共 50 条
- [1] Behavior of irradiated Zircaloy-4 fuel cladding under simulated LOCA conditions 2000, American Society for Testing and Materials, Conshohocken, PA, USA
- [2] MODEL FOR INVERTED PRIMARY CREEP IN BETA-PHASE ZIRCALOY-4 FUEL SHEATHING TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1977, 27 (NOV): : 294 - 295
- [3] MODEL TO PREDICT ZIRCALOY-4 IRRADIATION GROWTH TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1976, 24 (NOV19): : 165 - 166
- [4] DEFORMATION AND FAILURE OF ZIRCALOY FUEL SHEATHS UNDER LOCA CONDITIONS. Atomic Energy of Canada Limited, AECL (Report), 1982,
- [6] Mitigating the Stress Corrosion Cracking of Zircaloy-4 Fuel Sheathing: Siloxane Coatings Revisited JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2016, 2 (02):
- [9] Microstructure and Mechanical Properties of Zircaloy-4 Cladding Hydrogenated at Temperatures Typical for LOCA Conditions 22ND INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2013), 2013,
- [10] IDENTIFICATION OF 2ND-PHASE PARTICLES IN ZIRCALOY-4 NUCLEAR-FUEL SHEATHING METALLOGRAPHY, 1982, 15 (01): : 27 - 41