Research Article

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

Table 3

The maximum 32 and 64 EFPY neutron fluence on beltline major regions.

Material IDMajor regionRatio to max.
neutron flux
Neutron fluence
for 32 EFPY
(1019 n/cm2)
Neutron fluence
for 64 EFPY
(1019 n/cm2)

Axial weldsW-1001-0710.490.04780.0956
W-1001-0820.990.08450.1690
W-1001-0930.660.05640.1128
W-1001-1040.390.03330.0666
W-1001-1150.2780.02370.0474
W-1001-1260.5050.04310.0862

Circumferential weldW-1102-370.5610.04790.0958

PlatesSC-03-S381.000.08540.1708
SC-03-S291.000.08540.1708
SC-03-S1101.000.08540.1708
SC-04-S1110.550.04700.0940
SC-04-S3120.550.04700.0940
SC-04-S2130.550.04700.0940

The maximum values are 0.0854 1019 n/cm2 and 0.1708 1019 n/cm2 for 32 EFPY and 64 EFPY, respectively.