Data for: Theory-guided bottom-up design of the FeCrAl alloys as accident tolerant fuel cladding materials
收藏NIAID Data Ecosystem2026-03-10 收录
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Supplementary Information
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创建时间：
2019-01-18
相关数据集
Uniaxial tensile test data for 15-15 Ti ar cw material at 23 °C (specimen identifier 24CW_03_023)
Data created at HZDR in the scope of the EERA JPNM pilot project TASTE to assess miniature testing techniques for fuel claddings.
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Small punch test data for Zircaloy 4 and 15 15 Ti on tube specimens cut from nuclear fuel cladding tubes. The data were acquired in the framework of the EERA JPNM pilot project TASTE.
Small punch test data for Zircaloy 4 and 15 15 Ti on tube specimens cut from nuclear fuel cladding tubes.
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High pressure XLD and scXRD measurements of Zr-based nanolamellar carbide single crystals patterned by Focused Ion Beam
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Synergistic effects of alloying elements and primary knock-on atoms on irradiation damage in Zr-Nb-Ti ternary alloys
Zirconium alloys, widely used in PWR fuel cladding due to their low neutron absorption and radiation resistance, face challenges in understanding alloying effects on irradiation damage. This study emp
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Uniaxial tensile test data for 15-15 Ti ar cw material at 23 °C (specimen identifier 24CW_01_023)
Data created at HZDR in the scope of the EERA JPNM pilot project TASTE to assess miniature testing techniques for fuel claddings.
DataCite Commons2023-04-21 更新40
