Corrosion behavior of unirradiated oxide fuel pellets in high temperature water

K. Une, S. Kashibe, K. Nogita

Research output: Contribution to journalArticle

8 Citations (Scopus)

Abstract

In order to elucidate fuel wash-out behavior after the degraded secondary failure of LWR fuel rods, corrosion experiments in high temperature and high pressure water of 340°C and 15 MPa were conducted for unirradiated oxide fuels, two each of undoped UO2 with two different grain sizes, 5 wt% Gd2O3- and 10 wt% Gd2O3-doped UO2. In degassed water of dissolved oxygen concentration (DO) equal to 10 ppb, no corrosion or oxidation was found, but the corrosion became noticeable above DO = 3 ppm. Pellet oxidation proceeded with U4O9 formation along the grain boundaries and subsequent U4O9 growth into enveloped UO2 grains. Consequently, the grain boundary penetration rate in the oxygenated water followed a diffusion-controlled parabolic law. Mismatch in the O/U ratio between the grain boundaries and interiors led to weakened boundaries, which is the cause of fuel wash-out in heavily degraded fuel rods. Both increases of grain size and Gd2O3 content were found to provide improved corrosion resistance.

Original languageEnglish
Pages (from-to)32-39
Number of pages8
JournalJournal of Nuclear Materials
Volume227
Issue number1-2
DOIs
Publication statusPublished - Dec 1995

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

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