A computer model for probabilistic leak-rate analysis of nuclear piping and piping welds

Application of probabilistic modelling to the lifetime management of nuclear boilers in the creep regime: Part 1

“…[11,12], and within the creep regime, e.g., Refs. [13e18]; and applications to the evaluation or reliability analysis of nondestructive testing data, e.g., Refs.…”

Structural Reliability Improvement Using In-Service Inspection for Intergranular Stress Corrosion of Large Stainless Steel Piping

“…Harris et al (Harris et al, 1992) developed a computer code named PRAISE (piping reliability analysis, including seismic events) for estimating the probability of pipe leak age under SCC. Rahman (Rahman S. 1997) has developed another computer code named PSQUIRT (probabilistic see page quantification of upsets in reactor tubes) to determine the probability of leak age of piping made of stainless steel and carbon steel subjected to intergranular stress corrosion cracking (IGSCC) and corrosion fatigue. Failure probabilities of a piping component subjected to SCC was computed in (Priya C et al, 2005and Guedri et al, 2009a, 2009b) using a Monte Carlo simulation (MCS) technique.…”

Three-dimensional Finite Element Analysis of a Semi-Elliptical Circumferential Surface Crack in a Carbon Steel Pipe Subjected to a Bending Moment

“…Significant efforts to investigate the crack growth induced by fatigue have been made during recent decades to prevent the fatigue failure of structures. Several workers [1][2][3][4][5][6][7] have examined and analysed the behaviour of a through-wall circumferential crack in pipes. Forman et al…”

“…Rahman et al [2] developed a computer code for evaluation of the leak rate in nuclear piping using crack-opening area analysis in a through-wall circumferentially cracked pipe subjected to combined bending and tension. Chen [3] used the finite element difference method to obtain SIF solutions for fully circumferential defects in cylinders.…”