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 language | English |
---|---|
Pages (from-to) | 1-7 |
Number of pages | 7 |
Journal | Journal of Nuclear Materials |
Volume | 218 |
Issue number | 1 |
DOIs | |
Publication status | Published - Jan 1995 |
Externally published | Yes |
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- General Materials Science
- Nuclear Energy and Engineering