Experimental system for studying temperature gradient-driven fracture of oxide nuclear fuel out of reactor

  • S. Patnaik
  • , D. A. Lopes
  • , T. M. Besmann
  • , B. W. Spencer
  • , T. W. Knight

Research output: Contribution to journalArticlepeer-review

10 Scopus citations

Abstract

Temperature gradients in ceramic light water reactor (LWR) uranium dioxide (UO2) nuclear fuel pellets generate thermal stresses that cause fractures in the fuel, which begins early in the life of fresh fuel. The combination of heating due to fission and forced convective cooling on the exterior of LWR fuel rods generates a temperature profile that is difficult to replicate outside the reactor environment. In this study, a state-of-the-art experimental setup using electrical heating to study certain aspects of temperature driven fracture was built, and surrogate fuel materials such as ceria (CeO2) were used to validate the system. Cracking experiments were conducted on these surrogates by inducing reactivity-initiated-accident like temperature gradients in the pellets via induction and direct resistance heating. Induction heating was done using copper coils and molybdenum susceptors, which heated the surrogates to a threshold temperature that is sufficiently high for the fuel material to conduct current. Thereafter, direct resistance heating was achieved by passing current through the specimen using a DC power supply to introduce volumetric heating to replicate LWR operating conditions. The pellets were held against nickel electrodes and mounted on a boron nitride test-stand. All the tests were carried out in a stainless-steel vacuum chamber. Simultaneous real-time dual imaging of the surrogate pellet surface was implemented using an optical and infrared camera system that was mounted along axial and perpendicular directions to the pellet surface, respectively. A beam-splitter was used to split the incoming radiation from the sample into two halves. While one of the beams was transmitted from the splitter through a bandpass filter to obtain optical images, the other beam was reflected from the splitter to the thermal camera to capture full-field temperature gradients of the as-fabricated pellet surface during cracking. Some initial tests were conducted with a 2-color pyrometer that was later substituted with a forward-looking infrared thermal camera to capture the temperature profiles. A LabVIEW data acquisition system was set up for collecting useful data during experiments.

Original languageEnglish
Article number035101
JournalReview of Scientific Instruments
Volume91
Issue number3
DOIs
StatePublished - Mar 1 2020
Externally publishedYes

Funding

This research is a part of the integrated research project (IRP) IRP FC-1 funded by the U.S. Department of Energy Office of Nuclear Energy’s Nuclear Energy University Programs (NEUP) under Grant No. DE-NE-0008531. This is NEUP Project 16-10905. The submitted manuscript has been authored by a contractor of the U.S. Government under Contract No. DE-AC07-05ID14517. Accordingly, the U.S. Government retains a non-exclusive, royalty free license to publish or reproduce the published form of this contribution, or allow others to do so, for U.S. Government purposes.

Fingerprint

Dive into the research topics of 'Experimental system for studying temperature gradient-driven fracture of oxide nuclear fuel out of reactor'. Together they form a unique fingerprint.

Cite this