A review of significant safety research results on zircaloy fuel cladding deformation and coolability of deformed rod bundles in a LOCA
| Zugehörige Institution(en) am KIT | Institut für Reaktorbauelemente (IRB) |
| Publikationstyp | Vortrag |
| Publikationsjahr | 1987 |
| Sprache | Englisch |
| Identifikator | KITopen-ID: 230024104 |
| Erscheinungsvermerk | IAEA Specialists' Meeting on Water Reactor Fuel Behavior and Fission Products Release in Off-Normal and Accident Conditions, Wien, A, November 10-13, 1986 |