Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Channel Gap Measurements of Irradiated Plate Fuel and Comparison with Post-Irradiation Plate Thickness

  • James A. Smith (Nuclear Science and Technology Division, Idaho National Laboratory) ;
  • Casey J. Jesse (Nuclear Science and Technology Division, Idaho National Laboratory) ;
  • William A. Hanson (Nuclear Science and Technology Division, Idaho National Laboratory) ;
  • Clark L. Scott (Nuclear Science and Technology Division, Idaho National Laboratory) ;
  • David L. Cottle (Nuclear Science and Technology Division, Idaho National Laboratory)
  • Received : 2022.11.09
  • Accepted : 2023.02.24
  • Published : 2023.06.25
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Abstract

One of the salient nuclear fuel performance parameters for new fuel types under development is changes in fuel thickness. To test the new commercially fabricated U-10Mo monolithic plate-type fuel, an irradiation experiment was designed that consisted of multiple mini-plate capsules distributed within the Advanced Test Reactor (ATR) core, the mini-plate 1 (MP-1) experiment. Each capsule contains eight mini-plates that were either fueled or "dummy" plates. Fuel thickness changes within a fuel assembly can be characterized by measuring the gaps between the plates ultrasonically. The channel gap probe (CGP) system is designed to measure the gaps between the plates and will provide information that supports qualification of U-10Mo monolithic fuel. This study will discuss the design and the results from the use of a custom-designed CGP system for characterizing the gaps between mini-plates within the MP-1 capsules. To ensure accurate and repeatable data, acceptance and calibration procedures have been developed. Unfortunately, there is no "gold" standard measurement to compare to CGP measurements. An effort was made to use plate thickness obtained from post-irradiation measurements to derive channel gap estimates for comparison with the CGP characterization.

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Acknowledgement

This work was supported by DOE Idaho Operations Office Contract DE-AC07-05ID14517. Accordingly, the U.S. Government retains and the publisher, by accepting the article for publication, acknowledges that the U.S. Government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript or allow others to do so, for U.S. Government purposes. This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof. The authors would like to acknowledge the PIs, staff, engineers, and operators of the INL Materials and Fuels Complex (MFC) Hot Fuel Examination Facility (HFEF) for their efforts during the post-irradiation examinations and specifically G. C. Papaioannou and B. K. Allen for their work on the BONA4INL measurement bench and A. B. Robinson for his input and expertise on PIE profilometry. The authors would also like to thank G. K. Housley for providing graphical representations of the MP-1 irradiation experiment capsules, the MP-1 experimental irradiation team for implementing the experiment, D. O. Choe for providing the MP-1 neutronics information, and ATR operators for performing the work.

References

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