CODEX-B4C experiment : core degradation test with boron carbide control rod

Veröffentlicht 2003

Codex-3/1 and Codex-3/2 experiments: quenching of high temperature VVER bundles

Veröffentlicht 2000

Oxidation of Zirconium Cladding in Air, Nitrogen, and Nitrogen-Rich Steam Atmospheres

von Perez-Fero, Erzsébet
Veröffentlicht in Light Water Reactor Fuel Performance Conference (2019 : Seattle, Wash.) Light Water Reactor Fuel Performance Conference (TOP FUEL 2019) ; Volume 1 of 2 (2020)

Experimental Simulation of the Behavior of E110 Claddings under Accident Conditions Using Electrically Heated Bundles

von Hózer, Zoltán
Veröffentlicht in International Symposium on Zirconium in the Nuclear Industry (19. : 2019 : Manchester) Zirconium in the nuclear industry (2021)

Round Robin Exercise of the Candidate ATF Cladding Materials Within the ACTOF Project

von Sevecek, Martin
Veröffentlicht in Light Water Reactor Fuel Performance Conference (2019 : Seattle, Wash.) Light Water Reactor Fuel Performance Conference (TOP FUEL 2019) ; Volume 1 of 2 (2020)