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 ID | Major region | Ratio to max. neutron flux | Neutron fluence for 32 EFPY (1019 n/cm2) | Neutron fluence for 64 EFPY (1019 n/cm2) |
| Axial welds | W-1001-07 | 1 | 0.49 | 0.0478 | 0.0956 | W-1001-08 | 2 | 0.99 | 0.0845 | 0.1690 | W-1001-09 | 3 | 0.66 | 0.0564 | 0.1128 | W-1001-10 | 4 | 0.39 | 0.0333 | 0.0666 | W-1001-11 | 5 | 0.278 | 0.0237 | 0.0474 | W-1001-12 | 6 | 0.505 | 0.0431 | 0.0862 |
| Circumferential weld | W-1102-3 | 7 | 0.561 | 0.0479 | 0.0958 |
| Plates | SC-03-S3 | 8 | 1.00 | 0.0854 | 0.1708 | SC-03-S2 | 9 | 1.00 | 0.0854 | 0.1708 | SC-03-S1 | 10 | 1.00 | 0.0854 | 0.1708 | SC-04-S1 | 11 | 0.55 | 0.0470 | 0.0940 | SC-04-S3 | 12 | 0.55 | 0.0470 | 0.0940 | SC-04-S2 | 13 | 0.55 | 0.0470 | 0.0940 |
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The maximum values are 0.0854 1019 n/cm2 and 0.1708 1019 n/cm2 for 32 EFPY and 64 EFPY, respectively.
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