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Creep strength evaluation of welded joint made of modified 9Cr-1Mo steel for Japanese Sodium Cooled Fast Reactor (JSFR)

JSFRのための改良9Cr-1Mo鋼溶接継手のクリープ強度評価

若井 隆純 ; 永江 勇二 ; 鬼澤 高志  ; 小原 智史; Xu, Y.*; 大谷 知未*; 伊達 新吾*; 浅山 泰 

Wakai, Takashi; Nagae, Yuji; Onizawa, Takashi; Obara, Satoshi; Xu, Y.*; Otani, Tomomi*; Date, Shingo*; Asayama, Tai

This paper describes a proposal of provisional allowable stress for the welded joints made of modified 9Cr-1Mo steel applicable to the structural design of Japanese Sodium Cooled Fast Reactor (JSFR). In the welded joints of ferritic heat resistant steels including modified 9Cr-1Mo steel, creep strength may obviously degrade especially in long-term region. This phenomenon is known as "Type-IV" damage. Though obvious strength degradation has not observed at 550$$^{circ}$$C yet for the welded joint made of modified 9Cr-1Mo steel, it is proper to suppose strength degradation must take place in very long-term creep. Therefore, taking strength degradation due to "Type-IV" damage into account, the allowable stress applicable to JSFR pipe design was proposed based on creep rupture test data obtained in temperature acceleration conditions. Available creep rupture test data were analyzed by region partition method. For conservativeness, allowable stress was proposed provisionally considering design factor for each region. Present design of JSFR hot leg pipe of primary circuit was evaluated using the proposed allowable stress. As a result, it was successfully demonstrated that the compact pipe design was assured.

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