| METALS AND METAL MATRIX COMPOSITES |
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Research Progress on Properties and Composition of Ferritic/Martensitic
Heat-resistant Steels for Nuclear Power |
| NIU Ben1, WANG Zhenhua1, PAN Qianfu2, LIU Chaohong2, WANG Qing1, DONG Chuang1
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1 Key Laboratory of Materials Modification by Laser, Ion and Electron Beams (Ministry of Education) & School of Material Science and Engineering, Dalian University of Technology, Dalian 116024, China
2 Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu 610213, China |
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Abstract Recently, with the continuous development of nuclear power systems, the main stack type lead-cooled fast neutron reactor(LFR) as the fourth-generation nuclear reactor system has become a hot research topic due to its good thermal conductivity and neutron economy. In order to improve the corrosion and irradiation properties of the cladding material in lead-bismuth coolant, 9%—12% Cr ferritic/martensitic (F/M) steels, as an important high-temperature structural material for thermal power generation, have become a candidate cladding material for lead-cooled fast neutron reactors due to their good resistance to corrosion and radiation-resistant swelling properties.
However, as a candidate cladding material, the corrosion of ferritic/martensitic heat-resistant steels will increase due to the high temperature and irradiation caused by fission of nuclear fuel during service. Under irradiation conditions, the high temperature structural instability of the mate-rial is further aggravated to affect the high temperature mechanical properties of the material.
As regards the above problems, researchers have mainly designed two different F/M steels systems (Cr-Mo and Cr-W) from the perspective of composition and process to satisfy the service requirements by adjusting the addition of trace elements on the basis of 9%—12% Cr F/M steels and changing the heat treatment method. The results show that the addition of trace elements plays a key role in improving the microstructural stability and mechanical properties of F/M steels. A change in the heat treatment process can achieve a good commbination between strength and ductility.
The present work summarizes the research progress on various properties of F/M steels systematically, including mechanical properties, corrosion and irradiation-resistance properties, as well as microstructural stabilities. Then, the relationship between alloy properties and composition of F/M steels was generalized. Finally, a cluster formula approach for compositional design for multi-component alloys was used to explore the variation tendency of alloy compositions of existing F/M steels. And this approach was proposed in light of the chemical short-range orders of solute atoms in solid solution. The cluster formula of the improved low-activation F/M steels was then proposed, which will give a new design method to develop high-performance F/M steels combined with thermodynamics calculations.
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Published: 05 November 2020
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| Fund:This work was financially supported by the National Natural Science Foundation of China(U1867201,91860108), the National Key Research and Development Plans (2017YFB0702400), the Fundamental Research Funds for the Central Universities (DUT19LAB01). |
About author:: Ben Niu received his Bachelor degree of engineering in July 2017 from Luoyang Institute of Science and Technology. He is currently pursuing his master’s degree at the School of Materials Science and Engineering, Dalian University of Technology under the supervision of Prof. Qing Wang, focus on the composition optimization and microstructural stability of stainless steels for nuclear fuel cladding materials.
Qing Wang received her Ph.D. degree in November 2005 from Dalian University of Technology. She is cur-rently a professor and Ph.D. supervisor in School of Materials Science and Engineering, Dalian University of Technology.Her research interest are materials composition design and development of multi-component alloys, including the stainless steels,Ti-alloys, high-entropy alloys and superalloys. |
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2020, Vol. 34 
