About this Research Topic
Nuclear energy plays a vital role in achieving carbon peaking and carbon neutrality goals. However, the Fukushima-Daiichi nuclear accident in 2011 has posed a significant challenge for researchers to develop new strategies to ensure the safety and lifetime of nuclear reactors through applying advanced materials with stable physical and chemical properties. The utilization of materials for nuclear claddings requires high irradiation tolerance and excellent corrosion resistance, taking into account the fact that nuclear reactors serve under extremely irradiative and corrosive environment. Therefore, exploring the material irradiation effects and corrosion damage in structural materials for nuclear reactors with different coolants is essential to facilitate the structural materials or protective coatings design.
Structural materials in nuclear reactor commonly suffered from irradiation and corrosion. To deal with these problems, experiments or simulation have proven to be effective methods to reveal the irradiation damage or corrosion behaviors. Thus, irradiation research related to ion irradiation, neutron irradiation, and simulation conducted on different structural materials or protective coatings are expected to reveal the microstructure and properties evolution. Corrosion tests with water, steam, and molten salt are also effective methods to present the corrosion process. Moreover, synergetic damage experiments with irradiation, corrosion, or even wear are closer to the service simulation and are regarded as a better method to understand the failure mechanism. Based on these failure mechanisms, advanced materials design can contribute to alleviating the degradation.
Topics covered include, but are not limited to:
• Microstructure and mechanical properties evolution of materials (structural or coating) under irradiation;
• New technologies developed to detect the degradation of materials after irradiation;
• Irradiation damage in materials via simulation;
• Corrosion behaviors for materials under different coolants;
• Synergetic damage of materials under irradiation, corrosion, and wear;
• Advanced strategies in developing materials for nuclear reactor.
Structural materials in nuclear reactor commonly suffered from irradiation and corrosion. To deal with these problems, experiments or simulation have proven to be effective methods to reveal the irradiation damage or corrosion behaviors. Thus, irradiation research related to ion irradiation, neutron irradiation, and simulation conducted on different structural materials or protective coatings are expected to reveal the microstructure and properties evolution. Corrosion tests with water, steam, and molten salt are also effective methods to present the corrosion process. Moreover, synergetic damage experiments with irradiation, corrosion, or even wear are closer to the service simulation and are regarded as a better method to understand the failure mechanism. Based on these failure mechanisms, advanced materials design can contribute to alleviating the degradation.
Topics covered include, but are not limited to:
• Microstructure and mechanical properties evolution of materials (structural or coating) under irradiation;
• New technologies developed to detect the degradation of materials after irradiation;
• Irradiation damage in materials via simulation;
• Corrosion behaviors for materials under different coolants;
• Synergetic damage of materials under irradiation, corrosion, and wear;
• Advanced strategies in developing materials for nuclear reactor.
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