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RISDevelopment of Leak Before Break Assessment Method for Japan Sodium Cooled Fast Reactor Pipe—Part 1 Crack Opening Displacement Assessment of Thin Wall Pipes Made of Modified 9Cr 1Mo Steel
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: This was carried out to establish crack opening displacement (COD) evaluation methods used in leakbeforebreak (LBB) assessment of sodium pipes of the Japan sodium cooled fast reactor (JSFR). For sodium pipes of JSFR, the ...
The Welded Joint Strength Reduction Factors of Modified 9Cr–1Mo Steel for the Advanced Loop-Type Sodium Cooled Fast Reactor
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Creep strength enhanced ferritic (CSEF) steels including ASME Gr.91 are widely used in fossil power plants. In the advanced loop-type sodium-cooled fast reactor (SFR), modified 9Cr–1Mo steel (ASME Gr.91) is going to be ...
A Screening Method for Prevention of Ratcheting Strain Derived From Movement of Temperature Distribution
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: In this paper, we simplify the existing method and propose a screening method to prevent thermal ratcheting strain in the design of practical components. The proposed method consists of two steps to prevent the continuous ...