Results 21 to 30 of about 935 (164)

Ultrafine-grained oxide-dispersion-strengthened 9Cr steel with exceptional strength and thermal stability

Nuclear Materials and Energy, 2022
As important structural materials for sodium-cooled fast reactors and fusion reactors, oxide-dispersion-strengthened (ODS) steels of the ferritic/martensitic (F/M) type containing 8–12 wt% Cr have been extensively studied.
B.R. Sun, A.D. Zhou, Y.L. Li, Z.L. Zhang, C.C. Du, S.X.Y. Gu, Z. Chen, X.C. Cai, S.W. Xin, T.D. Shen   +9 more
doaj   +1 more source

Research Progress of Steels for Nuclear Reactor Pressure Vessels

Materials, 2022
The nuclear reactor pressure vessel is an important component of a nuclear power plant. It has been used in harsh environments such as high temperature, high pressure, neutron irradiation, thermal aging, corrosion and fatigue for a long time, which puts forward higher standards for the performance requirements for nuclear pressure vessel steel.
Zhou, Linjun, Dai, Jie, Li, Yang, Dai, Xin, Xie, Changsheng, Li, Linze, Chen, Liansheng   +6 more
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Effect of Neutron Fluence Rate on Irradiation Embrittlement of Low-copper RPV Steel

Yuanzineng kexue jishu
The reactor pressure vessels (RPVs) of pressurized water reactor (PWR) nuclear power plants currently in operation and under construction in China are all made of low-alloy ferritic steels obtained by quenching and tempering treatments (which meet the ...
WU Yazhen, LI Guoyun, WANG Haidong, HUANG Juan, ZHANG Haisheng, SUN Kai, LEI Yang, ZHU Lini
doaj   +1 more source

Effect of Pre-Heating and Post-Heating on Electron Beam Welding of Reduced Activation Ferrite/Martensite Steel

Journal of Nuclear Engineering, 2021
Reduced activation ferritic/martensitic (RAFM) steels are considered the main candidate material for the water-cooled ceramic breeder (WCCB) in a fusion reactor.
Yong Zhang, Jiefeng Wu, Zhihong Liu, Songlin Liu, Mingzhun Lei, Muhammad Atif, Zhenfei Liu, Jianguo Ma   +7 more
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Investigation of mechanical properties and proton irradiation behaviors of SA-738 Gr.B steel used as reactor containment

Nuclear Materials and Energy, 2016
The proton irradiation behaviors of two kinds of SA-738Gr.B steels prepared by different heat treatment used as AP1000 reactor containment were investigated by transmission electron microscopy and positron annihilation lifetime spectrum (PAS).
Ma Yongzheng, Ran Guang, Chen Nanjun, Lei Penghui, Shen Qiang   +4 more
doaj   +1 more source

Tailoring Microstructure of Austenitic Stainless Steel with Improved Performance for Generation-IV Fast Reactor Application: A Review

Crystals, 2023
Austenitic stainless steels are selected as candidate materials for in-core and out-of-core components of Generation-IV fast reactors due to their excellent operating experience in light-water reactors over several decades.
Shenghu Chen, Ang Xie, Xinliang Lv, Sihan Chen, Chunguang Yan, Haichang Jiang, Lijian Rong   +6 more
doaj   +1 more source

Analysis of Shift in Nil-Ductility Transition Reference Temperature for RPV Steels Due to Irradiation Embrittlement Using Probability Distributions and Gamma Process

Metals
Reactor pressure vessel (RPV) steels are highly susceptible to irradiation embrittlement due to prolonged exposure to high temperature, high pressure, and intense neutron irradiation.
Kaikai Tang, Yan Li, Yuebing Li, Weiya Jin, Jiameng Liu   +4 more
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Overview of Intergranular Fracture of Neutron Irradiated Austenitic Stainless Steels

Metals, 2017
Austenitic stainless steels are normally ductile and exhibit deep dimples on fracture surfaces. These steels can, however, exhibit brittle intergranular fracture under some circumstances.
Anna Hojná
doaj   +1 more source

Inspection of Reactor Steel Degradation by Magnetic Adaptive Testing [PDF]

Materials, 2019
Degradation of nuclear pressure vessel steel materials, 15Kh2NMFA type and A508 Cl2 type (definition is given in the text) were investigated by a novel magnetic nondestructive testing method, so-called Magnetic Adaptive Testing (MAT), which is based on systematic measurement and evaluation of minor magnetic hysteresis loops.
Gábor Vértesy, Antal Gasparics, Ildikó Szenthe, Ferenc Gillemot, Inge Uytdenhouwen   +4 more
openaire   +3 more sources

COMPARISON OF TWO TECHNIQUES FOR EVALUATING SPHERICAL INDENTATION DATA

Acta Polytechnica CTU Proceedings, 2020
Flow curves of 15Kh2MFA, Sv 08Kh19N10G2B and 08Kh18N10T steels used for fabrication of WWER-440 nuclear reactor pressure vessel and core internals were obtained using the automated ball indentation (ABI) test technique and compared with flow curves ...
Aleš Materna, Petr Haušild, Jan Ondráček   +2 more
doaj   +1 more source