Abstract
The present Light Water Reactor (LWR) pressure vessel safety regulations refer to the actual steel fracture toughness through indexation to Charpy impact test ductile-to-brittle transition temperatures or upper shelf energies, depending on the fracture mode. These conventional concepts bear upon an absolute one: reactor service life limit and total generated MW(e) power. They do not nor do need to carry an absolute meaning, intrinsically, provided they adequately correlate with fracture probabilities.
| Original language | English |
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| Title of host publication | CAPRICE 79: Correlation accuracy in pressure vessel steel as reactor component investigation of change of material properties with exposure data |
| Place of Publication | Germany |
| Publisher | IAEA - International Atomic Energy Agency |
| Pages | 210-211 |
| Number of pages | 2 |
| State | Published - 1979 |
| Event | 1979 - Meeting on accuracies in correlation between property change and exposure data from reactor pressure vessel steel radiation: IAEA - Juelich Duration: 24 Sep 1979 → 27 Sep 1979 |
Conference
| Conference | 1979 - Meeting on accuracies in correlation between property change and exposure data from reactor pressure vessel steel radiation |
|---|---|
| Abbreviated title | JUEL-CONF-37 |
| Country/Territory | Germany |
| City | Juelich |
| Period | 1979-09-24 → 1979-09-27 |