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    Development of Creep Fatigue Evaluation Method for Modified 9Cr 1Mo Steel 

    Source: Journal of Pressure Vessel Technology:;2014:;volume( 136 ):;issue: 003:;page 31404
    Author(s): Takaya, Shigeru; Nagae, Yuji; Asayama, Tai
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper describes a creep–fatigue evaluation method for modified 9Cr1Mo steel, which has been newly included in the 2012 edition of the Japan Society of Mechanical Engineers code for design and construction of fast ...
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    Development of Creep–Fatigue Evaluation Method for 316FR Stainless Steel 

    Source: Journal of Pressure Vessel Technology:;2015:;volume( 137 ):;issue: 004:;page 41407
    Author(s): Nagae, Yuji; Takaya, Shigeru; Asayama, Tai
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In the design of fast reactor plants, the most important failure mode to be prevented is creep–fatigue damage at elevated temperatures. 316FR stainless steel is a candidate material for the reactor vessel and internal ...
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    Strength of 316FR Joints Welded by Type 316FR/16 8 2 Filler Metals 

    Source: Journal of Pressure Vessel Technology:;2016:;volume( 138 ):;issue: 002:;page 24501
    Author(s): Yamashita, Takuya; Nagae, Yuji; Satoh, Kenichiro; Yamamoto, Kenji
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Type 316 stainless steel with lowcarbon and mediumnitrogen contents called 316FR stainless steel is a candidate structural material for reactor vessels and internals of futuregeneration fast breeder reactors (FBRs). The ...
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    Application of Nontransfer Type Plasma Heating Technology for Core-Material-Relocation Tests in Boiling Water Reactor Severe Accident Conditions 

    Source: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002:;page 20901
    Author(s): Abe, Yuta; Sato, Ikken; Nakagiri, Toshio; Ishimi, Akihiro; Nagae, Yuji
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A new experimental program using nontransfer (NTR) type plasma heating is under consideration in Japan Atomic Energy Agency (JAEA) to clarify the uncertainty on core-material relocation (CMR) behavior of boiling water ...
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