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Uniaxial ratcheting behavior and microstructure evolution of 316H stainless steel under the random cyclic loads
W Zhou, GY Zhou, X ** due to a macro-crack pre-existent in nuclear reactors at high temperature
M Dougdag, R Fernandez, D Lamberts - Annals of Nuclear Energy, 2022 - Elsevier
Thermal stri** phenomenon is a random temperature fluctuation that may cause thermal
fatigue damage of components until their break. These situations can cause the failure of …
fatigue damage of components until their break. These situations can cause the failure of …
[KÖNYV][B] Sodium fast reactors with closed fuel cycle
B Raj, P Chellapandi, PRV Rao - 2015 - books.google.com
This book presents the state of the art of sodium-cooled fast reactors with closed fuel cycles,
offering in-depth coverage of reactor physics, materials, design, safety analysis, validations …
offering in-depth coverage of reactor physics, materials, design, safety analysis, validations …
Biaxial High Cycle Fatigue of a type 304L stainless steel: Cyclic strains and crack initiation detection by digital image correlation
M Poncelet, G Barbier, B Raka, S Courtin… - European Journal of …, 2010 - Elsevier
A series of biaxial High Cycle Fatigue tests at room temperature is performed to build up an
extensive and well-documented database. The testing specimen is a maltese cross thinned …
extensive and well-documented database. The testing specimen is a maltese cross thinned …
Prognostic model and failure mechanisms of steam generators in Sodium-Cooled fast reactors
This paper presents a prognostic model for sodium-cooled fast reactor (SFR) steam
generators (SGs). The purpose of the model is to estimate the remaining useful life of SFR …
generators (SGs). The purpose of the model is to estimate the remaining useful life of SFR …
[HTML][HTML] Assessment of thermal fatigue life for 316L and P91 pipe components at elevated temperatures
KF Nilsson, F Dolci, T Seldis, S Ripplinger… - Engineering Fracture …, 2016 - Elsevier
This paper presents an analysis of thermal fatigue tests of pipe components with 14 mm wall
thickness made of 316L austenitic steel or P91 ferritic-martensitic steels. The tests are done …
thickness made of 316L austenitic steel or P91 ferritic-martensitic steels. The tests are done …
Large eddy simulation on the mixing characteristics of liquid sodium at the core outlet of sodium cooled fast reactors (SFR)
Y Wang, M Wang, J Zhang, S Qiu, W Tian, G Su - Annals of Nuclear Energy, 2021 - Elsevier
It is a critical safety issue of thermal fatigue in the core outlet of sodium cooled fast reactors
(SFRs) due to the mixing phenomenon of coolant with different temperatures flowing from …
(SFRs) due to the mixing phenomenon of coolant with different temperatures flowing from …