Interdiffusion behavior of U3Si2 with FeCrAl via diffusion couple studies

被引:9
作者
Hoggan, Rita E. [1 ]
He, Lingfeng [1 ]
Harp, Jason M. [1 ]
机构
[1] Idaho Natl Lab, POB 1625,MS6188, Idaho Falls, ID 83415 USA
关键词
U3Si2; FeCrAl; Cladding; URANIUM; MICROSTRUCTURE; SYSTEM; FUELS; IRRADIATION; POWDER; IRON;
D O I
10.1016/j.jnucmat.2017.10.057
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Uranium silicide (U3Si2) is a candidate to replace uranium oxide (UO2) as light water reactor (LWR) fuel because of its higher thermal conductivity and higher fissile density relative to the current standard, UO2. A class of Fe, Cr, Al alloys collectively known as FeCrAl alloys that have superior mechanical and oxidation resistance are being considered as an alternative to the standard Zirconium based LWR cladding. The interdiffusion behavior between FeCrAl and U3Si2 is investigated in this study. Commercially available FeCrAl, along with U3Si2 pellets were placed in diffusion couples. Individual tests were ran at temperatures ranging from 500 degrees C to 1000 degrees C for 30 h and 100 h. The interdiffusion was analyzed with an optical microscope, scanning electron microscope, and transmission electron microscope. Uniform and planar interdiffusion layers along the material interface were illustrated with backscatter electron micrographs and energy-dispersive X-ray spectroscopy. Electron diffraction was used to validate phases present in the system, including distinct U2Fe3Si/UFe2 and UFeSi layers at the material interface. U and Fe diffused far into the FeCrAl and U3Si2 matrix, respectively, in the higher temperature tests. No interaction was observed at 500 degrees C for 30 h. (c) 2018 Published by Elsevier B.V.
引用
收藏
页码:356 / 369
页数:14
相关论文
共 27 条
[21]  
Robb, 2015, P 16 INT TOPICAL M N
[22]   ON THE POROSITY OBSERVED IN THE KIRKENDALL EFFECT [J].
SEITZ, F .
ACTA METALLURGICA, 1953, 1 (03) :355-369
[23]  
Sitton S. B., 2014, INLEXT1329957 US DEP
[24]   INTERACTION OF IRON WITH MOLTEN URANIUM [J].
WALTER, CM ;
KELMAN, LR .
JOURNAL OF NUCLEAR MATERIALS, 1966, 20 (03) :314-&
[25]   Thermophysical properties of U3Si2 to 1773 K (vol 464, pg 275, 2015) [J].
White, J. T. ;
Nelson, A. T. ;
Dunwoody, J. T. ;
Safarik, D. J. ;
McClellan, K. J. .
JOURNAL OF NUCLEAR MATERIALS, 2017, 484 :386-387
[26]   Thermal conductivity of UO2+x and U4O9-y [J].
White, J. T. ;
Nelson, A. T. .
JOURNAL OF NUCLEAR MATERIALS, 2013, 443 (1-3) :342-350
[27]   Preliminary safety analysis of the PWR with accident-tolerant fuels during severe accident conditions [J].
Wu, Xiaoli ;
Li, Wei ;
Wang, Yang ;
Zhang, Yapei ;
Tian, Wenxi ;
Su, Guanghui ;
Qiu, Suizheng ;
Liu, Tong ;
Deng, Yongjun ;
Huang, Heng .
ANNALS OF NUCLEAR ENERGY, 2015, 80 :1-13