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- [2] Model to describe the anisotropic viscoplastic behaviour of Zircaloy-4 tubes J Nucl Mater, 2-3 (135-162):
- [5] Behavior of irradiated Zircaloy-4 fuel cladding under simulated LOCA conditions 2000, American Society for Testing and Materials, Conshohocken, PA, USA
- [8] Behavior of lithium and boron in irradiated and unirradiated oxides formed on Zircaloy-4 claddings ZIRCONIUM IN THE NUCLEAR INDUSTRY: TWELFTH INTERNATIONAL SYMPOSIUM, 2000, 1354 : 773 - 792
- [9] On the embrittlernent of Zircaloy-4 under RIA-relevant conditions ZIRCONIUM IN THE NUCLEAR INDUSTRY: THIRTEENTH INTERNATIONAL SYMPOSIUM, 2002, 1423 : 702 - 718