Fracture mechanics assessment of thermal aged nuclear piping based on the Leak-Before-Break concept

Chen, Mingya; Wang, Yu; Qian, Guian; Wang, Rongshan; Lü, Feng; Zhang, Guodong; Xue, Fei; Chen, Zhilin

doi:10.1016/j.nucengdes.2016.03.025

Cited by 9 publications

(3 citation statements)

References 8 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…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. Chen et al implemented leak before break (LBB) assessment through elastic plastic fracture mechanics (EPFM) analyses. 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.…”

Section: Introductionmentioning

confidence: 99%

“…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.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

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

Sim

Chang

2018

Fatigue Fract Eng Mat Struct

View full text Add to dashboard Cite

Since thermal aging embrittlement (TE) causes loss of fracture toughness and may lead to failure, it is one of structural integrity issues to be assessed in nuclear industry. In this study, crack growth simulation by using extended finite element method (XFEM) was carried out for CF8M base metal and ER316L weld metal, which are typical vulnerable materials. First, user subroutines were constructed to incorporate variation of mechanical properties of two materials due to the TE. In particular, with regard to ER316L, weld residual stress (WRS) distribution was considered. Second, validity of the subroutines and XFEM was confirmed by comparing with analytical and experimental data. Finally, crack growth analyses for nuclear pipes were performed by applying the verified methodology. Thereby, differences of the crack growth amounts and paths as the presence or absence of the TE and WRS were quantified and discussed.

show abstract

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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

Sim

Chang

2018

Fatigue Fract Eng Mat Struct

View full text Add to dashboard Cite

show abstract

“…Potential hazards of leaking pressure vessel can be tremendous. Numerical investigation of J-integral in the notched walls of pressure vessels can be a great step toward the anticipation of safety zone and 'leak-before-the-brake' margin in vessels exploitation, [2].…”

Section: Introductionmentioning

confidence: 99%

Numerical Investigation of J-Integral on a Notched Pressure Vessel

Tadić¹,

Sedmak²,

Nikolić

2018

AMR

View full text Add to dashboard Cite

Finite elements analysis has been performed to compute a J-integral values in a notched pressure vessel. A semi-elliptical notch was introduced in a wall of cylindrical pressure vessel with aspect ratio of notch depth to wall thickness a/w = 1/6 to 5/6, where the wall thickness was 3 mm. Two cases were examined – inner and outer notch. Numerical examinations were revealed that outer notch has much higher values of J-integral (3-4 times), all other being the same, (i.e. inner pressure and dimensions of the notch). That was explained in terms of triaxality stress state in front of notch. Namely, it was shown that inner notch has positive triaxiality stress ratio and vice-versa, outer notch revealed highly negative hydrostatic stress component ahead the notch.

show abstract

Leak-Before-Break assessment of a welded piping based on 3D finite element method

Chen

Wang

Chen

et al. 2017

Annals of Nuclear Energy

View full text Add to dashboard Cite

Fracture mechanics assessment of thermal aged nuclear piping based on the Leak-Before-Break concept

Cited by 9 publications

References 8 publications

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

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

Numerical Investigation of J-Integral on a Notched Pressure Vessel

Leak-Before-Break assessment of a welded piping based on 3D finite element method

Contact Info

Product

Resources

About