U3Si2 behavior in H2O environments: Part II, pressurized water with controlled redox chemistry

A. T. Nelson, A. Migdisov, E. Sooby Wood, C. J. Grote

Research output: Contribution to journalArticlepeer-review

61 Scopus citations

Abstract

Recent interest in U3Si2 as an advanced light water reactor fuel has driven assessment of numerous properties, but characterization of its response to H2O environments is sparse in available literature. The behavior of U3Si2 in H2O containing atmospheres is investigated and presented in a two-part series of articles. This work examines the behavior of U3Si2 following exposure to pressurized H2O at temperatures from 300 to 350 °C. Testing was performed using two autoclave configurations and multiple redox conditions. Use of solid state buffers to attain a controlled water chemistry is also presented as a means to test actinide-bearing systems. Buffers were used to vary the hydrogen concentration between 1 and 30 parts per million H2. Testing included UN, U3Si5, and UO2. Both UN and U3Si5 were found to rapidly pulverize in less than 50 h at 300 °C. Uranium dioxide was included as a control for the autoclave system, and was found to be minimally impacted by exposure to pressurized water at the conditions tested for extended time periods. Testing of U3Si2 at 300 °C found reasonable stability through 30 days in 1–5 ppm H2. However, pulverization was observed following 35 days. The redox condition of testing strongly affected pulverization. Characterization of the resulting microstructures suggests that the mechanism responsible for pulverization under more strongly reducing conditions differs from that previously identified. Hydride formation is hypothesized to drive this transition. Testing performed at 350 °C resulted in rapid pulverization of U3Si2 in under 50 h.

Original languageEnglish
Pages (from-to)81-91
Number of pages11
JournalJournal of Nuclear Materials
Volume500
DOIs
StatePublished - Mar 2018
Externally publishedYes

Funding

This work was conducted at Los Alamos National Laboratory under the National Nuclear Security Administration contract DE-AC52-06NA25396 and supported by the U.S. Department of Energy, Office of Nuclear Energy Nuclear Technology Research and Development program. The assistance of J. Dunwoody and J. White in preparation of the monolithic samples for testing is appreciated. The authors would like to acknowledge reviewer suggestions regarding corollaries of the present study to hydriding of metallic uranium, as these have strengthened the manuscript.

FundersFunder number
Office of Nuclear Energy Nuclear Technology Research and Development program
U.S. Department of Energy
National Nuclear Security AdministrationDE-AC52-06NA25396

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