The complex influence of gas-phase hydrogenation, irradiation with high-energy krypton ions and high-temperature oxidation in water vapor flow on the structural-phase state and the formation of defects in zirconium alloy E110 with chromium coatings; Journal of Nuclear Materials; Vol. 629
| Parent link: | Journal of Nuclear Materials.— .— Amsterdam: Elsevier Science Publishing Company Inc. Vol. 629.— 2026.— Article number 156654, 15 p. |
|---|---|
| Corporate Author: | |
| Other Authors: | , , , , , , , , , , , |
| Summary: | This research combines experimental testing of hydrogen sorption, krypton ion irradiation, and high-temperature steam oxidation with first-principles theoretical modeling to elucidate protective mechanisms of chromium coatings on the surface of zirconium alloy E110. Results indicate that the Cr coating reduced the hydrogen sorption rate and decreased radiation-induced defect concentration. The chromium coating deposition leads to the reduction of oxidation-induced weight gain by approximately 50% during LOCA-simulated testing. The probability of oxygen location in the Zr bulk and at the Cr/Zr interface is approximately equal based on first-principles calculations, indicating that the Cr/Zr interface does not impede oxygen diffusion into the bulk of zirconium. Therefore, the reduced impact of oxidation is primarily due to the barrier properties of the chromium coating: the location of the oxygen atom on the chromium surface and at the Cr/Zr interface is energetically more favorable than in the Cr bulk. Prior irradiation of the Cr-coated zirconium alloy with heavy krypton ions increases the weight gain of the alloy due to oxidation. This is because the formation of vacancies in the chromium lattice facilitates oxygen uptake due to the formation of strong O–Cr bonds within vacancies. Thus, the irradiation-induced vacancies in the Cr lattice act as oxidation initiation centers Текстовый файл AM_Agreement |
| Language: | English |
| Published: |
2026
|
| Subjects: | |
| Online Access: | https://doi.org/10.1016/j.jnucmat.2026.156654 |
| Format: | Electronic Book Chapter |
| KOHA link: | https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=687784 |
| Summary: | This research combines experimental testing of hydrogen sorption, krypton ion irradiation, and high-temperature steam oxidation with first-principles theoretical modeling to elucidate protective mechanisms of chromium coatings on the surface of zirconium alloy E110. Results indicate that the Cr coating reduced the hydrogen sorption rate and decreased radiation-induced defect concentration. The chromium coating deposition leads to the reduction of oxidation-induced weight gain by approximately 50% during LOCA-simulated testing. The probability of oxygen location in the Zr bulk and at the Cr/Zr interface is approximately equal based on first-principles calculations, indicating that the Cr/Zr interface does not impede oxygen diffusion into the bulk of zirconium. Therefore, the reduced impact of oxidation is primarily due to the barrier properties of the chromium coating: the location of the oxygen atom on the chromium surface and at the Cr/Zr interface is energetically more favorable than in the Cr bulk. Prior irradiation of the Cr-coated zirconium alloy with heavy krypton ions increases the weight gain of the alloy due to oxidation. This is because the formation of vacancies in the chromium lattice facilitates oxygen uptake due to the formation of strong O–Cr bonds within vacancies. Thus, the irradiation-induced vacancies in the Cr lattice act as oxidation initiation centers Текстовый файл AM_Agreement |
|---|---|
| DOI: | 10.1016/j.jnucmat.2026.156654 |