TEM examination of phases formed between U-Pu-Zr fuel and Fe

JOURNAL OF NUCLEAR MATERIALS

卷:467

Article

Aitkaliyeva, Assel¹  Madden, James W.¹  Miller, Brandon D.¹  Papesch, Cynthia A.¹  Cole, James I.¹ 

[1] Idaho Natl Lab, Idaho Falls, ID 83415 USA

关键词: Metal fuel;    U-Pu-Zr;    Fuel-cladding chemical interaction (FCCI);   

DOI  :  10.1016/j.jnucmat.2015.10.043

来源: Elsevier

【 摘 要 】

Exposure to high temperatures and irradiation results in interaction and interdiffusion between fuel and cladding constituents that can lead to formation of undesirable brittle or low-melting point phases. A diffusion couple study has been conducted to understand fuel-cladding interaction occurring between U-22Pu-4Zr (in wt%) fuel and pure Fe at elevated temperatures. The phases formed within fuel cladding chemical interaction (FCCI) layer have been characterized in the transmission electron microscope (TEM). The phases formed within FCCI layer have been identified as Fe2U (Fd-3m), FeU6 (I4/mcm), Fe2Zr (Fd-3m), FeZr2 (I4/mcm), Fe2Pu (Fd-3m), UZr2 (P6/mmm), beta-Zr (Im-3m), and ZrO2 (Fm-3m). Published by Elsevier B.V.

【 授权许可】

Free