The influence of cladding on fission gas release from irradiated U-Mo monolithic fuel

JOURNAL OF NUCLEAR MATERIALS

卷:486

Article

Burkes, Douglas E.¹  Casella, Amanda J.¹  Casella, Andrew M.¹ 

[1] Pacific Northwest Natl Lab, POB 999, Richland, WA 99352 USA

关键词: Uranium-molybdenum;    Fission gas release;    Thermal analysis;    Irradiation;   

DOI  :  10.1016/j.jnucmat.2017.01.016

来源: Elsevier

【 摘 要 】

The monolithic uranium-molybdenum (U-Mo) alloy has been proposed as a fuel design capable of converting the world's highest power research reactors from use of high enriched uranium to low enriched uranium. However, a zirconium (Zr) diffusion barrier must be used to eliminate interactions that form between the U-Mo monolith and aluminum alloy 6061 (AA6061) cladding during fabrication and are enhanced during irradiation. One aspect of fuel development and qualification is to demonstrate an appropriate understanding of the extent of fission product release from the fuel under anticipated service environments. An exothermic reaction has previously been observed between the AA6061 cladding and Zr diffusion layer. In this paper, two fuel segments with different irradiation history were subjected to specified thermal profiles under a controlled atmosphere using a thermogravimetric/differential thermal analyzer coupled with a mass spectrometer inside a hot cell. Samples from each segment were tested with cladding and without cladding to investigate the effect, if any, that the exothermic reaction has on fission gas release mechanisms. Measurements revealed there is an instantaneous effect of the cladding/Zr exothermic reaction, but not necessarily a cumulative effect above approximately 973 K (700 degrees C). The mechanisms responsible for fission gas release events are discussed. (C) 2017 Elsevier B.V. All rights reserved.

【 授权许可】

Free