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    Characteristics of the New Embrittlement Correlation Method for the Japanese Reactor Pressure Vessel Steels 

    Source: Journal of Engineering for Gas Turbines and Power:;2010:;volume( 132 ):;issue: 010:;page 102918
    Author(s): Naoki Soneda; Akiyoshi Nomoto
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Neutron irradiation embrittlement of reactor pressure vessel steels is an important aging issue for the long-term operation of light water reactors. A new embrittlement correlation method was ...
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    Evaluation of Fracture Toughness by Master Curve Approach Using Miniature C(T) Specimens 

    Source: Journal of Pressure Vessel Technology:;2012:;volume( 134 ):;issue: 002:;page 21402
    Author(s): Naoki Miura; Naoki Soneda
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The fracture toughness master curve shows the relationship between the median of fracture toughness and temperature in the ductile–brittle transition temperature region of ferritic steels such as ...
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    Industry Practice for the Neutron Irradiation Embrittlement of Reactor Pressure Vessels in Japan 

    Source: Journal of Engineering for Gas Turbines and Power:;2010:;volume( 132 ):;issue: 010:;page 102919
    Author(s): Norimichi Yamashita; Masanobu Iwasaki; Koji Dozaki; Naoki Soneda
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Neutron irradiation embrittlement of reactor pressure vessel steels (RPVs) is one of the important material aging issues. In Japan, almost 40 years have past since the first plant started its ...
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