Results 21 to 30 of about 418,826 (248)
Nuclear Engineering and Technology, 2022 Alloy 690 tubing has been shown to be highly resistant to primary water stress corrosion cracking (PWSCC). Nevertheless, predicting the failure by PWSCC in Alloy 690 SG tubes is indispensable.
Dayu Fajrul Falaakh, Chi Bum Bahn
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Electrochemical behavior and corrosion rate prediction study of alloy 690
International Journal of Advanced Nuclear Reactor Design and Technology, 2022 Alloy 690 is a material commonly used in heat transfer tubes of steam generators (SGTs). The electrochemical corrosion behavior in different volumes (V) of NaCl–Na2S2O3 solution for different surface roughness (Ra) of alloy 690 was studied, and a BPNN ...
Weibing Wang +5 more
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Effects of the weld thermal cycle on the microstructure of alloy 690. [PDF]
Alloy 690 has been introduced as a material for use as the heat exchanger tubes in the steam generators (SGs) of pressurised water reactor (PWR) nuclear power plant. Its immediate predecessor, alloy 600, suffered from a number of degradation modes and another alternative, alloy 800, has also had in-service problems.
Tuttle, James R.
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Effect of Microstructure Evolution on Thermal Conductivity of Alloy 690 [PDF]
TeshugangThe effect of microstructure evolution on thermal conductivity of alloy 690 electrode was studied according to the working conditions of electrode materials in Joule furnace.
Feng Han +5 more
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Nuclear Engineering and Technology, 2021 By using miniature SENB specimens, the fracture properties of the materials in the region of welded metal, 321 stainless steel heat affected zone, 690 alloy heat affected zone of 321/690 dissimilar metal girth welded joints were tested.
Bao Chen +5 more
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Microstructure dependence on mechanical behavior of Alloy 690 [PDF]
AIP Conference Proceedings, 2016 The influence of microstructure on the mechanical behavior of Alloy 690 was studied in this work. The microstructures with and without carbide precipitation were obtained through solution annealing and/or thermal treatment. The mechanical impact tests on different microstructure at a high strain rate of 5.3×103/s were performed by compressive split ...
X. M. Pan +3 more
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Magnetite Deposition Behavior on Alloy 600 and Alloy 690 Tubes in Simulated PWR Secondary Water
, 2022 Fouling due to magnetite deposition has been a major concern for steam generator (SG) tubing of pressurized water reactors (PWRs). Alloy 690 SG tubes are now used for new plants or are scheduled to replace old Alloy 600 tubes of operating plants.
Soon-Hyeok Jeon +3 more
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Influence of oxide films on primary water stress corrosion cracking initiation of alloy 600 [PDF]
, 2006 In the present study alloy 600 was tested in simulated pressurised water reactor (PWR) primary water, at 360 °C, under an hydrogen partial pressure of 30 kPa. These testing conditions correspond to the maximum sensitivity of alloy 600 to crack initiation.
Panter, J. +6 more
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Frontiers in Materials, 2022 In order to find the low-alloy high-strength steel welded with the strongest corrosion resistance, the corrosion resistance of HSAL weld metal was studied by considering different alloy compositions. Corrosion resistance of alloy compositions of 460, 690,
Liang Song +5 more
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Friction behavior of laser cladding magnesium alloy against AISI 52100 steel [PDF]
, 2012 The use of magnesium alloys in engineering applications is becoming increasingly important as a relatively low density allows savings in energy consumption and therefore reduction in air pollution.
J.E. Masse +3 more
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