Experimental investigation of fission and activation product release from LWR fuel rods at temperatures ranging from 1500-2800⁰C
| Zugehörige Institution(en) am KIT | Institut für Radiochemie (IRCH) |
| Publikationstyp | Vortrag |
| Publikationsjahr | 1979 |
| Sprache | Englisch |
| Identifikator | KITopen-ID: 230013610 |
| Erscheinungsvermerk | Behaviour of Defected Zirconium Alloy Clad Ceramic Fuel in Water Cooled Reactors, IAEA Specialists' Meeting, Chalk River, Canada, September 17-21, 1979 |