate.net\/publication\/285986817_Corrosion_issues_in_supercritical_water_reactor_SCWR_systems."},{"key":"ref_13","doi-asserted-by":"crossref","first-page":"1221","DOI":"10.1016\/j.jnucmat.2011.02.033","article-title":"SCC behavior of austenitic and martensitic steels in supercritical pressurized water","volume":"417","author":"Muthukumar","year":"2011","journal-title":"J. Nucl. Mater."},{"key":"ref_14","doi-asserted-by":"crossref","first-page":"30","DOI":"10.1016\/j.jnucmat.2009.09.012","article-title":"Tensile and stress corrosion cracking behavior of ferritic-martensitic steels in supercritical water","volume":"395","author":"Ampornrat","year":"2009","journal-title":"J. Nucl. Mater."},{"key":"ref_15","unstructured":"Teysseyre, S., and Was, G.S. Available online: https:\/\/www.oecd-nea.org\/upload\/docs\/application\/pdf\/2019-12\/6260-smins2008.pdf."},{"key":"ref_16","unstructured":"Allen, T.R., Busby, J., and King, P.J. (2007). 13th International Conference on Degradation of Materials in Nuclear Power Systems\u2014Water Reactors, Canadian Nuclear Society."},{"key":"ref_17","doi-asserted-by":"crossref","first-page":"735","DOI":"10.1016\/j.actamat.2012.11.004","article-title":"Materials challenges in nuclear energy","volume":"61","author":"Zinkle","year":"2013","journal-title":"Acta Mater."},{"key":"ref_18","unstructured":"Kofstad, P. (1988). High Temperature Corrosion, Elsevier."},{"key":"ref_19","doi-asserted-by":"crossref","first-page":"104235","DOI":"10.1016\/j.engfailanal.2019.104235","article-title":"Analysis of mechanisms inducing corrosion cracking of irradiated austenitic steels and development of a model for prediction of crack initiation","volume":"107","author":"Margolin","year":"2020","journal-title":"Eng. Fail. Anal."},{"key":"ref_20","doi-asserted-by":"crossref","first-page":"568","DOI":"10.5006\/1.3280670","article-title":"Influence of Carbide Precipitation and Rolling Direction on Intergranular Stress Corrosion Cracking of Austenitic Stainless Steels in Hydrogenated High-Temperature Water","volume":"62","author":"Arioka","year":"2006","journal-title":"Corrosion"},{"key":"ref_21","doi-asserted-by":"crossref","first-page":"5361","DOI":"10.1016\/j.actamat.2009.07.040","article-title":"Multi-scale characterization of stress corrosion cracking of cold-worked stainless steels and the influence of Cr content","volume":"57","author":"Yamada","year":"2009","journal-title":"Acta Mater."},{"key":"ref_22","doi-asserted-by":"crossref","first-page":"1072","DOI":"10.1080\/18811248.2008.9711894","article-title":"IASCC Initiation in Highly Irradiated Stainless Steels under Uniaxial Constant Load Conditions","volume":"45","author":"Nishioka","year":"2008","journal-title":"J. Nucl. Sci. Technol."},{"key":"ref_23","unstructured":"Pogodin, V.P., Bogoyavlenskiy, V.L., and Sentyurev, V.P. (1970). Intergranular Corrosion and Stress Corrosion Cracking of Stainless Steels in Water Environment, Atomizdat. (In Russian)."},{"key":"ref_24","unstructured":"Logan, H.L. (1967). Stress Corrosion of Metals, John Wiley & Sons Inc."},{"key":"ref_25","first-page":"134","article-title":"Micromechanics of dislocation channeling in intergranular stress corrosion crack nucleation","volume":"16","author":"Was","year":"2012","journal-title":"J. Nucl. Mater."},{"key":"ref_26","doi-asserted-by":"crossref","first-page":"138","DOI":"10.1016\/j.jnucmat.2010.01.029","article-title":"Localized deformation as a key precursor to initiation of intergranular stress corrosion cracking of austenitic stainless steels employed in nuclear power plants","volume":"406","author":"Karlsen","year":"2010","journal-title":"J. Nucl. Mater."},{"key":"ref_27","doi-asserted-by":"crossref","first-page":"203","DOI":"10.1016\/j.jnucmat.2008.08.032","article-title":"Localized deformation and IASCC initiation in austenitic stainless steels","volume":"382","author":"Jiao","year":"2008","journal-title":"J. Nucl. Mater."},{"key":"ref_28","doi-asserted-by":"crossref","first-page":"213","DOI":"10.1080\/00223131.2013.772448","article-title":"Current understanding of radiation-induced degradation in light water reactor structural materials","volume":"50","author":"Fukuya","year":"2013","journal-title":"J. Nucl. Sci. Technol."},{"key":"ref_29","unstructured":"Ernestova, M. (2014, January 15\u201318). Influence of the Neutron Spectrum on the Sensitivity to IASCC and Microstructure of CW 316 Material. Proceedings of the 8th International Symposium Fontevraud 8, Contribution of Materials Investigations and Operating Experience to LWRs Safety, Performance and Reliability, SFEN, Avignon, France."},{"key":"ref_30","doi-asserted-by":"crossref","first-page":"226","DOI":"10.1016\/B978-0-12-803581-8.12051-X","article-title":"Radiation Effects in Ferritic Steels and Advanced Ferritic-Martensitic Steels","volume":"3","author":"Hashimoto","year":"2020","journal-title":"Compr. Nucl. Mater."},{"key":"ref_31","unstructured":"Takakura, K., Nakata, K., Fujimoto, K., Sakima, K., and Kubo, N. (2009, January 23\u201327). IASCC properties of cold worked 316 stainless steel in PWR primary water. Proceedings of the 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, Virginia Beach, VA, USA."},{"key":"ref_32","doi-asserted-by":"crossref","first-page":"112","DOI":"10.1016\/j.jnucmat.2015.02.038","article-title":"Crack initiation testing of thimble tube material under PWR conditions to determine a stress threshold for IASCC","volume":"461","author":"Bosch","year":"2015","journal-title":"J. Nucl. Mater."},{"key":"ref_33","doi-asserted-by":"crossref","first-page":"110897","DOI":"10.1016\/j.matchar.2021.110897","article-title":"IASCC of neutron irradiated 316 stainless steel to 125 dpa","volume":"173","author":"Du","year":"2021","journal-title":"Mater. Charact."},{"key":"ref_34","unstructured":"(1995). Cylindrical Helical Compression (Extension) Springs Made of Special Steels and Alloys. General Specifications. Standard No. GOST 50753-95."},{"key":"ref_35","doi-asserted-by":"crossref","first-page":"89","DOI":"10.1016\/j.jnucmat.2017.10.024","article-title":"Effect of temperature and dissolved oxygen on stress corrosion cracking behavior of P92 ferritic-martensitic steel in supercritical water environment","volume":"498","author":"Zhang","year":"2018","journal-title":"J. Nucl. Mater."},{"key":"ref_36","unstructured":"Karzov, G.P., Margolin, B.Z., and Shvetsova, V.A. (1993). Physical and Mechanical Modeling of the Failure Processes, Polytechnic Publ."},{"key":"ref_37","doi-asserted-by":"crossref","first-page":"147","DOI":"10.1016\/0022-5096(76)90024-7","article-title":"On the mechanisms of ductile failure in high-strength steel subjected to multi-axial stress state","volume":"24","author":"Hancock","year":"1976","journal-title":"J. Mech. Phys. Solids"},{"key":"ref_38","doi-asserted-by":"crossref","first-page":"37","DOI":"10.1016\/j.jnucmat.2007.05.005","article-title":"Ferritic\/martensitic steels for next-generation reactors","volume":"371","author":"Klueh","year":"2007","journal-title":"J. Nucl. Mater."},{"key":"ref_39","doi-asserted-by":"crossref","first-page":"414","DOI":"10.1016\/j.jnucmat.2012.08.021","article-title":"Continuum modeling of localized deformation in irradiated bcc materials","volume":"432","author":"Patra","year":"2013","journal-title":"J. Nucl. Mater."},{"key":"ref_40","doi-asserted-by":"crossref","first-page":"162","DOI":"10.1557\/PROC-792-R1.1","article-title":"Microstructures of Irradiated and Mechanically Deformed Metals and Alloys: Fundamental Aspects. In Materials Research Society symposia proceedings","volume":"792","author":"Zinkle","year":"2003","journal-title":"Mater. Res. Soc."},{"key":"ref_41","doi-asserted-by":"crossref","first-page":"483","DOI":"10.1016\/S0022-3115(00)00370-6","article-title":"Tensile properties and microstructure of 590 MeV proton-irradiated pure Fe and a Fe-Cr alloy","volume":"283\u2013287","author":"Luppo","year":"2000","journal-title":"J. Nucl. Mater."}],"container-title":["Materials"],"original-title":[],"language":"en","link":[{"URL":"https:\/\/www.mdpi.com\/1996-1944\/16\/7\/2585\/pdf","content-type":"unspecified","content-version":"vor","intended-application":"similarity-checking"}],"deposited":{"date-parts":[[2025,10,10]],"date-time":"2025-10-10T19:02:19Z","timestamp":1760122939000},"score":1,"resource":{"primary":{"URL":"https:\/\/www.mdpi.com\/1996-1944\/16\/7\/2585"}},"subtitle":[],"short-title":[],"issued":{"date-parts":[[2023,3,24]]},"references-count":41,"journal-issue":{"issue":"7","published-online":{"date-parts":[[2023,4]]}},"alternative-id":["ma16072585"],"URL":"https:\/\/doi.org\/10.3390\/ma16072585","relation":{},"ISSN":["1996-1944"],"issn-type":[{"value":"1996-1944","type":"electronic"}],"subject":[],"published":{"date-parts":[[2023,3,24]]}}}