Analysis of Thermophysical Justification of the Applicability of Accident Tolerant Fuel for Nuclear Power Plants: Current Concepts, Technologies, and Chemical Stability of Accident Tolerant Fuel
The review considers the prerequisites for the development of accident tolerant fuel and presents the main concepts concerning the use of new fuel rod claddings for nuclear power plants with light water reactors. The current status of development in the field of accident tolerant fuel in Russia and abroad is described. The methods of applying protective coatings to zirconium fuel rod claddings and technologies for replacing zirconium with various alloys (FeCrAl, 42KhNM, and molybdenum) and ceramic composites are considered. The results of studies on the chemical resistance of fuel rod claddings to water and gases, in particular, at high temperatures, are analyzed.
Authors
- A. R. Zabirov (ORCID: https://orcid.org/0000-0002-5521-2970)
- V. V. Yagov (ORCID: https://orcid.org/0000-0002-8051-2342)
- D. A. Yashnikov
- I. A. Molotova (ORCID: https://orcid.org/0000-0002-2422-7475)
- Dmitrii V. Sidelev (ORCID: https://orcid.org/0000-0002-5685-6110)
- S. Shevchenko (ORCID: https://orcid.org/0000-0003-3367-416X)
Institutions
- Moscow Power Engineering Institute (RU)
- National Research Tomsk State University (RU)
- Tomsk Polytechnic University (RU)
Publication Details
- Journal
- High Temperature
- Published
- 2024-10-01
- DOI
- https://doi.org/10.1134/s0018151x25700191
- Citations
- 2
- Primary Topic
- Nuclear Materials and Properties
- Type
- article
- Field-Weighted Citation Impact
- 0.23