Special Issue: Behavior of Materials (Alloys, Coatings) in Conditions Specific to Gen IV Nuclear Reactors
Source abstract
Abstract
Today, countries all over the world, faced with a global energy crisis and the effects of climate change, are looking for alternatives to fossil fuels [...]
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Research context
OpenAlex topics: Nuclear Materials and Properties · Advanced materials and composites · Nuclear materials and radiation effects
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Affiliations
Nuclear Materials and Corrosion Department, Institute for Nuclear Research Pitesti, POB 78, Campului Street, No. 1, 115400 Mioveni, Romania
Advanced Reactor Materials & Chemistry Branch, Canadian Nuclear Laboratories (CNL), 286 Plant Road, Chalk River, ON K0J-1J0, Canada
Department of Material Testing, Research Centre Řež, Hlavní 130, 250 68 Husinec-Řež, Czech Republic
Department of Manufacturing and Industrial Management, University from Pitesti (UPIT), Str. Târgul din Vale nr. 1, 110040 Pitești, Romania
Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas (Ciemat), Avda. Complutense 40, 28040 Madrid, Spain
References (35)
Show source-provided references
1. DoE, U.S (2022). A Technology Roadmap for Generation IV Nuclear Energy Systems. Proceedings of the Nuclear Energy Research Advisory Committee and the Generation IV International Forum, Available online: https://www.gen-4.org/gif/jcms/c_40481/technology-roadmap.
2. Structural materials for Gen-IV nuclear reactors: Challenges and opportunities10.1016/j.jnucmat.2008.08.044 ↗
3. Yvon, P. (2016). Structural Materials for Generation IV Nuclear Reactors, Woodhead Publishing. [1st ed.].
4. Materials Challenges for Generation IV Nuclear Energy Systems10.13182/NT08-A3961 ↗
5. Materials challenges in nuclear energy10.1016/j.actamat.2012.11.004 ↗
6. Material issues for current and advanced designs10.7251/COMEN1401010H ↗
7. Tarantino, M., Angiolini, M., Bassini, S., Cataldo, S., Ciantelli, C., Cristalli, C., Del Nevo, A., Di Piazza, I., Diamanti, D., and Eboli, M. (2021). Overview on Lead-Cooled Fast Reactor Design and Related Technologies Development in ENEA. Energies, 14.10.3390/en14165157 ↗
8. Vogt, J.-B., and Proriol Serre, I. (2021). A Review of the Surface Modifications for Corrosion Mitigation of Steels in Lead and LBE. Coatings, 11.10.3390/coatings11010053 ↗
9. Fazio, C., and Balbaud, F. (2017). Corrosion phenomena induced by liquid metals in Generation IV reactors. Structural Materials for Generation IV Nuclear Reactors, Elsevier.10.1016/B978-0-08-100906-2.00002-1 ↗
10. Nuclear Energy Agency (NEA) (2015). Nuclear Energy Agency, Corrosion protection in lead and lead-bismuth eutectic at elevated temperatures. Handbook on Lead-Bismuth Eutectic Alloy and Lead Properties, Materials Compatibility, Thermal-hydraulics and Technologies, Available online: https://inis.iaea.org/collection/NCLCollectionStore/_Public/46/133/46133907.pdf.
11. Chen, Y., Hu, L., Qiu, C., He, B., Zhou, J., Zhao, J., and Li, Y. (2019). Influence of LBE Temperatures on the microstructure and properties of crystalline and amorphous multiphase ceramic coatings. Coatings, 9.10.3390/coatings9090543 ↗
12. Creep-resistant Al2O3-forming austenitic stainless steels10.1126/science.1137711 ↗
13. Long term corrosion resistance of alumina forming austenitic stainless steels in liquid lead10.1016/j.jnucmat.2015.03.011 ↗
14. Cižek, J., Kalivodová, J., Janecek, M., Stráský, J., Srba, O., and Macková, A. (2021). Advanced Structural Materials for Gas-Cooled Fast Reactors—A Review. Metals, 11.10.3390/met11010076 ↗
15. Zinkle, S.J. (2012, January 13–24). Nuclear technology applications of ceramics, composites and other nonmetallic materials. Proceedings of the IAEA/ICTP School on Physics of Radiation Effects and its Simulation for Non-Metallic Condensed Matter, Trieste, Italy.
16. Oxidation of SiCf-SiC CMC cladding tubes for GFR application in impure helium atmosphere and materials interactions with tantalum liner at high temperatures up to 1600 °C10.1016/j.jnucmat.2019.02.024 ↗
17. Corwin, W.R., Burchell, T.D., Katoh, Y., McGreevy, T.E., Nanstad, R.K., Ren, W., Snead, L.L., and Wilson, D.F. (2008). Generation IV Reactors Integrated Materials Technology Program Plan: Focus on Very High Temperature Reactor Materials.10.2172/951084 ↗
18. Yvon, P. (2017). SiCf/SiC composites as core materials for Generation IV nuclear reactors. Structural Materials for Generation IV Nuclear Reactors, Elsevier Ltd.. Chapter 12.
19. Current status and recent research achievements in SiC/SiC composites10.1016/j.jnucmat.2014.06.003 ↗
20. Yvon, P. (2017). Graphite as a core material for Generation IV nuclear reactors. Structural Materials for Generation IV Nuclear Reactors, Elsevier Ltd.. Chapter 14.
21. Nuclear graphite for high temperature gas-cooled reactors10.1016/S1872-5805(17)60116-1 ↗
22. Weaver, K.D., Totemeier, T., Feldman, E.E., Kulak, R.F., Tzanos, C.P., Cheng, L.-Y., Jo, J., Corwin, W., Gale, W.F., and Allen, T. (2022, November 05). Gas-Cooled Fast Reactor (GFR) FY 05 Annual Report; Idaho National Laboratory Report INL/EXT-05-00799; 2005, Available online: https://inldigitallibrary.inl.gov/sites/sti/sti/3480236.pdf.
23. Corrosion in the molten fluoride and chloride salts and materials development for nuclear applications10.1016/j.pmatsci.2018.05.003 ↗
24. Chengliang, L., and Mengjia, Y. (2009, January 9–14). The Challenge of Nuclear Reactor Structural Materials for Generation IV Nuclear Energy Systems. Proceedings of the 20th International Conference on Structural Mechanics in Reactor Technology (SMiRT 20), Espoo, Finland. SMiRT 20-Division 10, Paper 1586.
25. Supercritical water-cooled reactor materials e Summary of research and open issues10.1016/j.pnucene.2014.02.008 ↗
26. Buongiorno, J., and MacDonald, P.E. (2022, November 05). Supercritical Water Reactor (SCWR)—Progress Report for the FY-03 Generation-IV R&D Activities for the Development of the SCWR in the U.S.; 2003. Available online: http://large.stanford.edu/courses/2017/ph241/jones-c1/docs/ext-03-01210.pdf.
27. Nieuwenhove, R. (2013, January 3). Van Investigation of coatings, applied by PVD, for the corrosion protection of materials in supercritical water. Proceedings of the 6th International Conference on Supercritical Water Reactors, Shenzhen, China.
28. Materials challenges for the Supercritical Water-Cooled Reactor (SCWR)
29. (2022, November 05). Joint European Canadian Chinese Development of Small Modular Reactor Technology. Available online: https://ecc-smart.eu/.
30. Silicon carbide and its composites for nuclear applications-historical overview10.1016/j.jnucmat.2019.151849 ↗
31. Malerba, L., Al Mazouzi, A., Bertolus, M., Cologna, M., Efsing, P., Jianu, A., Kinnunen, P., Nilsson, K.F., Rabung, M., and Tarantino, M. (2022). Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations, Review. Energies, 15.10.3390/en15051845 ↗
32. Rebak, R.B., Terrani, K.A., and Fawcett, R.M. (2016, January 17–21). FeCrAl Alloys for Accident Tolerant Fuel Cladding in Light Water Reactors. Proceedings of the Pressure Vessels and Piping Conference, Vancouver, BC, Canada. Paper No: PVP2016-63162, V06BT06A009.
33. Research progress in FeCrAl alloys for accident-tolerant fuel cladding
34. Development of ODS FeCrAl for Compatibility in Fusion and Fission Energy Applications10.1007/s11837-014-1200-z ↗
35. A critical review of high entropy alloys and related concepts10.1016/j.actamat.2016.08.081 ↗