| MATERIALS AND SUSTAINABLE DEVELOPMENT: ADVANCED MATERIALS FOR CLEAN ENERGY UTILIZATION |
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| Radiation Resistance Design and Nanoscale Second-phase Particles Characterization for ODS Steels: a Review |
Pei HE( ),Weizhi YAO,Jianming LYU,Bo GAO,Xianrong LI
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| Institute of Materials, China Academy of Engineering Physics, Jiangyou 621908 |
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Abstract Advanced fission and fusion reactors require high-performance alloys with outstanding microstructure and property stability in ultra-severe service environment including high temperature and high pressure, intense neutron irradiation and long service life. Oxide dispersion strengthened (ODS) steels have been considered as the most promising candidate as fuel cladding in Gen. Ⅳ reactor and structural materials in fusion blanket. Based on neutron irradiation damage, this paper reviews the latest research progress of irradiation-resistant ODS steels, focusing on the alloy design and advanced nanoscale second-phase particles characterization techniques.
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Published: 10 January 2018
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Representative microstructures in irradiated materials as a function of irradiation temperature/melting temperature (T/Tm)[8]
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Calculated decay of γ-surface dose rate in iron and ferritic/martensitic steels after irradiation in a DEMO spectrum[17]
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Comparison of visible defect cluster accumulation in body-centered-cubic (BCC) versus face-centered-cubic (FCC) regions of a type 308 stainless steel weldment after fission neutron irradiation at 120 ℃ to 0.065 displacements per atom (dpa)[8]
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Nanoscale oxide in ODS steels with a NaCl structure[44]
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2018, Vol. 32 
