Results 11 to 20 of about 3,842 (255)
Methodological developments in the field of structural integrity analyses of large scale reactor pressure vessels in Hungary [PDF]
Fracture and Structural Integrity, 2016 Buildings, structures and systems of large scale and high value (e.g. conventional and nuclear power plants, etc.) are designed for a certain, limited service lifetime.
Tamás Fekete
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Science and Technology of Nuclear Installations, 2021 The safety-risk pressurized thermal shock (PTS) have on a reactor pressure vessel (RPV) is one of the most important studies for the lifetime ageing management of a reactor.
M. Annor-Nyarko, Hong Xia
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Nuclear Materials and Energy, 2021 The small punch test is evaluated as a screening procedure for irradiation embrittlement of reactor pressure vessel steels. In particular, the correlation between ductile-to-brittle transition temperatures obtained from this small specimen test technique
E. Altstadt, F. Bergner, M. Houska
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Effect of Tank Diameter on Solid Suspension in Industrial Reactor Vessels [PDF]
Journal of Applied Fluid MechanicsPresent research study analyses the suitability of baffled reactor vessels with large diameter agitated using the Rushton Turbine (RT) impeller maintained at standard clearance condition for the solid-liquid suspension process.
D. K. Iyer, A. K. Patel
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Modelling Irradiation Effects in Metallic Materials Using the Crystal Plasticity Theory—A Review
Crystals, 2023 The review starts by highlighting the significance of nuclear power plants in the contemporary world, especially its indispensable role in the global efforts to reduce CO2 emissions.
Karol Frydrych
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Nihon Kikai Gakkai ronbunshu, 2019 The reactor pressure vessel is made of ferritic low alloy steel, which has fracture behaviors that include ductile to brittle transition temperature and decrease of fracture toughness in the beltline region of the reactor pressure vessel steel due to ...
Takatoshi HIROTA, Kentaro YOSHIMOTO
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Validation of the code package MCPV [PDF]
Ядерна фізика та енергетика, 2009 The results of the validation of the code package MCPV that is used in the radiation exposure determination methodology for the pressure vessels of the VVER type reactors of Ukrainian NPPs are presented.
V. N. Bukanov +4 more
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Hot Deformation Behavior of SA508Gr.4N Steel for Reactor Pressure Vessels
Cailiao gongcheng, 2017 The high-temperature plastic deformation and dynamic recrystallization behavior of SA508Gr.4N steel were investigated through hot deformation tests in a Gleeble1500D thermal mechanical simulator.
YANG Zhi-qiang +3 more
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Mechanical Engineering Journal, 2020 Seismic buckling of vessels is one of main concerns for the design of fast reactor plants in Japan. Rational design is important because of two conflicting requirements; thicker walls are preferable to prevent seismic buckling of vessels, while ...
Shigeru TAKAYA, Naoto SASAKI
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Metals, 2018 In the 21st century, there is an increasing need for high-capacity, high-efficiency, and environmentally friendly power generation systems. The environmentally friendly integrated gasification combined-cycle (IGCC) technology has received particular ...
Hye-sung Na +3 more
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