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Oxidation Studies on NBG-18 Grade Nuclear Graphite

  • Boise State University
  • Center for Advanced Energy Studies

Research output: Contribution to journalArticlepeer-review

1 Scopus citations

Abstract

In this work we focus on the oxidation of grade NBG-18 nuclear graphite in oxygen/nitrogen atmospheres. NBG-18 was chosen because of its potential use in high dosage regions of the pebble bed concept VHTR.

Original languageAmerican English
JournalTransactions of the American Nuclear Society
StatePublished - 1 Jan 2011

Keywords

  • fission reactor fuel
  • gas cooled reactors
  • oxidation

EGS Disciplines

  • Materials Science and Engineering

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