Development of Radiation Porosity in the Material of Fuel-Element Cladding Produced by Different Technologies for Fast Neutron Reactors and Its Influence on the Fuel Assembly Service Life in the BN-600 Reactor

Research output: Contribution to journal › Article › peer-review

Original language	English
Pages (from-to)	528-534
Number of pages	7
Journal	Physics of Metals and Metallography
Volume	123
Issue number	5
DOIs	https://doi.org/10.1134/S0031918X22050052
Publication status	Published - May 2022

austenitic steel, BN-600 reactor, critical void diameter, fuel cladding, neutron irradiation, point defects, swelling, swelling prediction, vacancy migration

ID: 30456966