Crack initiation and crack growth during thermal shock tests in the reactor pressure vessel of the HDR under corrosive medium conditions
| Zugehörige Institution(en) am KIT | Projekt Heißdampfreaktor (PHDR) |
| Publikationstyp | Vortrag |
| Publikationsjahr | 1987 |
| Sprache | Englisch |
| Identifikator | KITopen-ID: 230025500 |
| Erscheinungsvermerk | Post SMIRT-9 Conf. No. 2 'Assuring Structural Integrity of Steel Reactor Pressure Boundary Components', Davos, CH, August 24-25, 1987 |