期刊
JOURNAL OF NUCLEAR MATERIALS
卷 544, 期 -, 页码 -出版社
ELSEVIER
DOI: 10.1016/j.jnucmat.2020.152588
关键词
Fuel-cladding chemical interaction (FCCI); Metallic fuel; Advanced nuclear fuel; Transmission electron microscopy (TEM); HT-9 cladding; Phase transformation
资金
- U.S. Department of Energy, Office of Nuclear Energy under DOE Idaho Operations Office as part of a Nuclear Science User Facilities [DEAC07-051D14517]
- Center for Thermal Energy Transport under Irradiation, an Energy Frontier Research Center - U.S. Department of Energy, Office of Science, Basic Energy Sciences
- Advanced Fuels Campaign (AFC) of the Nuclear Technology Research and Development (NTRD) program in the U.S. Department of Energy, Office of Nuclear Energy under DOE Idaho Operations Office Contract [DE-AC07-05ID14517]
The annular metallic fuel design eliminates the liquid sodium bond between the fuel and the cladding, providing back-end fuel cycle and other benefits, presenting new features. Negligible amounts of lanthanides were found in the FCCI layer in the investigated annular fuel, with most retained in the newly formed UZr 2 phase in the fuel center region.
As an alternative fuel form, the annular metallic fuel design eliminates the liquid sodium bond between the fuel and the cladding, providing back-end fuel cycle and other benefits. The fuel-cladding chemical interaction (FCCI) of annular fuel also presents new features. Here, state-of-the-art electron microscopy and spectroscopy techniques were used to study the FCCI of a prototype annular U-10wt%Zr (U-10Zr) fuel with ferritic/martensitic HT-9 cladding irradiated to 3.3% fission per initial heavy atom. Compared with sodium-bonded solid fuels, negligible amounts of lanthanides were found in the FCCI layer in the investigated helium-bonded annular fuel. Instead, most lanthanides were retained in the newly formed UZr 2 phase in the fuel center region. The interdiffusion of iron and uranium resulted in tetragonal (U,Zr)(6) Fe phase (space group I4/mcm) and cubic (U,Zr)(Fe,Cr)(2) phase (space group Fd3m). The (U,Zr)(Fe,Cr)(2) phase contains a high density of voids and intergranular uranium monocarbides of NaCl-type crystal structure (space group Fm (3) over barm). At the interdiffusion zone and inner cladding interface, a porous lamellar structure composed of alternating Cr-rich layers and U-rich layers was observed. Next to the lamellar region, the unexpected phase transformation from body-centered cubic ferrite (alpha-Fe) to tetragonal binary Fe-Cr sigma phase (space group P4(2)/mnm) occurred, and tetragonal Fe-Cr-U-Si phase (space group I4/mmm) was identified. Due to the diffusion of carbon into the interdiffusion zone, carbon depletion inside the HT-9 led to the disappearance of the martensite lath structure, and intergranular U-rich carbides formed as a result of the diffusion of uranium into the cladding. These detailed new findings reveal the unique features of the FCCI behavior of annular U-Zr fuels, which could be a promising alternative fuel form for high burnup fast reactor applications. (C) 2020 Elsevier B.V. All rights reserved.
作者
我是这篇论文的作者
点击您的名字以认领此论文并将其添加到您的个人资料中。
推荐
暂无数据