Assessment of thermal aging embrittlement in a cast stainless steel valve and its effect on the structural integrity

Thermal ageing on the deformation and fracture mechanisms of a duplex stainless steel by quasi in-situ tensile test under OM and SEM

“…Researches show that TAE occurs in Z3CN20-09M CDSSs after long term service [4][5][6][7][8]10,[18][19][20]. However, seldom papers focus on the influence of the long thermal ageing time on the deformation behavior and fracture mechanism of Z3CN20-09M CDSSs.…”

Crack growth evaluation by XFEM for nuclear pipes considering thermal aging embrittlement effect

“…For structural integrity assessment of thermally aged nuclear pipes constructed by CASS material, Cicero et al adopted Argonne National Laboratory (ANL) procedure to predict change of tensile properties and fracture toughness of CF8M using chemical composition and ferrite phase contents. Subsequently, they evaluated critical crack size for a component in a boiling water reactor (BWR) according to European fitness‐for‐service (FFS) procedure and compared results with those obtained from American Society of Mechanical Engineers (ASME) procedure.…”

“…The authors determined aged mechanical properties of CF3 based on NUREG/CR‐4513 and evaluated the critical crack size in use of J‐T diagram. While both of these studies for representative CASS materials are valuable, realistic crack growth behaviour was not considered. Jeon et al determined tensile properties of CF8M before and after the TE using tensile and small punch tests, which were used for prediction of J‐R curves by complex FE analyses combined with damage mechanics taking into account multiaxial fracture strain.…”

Effect of thermal aging on the leak-before-break analysis of nuclear primary pipes

“…However, these steels are susceptible to thermal aging embrittlement during long-term service at temperatures ranging from 280 to 450 • C (Chung, 1992;Pareige et al, 2011). The effect of thermal aging on microstructure and mechanical properties has been investigated extensively (Chung and Leax, 1990;Danoix and Auger, 2000;Li et al, 2013a), and the structural integrity assessment and probabilistic fracture mechanics analysis of thermally aged nuclear components have been well established (Tujikura and Urata, 1999;Cicero et al, 2009;Li et al, 2013b). However, the effect of thermal aging embrittlement on the LBB behavior has rarely been addressed.…”