Assessment of integrity of components in piping of 500 MWe PHWR: using R-6 method

Characterizing the crack initiation load in circumferentially through-wall cracked elbows under bending load

“…Geometric non-linearity is important to accurately capture the elbow deformation under closing/opening bending loading. In the case of defect-free elbows, good predictions by finite element analysis are reported in the literature [14][15][16][17][18][19][20][21][22][23][24]. A significant difference in the deflection behaviour of defect-free elbows is reported for closing and opening modes of bending.…”

Probabilistic risk assessment for the piping of a nuclear power plant: Uncertainty and sensitivity analysis by using SINTAP procedure

“…For homogeneous pipes and welds with defects, PROST considers the R6 [21] and FKM (Kiefner) [23] codes. Here the plastic limit stress proposed by Kiefner et al [24] for a circumferential semi-elliptical inner surface cracks in a cylinder is used, wherein only a uniform stress value is taken into account. Meanwhile, the involved variables are considered as random variables characterized by a certain distributional function.…”

Probabilistic fracture failure analysis of nuclear piping containing defects using R6 method

“…Three cracks at this reactor recirculation loop. needed in the analysis are given in Table 2 (Rastogi et al, 2002). In this example, there were 10,000,000 simulations and the assessment method used is the Option 1 curve of R6 approach.…”