Turnitin
降AI改写
早检测系统
早降重系统
Turnitin-UK版
万方检测-期刊版
维普编辑部版
Grammarly检测
Paperpass检测
checkpass检测
PaperYY检测
Research progress of steels for nuclear reactor pressure vessels
L Zhou, J Dai, Y Li, X Dai, C **e, L Li, L Chen - Materials, 2022 - mdpi.com
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 …
has been used in harsh environments such as high temperature, high pressure, neutron …
[HTML][HTML] Numerical simulation of oil and gas pipeline corrosion based on single-or coupled-factor modeling: A critical review
Numerical simulation is an effective research approach to assess the condition and predict
the remaining service life of process pipelines suffering corrosion hazards. This work …
the remaining service life of process pipelines suffering corrosion hazards. This work …
Long-term corrosion evolution associated with the structural heterogeneities of an Fe-based amorphous coating in H3BO3 solution at various temperatures
DB Wang, J Wu, JP Cui, Q Wang, TR Li, W Emori… - Journal of Materials …, 2023 - Elsevier
Understanding the long-term corrosion behavior of neutron absorber materials in H 3 BO 3
solution is crucial for the materials applications in spent fuel storage. In this paper, long-term …
solution is crucial for the materials applications in spent fuel storage. In this paper, long-term …
Effects of mill scale and varying exposure conditions on corrosion behavior of A572 structural steel
Today, many steel structures are multi-decades old and commonly suffer from corrosion that
induces progressive loss of the base metal in various forms including localized and …
induces progressive loss of the base metal in various forms including localized and …
Characterization of microstructure of A508III/309L/308L weld and oxide films formed in deaerated high-temperature water
The microstructure of A508III/309L/308L weld clad and the properties of the oxide films
formed in simulated pressurized water reactor primary water at 290° C were characterized …
formed in simulated pressurized water reactor primary water at 290° C were characterized …
Non-negligible corrosion from vaporized boric acid on 304 stainless steel
X Li, D Wei, S Zhang, Y Qi, W Sun, J Zhong… - Journal of Nuclear …, 2023 - Elsevier
Based on the volatility and sublimation properties of boric acid, the corrosion behaviours of
304 stainless steel (SS) in boric acid-containing vapour over the boric acid aqueous solution …
304 stainless steel (SS) in boric acid-containing vapour over the boric acid aqueous solution …
[HTML][HTML] Heat-induced morphology-dependent corrosion of solid boric acid on carbon steel
X Li, W Sun, G Ning - Journal of Materials Research and Technology, 2024 - Elsevier
The corrosion of solid boric acid (s-BA) has so far remained unnoticed, which could pose a
potential hazard to the safety of boron-containing equipment. In this work, a morphology …
potential hazard to the safety of boron-containing equipment. In this work, a morphology …
[HTML][HTML] Stress corrosion crack propagation affected by microstructures for nuclear steam turbine rotor steels in the simulated environment
S Weng, Y Huang, S Lin, FZ Xuan - Journal of Materials Research and …, 2022 - Elsevier
The propagation behavior of stress corrosion cracking (SCC) for two CrNiMoV steels in the
simulated environment of low-pressure nuclear steam turbine rotor was systematically …
simulated environment of low-pressure nuclear steam turbine rotor was systematically …
Effect of temperature on corrosion behavior of E690 steel in 3.5 wt.% NaCl solution
Q Yan, Q Yin, J Cui, X Wang, Y Qiao… - Materials Research …, 2021 - iopscience.iop.org
The corrosion behavior of E690 steel in 3.5 wt.% NaCl solution at temperatures from 20 C to
60 C was investigated using electrochemical test. The corrosion morphology was …
60 C was investigated using electrochemical test. The corrosion morphology was …
Effects of surface treatments and temperature on the oxidation behavior of 308L stainless steel cladding in hydrogenated high-temperature water
T Cui, X Xu, D Pan, J Ma, Z Lu, J Chen, X Liang… - Journal of Nuclear …, 2022 - Elsevier
The properties of the oxide films grown on 308 L SS cladding with various surface
treatments and temperatures in simulated PWR primary water are studied. The thickness of …
treatments and temperatures in simulated PWR primary water are studied. The thickness of …