Cavitation Wear of T91 Ferritic-Martensitic Steel

被引:0
作者
H. Yu. Rostova
G. D. Tolstolutska
R. L. Vasilenko
I. V. Kolodiy
V. І. Kovalenko
V. G. Marinin
M. А. Tikhonovsky
O. S. Kuprin
机构
[1] “Kharkiv Institute of Physics and Technology” National Science Center,
[2] National Academy of Sciences of Ukraine,undefined
来源
Materials Science | 2022年 / 58卷
关键词
ferritic-martensitic steel; structure; hardness; cavitation erosion; wear;
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摘要
The microstructure, hardness and cavitation wear of T91 ferritic-martensitic steel are studied and compared with some other reactor steels of the Eurofer 97 and Cr18Ni10Ti grades. It is shown that the cavitation resistance of T91 steel is 34 times higher than the cavitation resistance of Eurofer 97 steel and 11 times higher than the resistance of traditionally used Cr18Ni10Ti austenitic steel. Unlike the Eurofer 97 ferritic-martensitic steel alloyed with tungsten and tantalum, the T91 steel alloyed with molybdenum and niobium has larger prior austenite grain sizes (20 vs. 6 μm), length and width of martensitic packets (30–40 and 3–10 vs. 10–20 and 2–4 μm, respectively), and microhardness (2.47 vs. 2.07 GPa).
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页码:364 / 368
页数:4
相关论文
共 95 条
[1]  
Klueh RL(2009)Ferritic/martensitic steels for advanced nuclear reactors Trans. Indian Inst. Met. 62 81-87
[2]  
Murty KL(2008)Structural materials for Gen-IV nuclear reactors: Challenges and opportunities J. Nucl. Mater. 383 189-195
[3]  
Charit I(2021)The effects of fusion reactor thermal transients on the microstructure of Eurofer97 steel J. Nucl. Mater. 554 153084-658
[4]  
Kumar D(2017)Choice of a low operating temperature for the DEMO EUROFER97 divertor cassette Fusion Eng. Des. 124 655-6
[5]  
Hargreaves J(2014)EUROFER as wall material: Reduced sputtering yields due to W surface enrichment J. Nucl. Mater. 454 1-73
[6]  
Bharj A(2022)Divertor of the European DEMO: Engineering and technologies for power exhaust Fusion Eng. Des. 175 113010-471
[7]  
Scorror A(2011)Current status of fast reactors and future plans in India Energy Procedia 7 64-373
[8]  
Harding LM(2011)Design study and R&D progress on Japan Sodium-cooled fast reactor J. Nucl. Sci. Technol. 48 463-201
[9]  
Dominguez-Andrade H(2012)Evaluation of JSFR key technologies Nucl. Technol. 179 360-2523
[10]  
Holmes R(2007)Corrosion and stress corrosion cracking in supercritical water J. Nucl. Mater. 371 176-71