Results 41 to 50 of about 935 (164)
Nuclear FusionThe activated corrosion product assessments of fusion structural materials are essential to designing components and evaluating workers’ radiation exposure.
Motoki Nakajima, Takashi Nozawa
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Ubiquity Proceedings, 2018 The paper deals with experimentally estimation and comparison of the mechanical properties changes of RPV steels before and after irradiation of samples in Halden reactor in Norway coming from Unit #3 and #4 of NPP Mochovce (still under construction ...
M. Adamech +3 more
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Nuclear Materials and EnergyTo enhance the high-temperature performance and extend the upper service temperature of oxide dispersion strengthened (ODS) steels for fusion reactor applications, a novel 9Cr-ODS steel was designed by co-adding 0.2 wt% VN and 0.35 wt% Y2O3 powders ...
Yaozhi Li +4 more
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Neutron Irradiation Brittleness of Structural Steels on Reactors
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan, 1964 As a recently results of the irradiation test, it has been found that the brittleductile transition temperature shifts to higher temperature for the structural steels when these are irradiated. Therefore, the problem of the brittle fracture of the reactor pressure vessel is now emphasized from the standpoint of the safety of reactor operation.This ...
ANDO, Yoshio, FUJIMURA, Tadato
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Ratcheting behavior of Eurofer97 at 550 °C
Nuclear Materials and Energy, 2018 The components in reactor are usually exposed to cyclic loading caused by frequent startups, shutdown and load fluctuations which lead to ratcheting effect.
Kuo Zhang, Jarir Aktaa
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Forge and Heat-treatments in Microalloyed Steels – A Review
High Temperature Materials and Processes, 2013 Improved designs, mostly for lightweight component manufacturer, have been made for improvement of forging and heat-treatment techniques. Low temperature precipitation strengthening and resistance to austenite grain size coarsening at reheat temperature ...
Raj A., Goswami B., Kumar S.B., Ray A.K.
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Development and Validation of Radiation Embrittlement Prediction Model of Austenitic Stainless Steel
Yuanzineng kexue jishuAustenitic stainless steels are used as important structural materials in nuclear reactors due to their high fracture toughness. In the process of long-term service, austenitic stainless steel will be subjected to neutron irradiation to cause ...
JIA Lixia, WANG Dongjie, HE Xinfu, WU Shi, YANG Wen
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MetalsThe irradiation-induced precipitation of Mn-Ni-rich precipitates (MNPs) or Mn-Ni-Si-rich precipitates (MNSPs) is the primary cause of embrittlement in reactor pressure vessel (RPV) steels.
Fan Yang +3 more
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Microstructure-Informed Prediction of Hardening in Ion-Irradiated Reactor Pressure Vessel Steels
MetalsIon irradiation combined with nanoindentation is a promising tool for studying irradiation-induced hardening of nuclear materials, including reactor pressure vessel (RPV) steels.
Libang Lai +8 more
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BEHAVIOR OF ALUMINUM COATING BY CVD-FBR IN STEAM OXIDATION AT 700°C
CT&F Ciencia, Tecnología & Futuro, 2014 Aluminum coatings have been obtained using the Chemical Vapor Deposition of Fluidized Bed Reactor technique (CVD-FBR), on austenitic stainless steels (AISI 304, AISI 316 and AISI 317), in order to evaluate resistance to steam oxidation at 700ºC.
José-Luddey Marulanda-Arévalo +2 more
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