Research Article

Probabilistic Structural Integrity Analysis of Boiling Water Reactor Pressure Vessel under Low Temperature Overpressure Event

Table 4

Mean values of beltline region materials on clad/base interface (°C).

Material IDMajor region for 32 EFPYControl region for 64 EFPYControl region

Axial weldsW-1001-0711010
W-1001-08288
W-1001-09388
W-1001-1041212
W-1001-1151313
W-1001-1261212

Circumferential weldW-1102-3788

PlatesSC-03-S38
SC-03-S29
SC-03-S110
SC-04-S111
SC-04-S312
SC-04-S213