HRTEM and chemical study of an ion-irradiated chromium/zircaloy-4 interface

JOURNAL OF NUCLEAR MATERIALS

卷:504

Review

Wu, A.¹  Ribis, J.¹  Brachet, J. -C.¹  Clouet, E.²  Lepretre, F.²  Bordas, E.²  Arnal, B.¹ 

[1] Univ Paris Saclay, Serv Rech Met Appl, DEN, CEA, F-91191 Gif Sur Yvette, France

[2] Univ Paris Saclay, Serv Rech Met Phys, DEN, CEA,DMN, F-91191 Gif Sur Yvette, France

关键词: High resolution transmission electron microscopy;    Interface;    Ion-irradiation;    Accident tolerant fuel;   

DOI  :  10.1016/j.jnucmat.2018.01.029

来源: Elsevier

【 摘 要 】

Chromium-coated zirconium alloys are being studied as Enhanced Accident Tolerant Fuel Cladding for Light Water Reactors (LWRs). Those materials are especially studied to improve the oxidation resistance of LWRs current fuel claddings in nominal and at High Temperature (HT) for hypothetical accidental conditions such as LOss of Coolant Accident. Beyond their HT behavior, it is essential to assess the materials behavior under irradiation. A first generation chromium/Zircaloy-4 interface was thus irradiated with 20 MeV Kr8+ ions at 400 degrees C up to 10 dpa. High-Resolution Transmission Electron Microscopy and chemical analysis (EDS) were conducted at the Cr/Zr interface. The atomic structure of the interface reveals the presence of Zr(Fe, Cr)(2) Laves phase, displaying both C14 and C15 structure. After irradiation, only the C14 structure was observed and atomic row matching was preserved across the different interfaces, thus ensuring a good adhesion of the coating after irradiation. (c) 2018 Elsevier B.V. All rights reserved.

【 授权许可】

Free