Detailed measurements of local thickness changes for U-7Mo dispersion fuel plates with Al-3.5Si matrix after irradiation at different powers in the RERTR-9B experiment

  • Dennis D. Keiser
  • , Walter Williams
  • , Adam Robinson
  • , Dan Wachs
  • , Glenn Moore
  • , Doug Crawford

Research output: Contribution to journalArticlepeer-review

8 Scopus citations

Abstract

The Materials Management and Minimization program is developing fuel designs to replace highly enriched fuel with fuels of low enrichment. Swelling is an important irradiation behavior that needs to be well understood. Data from high resolution thickness measurements performed on U-7Mo dispersion fuel plates with Al-Si alloy matrices that were irradiated at high power is sparse. This paper reports the results of detailed thickness measurements performed on two dispersion fuel plates that were irradiated at relatively high power to high fission densities in the Advanced Test Reactor in the same RERTR-9B experiment. Both plates were irradiated to similar fission densities, but one was irradiated at a higher power than the other. The goal of this work is to identify any differences in the swelling behavior when fuel plates are irradiated at different powers to the same fission densities. Based on the results of detailed thickness measurments, more swelling occurs when a U-7Mo dispersion fuel with Al-3.5Si matrix is irradiated to a high fission density at high power compared to one irradiated at a lower power to high fission density.

Original languageEnglish
Pages (from-to)448-460
Number of pages13
JournalJournal of Nuclear Materials
Volume494
DOIs
StatePublished - Oct 2017
Externally publishedYes

Funding

This work was supported by the U.S. Department of Energy, Office of Material Management and Minimization, National Nuclear Security Administration, under DOE-NE Idaho Operations Office Contract DE-AC07-05ID14517. This manuscript was authored by a contractor for the U.S. Government. 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. Personnel at the Hot Fuel Examination Facility at the Idaho National Laboratory are acknowledged for their assistance in performing the thickness measurements.

Keywords

  • Dispersion fuel
  • Low-enriched uranium fuel
  • Nuclear fuel
  • Plate fuel
  • Research reactors
  • Swelling
  • Uranium molybdenum alloy

Fingerprint

Dive into the research topics of 'Detailed measurements of local thickness changes for U-7Mo dispersion fuel plates with Al-3.5Si matrix after irradiation at different powers in the RERTR-9B experiment'. Together they form a unique fingerprint.

Cite this