Determination of occluded gases in mixed oxide fuel pellets using gas sampling unit and gas chromatography

T. Hiyama, S. Sugaya, J. Yamamoto, K. Kamimura

Research output: Contribution to journalArticle

3 Citations (Scopus)

Abstract

A new technique for the determination of occluded gases in sintered plutonium-uranium mixed oxide (MOX) fuel pellets was developed. The gases extracted from the sample at vacuum condition were injected into a gas chromatograph through an originally developed gas sampling unit. The gases were simultaneously determined using the improved gas chromatograph equipped with several separation columns and a photoionization detector. The relative standard deviations (n = 10) were 1.0, 3.4, 0.6, 1.0, 1.4, 0.8 and 0.9% for H2, O2, N2, CH4, CO2, CO and C2H6, respectively. The gases H2, O2, N2, CH4, CO2 and CO from the MOX fuel pellets were simultaneously determined in this study. The results of gas analysis using this method were in agreement with that of high temperature vacuum extraction method in the range less than 300 μl of extracted gas.

Original languageEnglish
Pages (from-to)1-7
Number of pages7
JournalJournal of Nuclear Materials
Volume218
Issue number1
DOIs
Publication statusPublished - Jan 1995
Externally publishedYes

All Science Journal Classification (ASJC) codes

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

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