首页|Post-transient examination of performance of uranium silicide fuel and silicon-carbide composite cladding under reactivity-initiated accident conditions

Post-transient examination of performance of uranium silicide fuel and silicon-carbide composite cladding under reactivity-initiated accident conditions

扫码查看
原文链接
  • NSTL
© 2022New fuels are being developed for light water nuclear reactors with the initial goal of improving accident tolerance. More recently, these new fuel systems are also being recognized for their potential to support higher fuel burnups and thus improved economics for reactor plants through improved fuel utilization. Fuel safety testing of these new fuels systems is being conducted under transient irradiation conditions in the Transient Reactor Test facility at Idaho National Laboratory. A test campaign including two rodlets of U3Si2 fuel in Zircaloy-4 cladding and two rodlets of U3Si2 fuel in Silicon-Carbide Composite cladding has been performed to begin the development of fuel-safety criteria in design-basis reactivity-initiated accident conditions. Post-Transient-Irradiation Examinations have been performed and found that the accident tolerant materials maintained their primary rod-like geometry. Elemental species diffusion was found to occur in the Zircaloy rodlets indicating rapid diffusion kinetics at the temperatures achieved. No elemental species diffusion was found in the Silicon-Carbide rodlets. However, through-wall thickness cracks were observed due to displacement loading of the cladding from thermal expansion of the fuel pellets. This work presents the first experimental evidence of the performance of these fuel systems under transient nuclear heating and representative reactivity-initiated accident energy depositions.

Design-basis accidentFuel safetyNuclear fuelReactivity-initiated accidentSilicideSilicon-carbideSilicon-carbide compositeUraniumUranium silicideZircaloyZirconium

Schulthess J.、Kamerman D.、Winston A.、Pomo A.、Trowbridge T.、Pu X.、Woolstenhulme N.、Imholte D.、Jensen C.、Wachs D.

展开 >

Characterization and Advanced Post-Irradiation Examinations Idaho National Laboratory

2022

10.1016/j.jnucmat.2022.153520

Journal of Nuclear Materials

Journal of Nuclear Materials

EISCI
ISSN：0022-3115
年,卷(期)：2022.560
  • 75