Quantitative analysis of occluded gases in mixed oxide fuel pellets by high temperature and vacuum extraction-gas chromatography
- 1. Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works
Description
We have developed a technique for the quantitative analysis of an occluded gases in the sintered plutonium-uranium mixed oxide (MOX) fuel pellets. The total volume of occluded gases in MOX pellet was determined using a high temperature and vacuum extraction system. The extracted gases were transferred into a special gas sampler by the McLeod gauge and their gas components were analyzed using the gas chromatography technique. Hydrogen, oxygen, nitrogen, methane, carbondioxide and carbonmonoxide were detected in the extracted gases. Relative standard deviation (n=10) were 1.0, 3.4, 0.6, 1.0, 1.4, 0.8 and 0.9 % for hydrogen, oxygen, nitrogen, methane, carbondioxide, carbonmonoxide and ethane, respectively. The time required for one determination is less than one hour. (author)
Additional details
Publishing Information
- Journal Title
- Donen Giho
- Journal Issue
- no.87
- Journal Page Range
- p. 45-52.
- ISSN
- 0289-6605
- CODEN
- DOGIEL
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 25028979
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCURACY; BENCH-SCALE EXPERIMENTS; FUEL PELLETS; GAS CHROMATOGRAPHY; GASES; MIXED OXIDE FUELS; PLUTONIUM; QUANTITATIVE CHEMICAL ANALYSIS; SAMPLERS
- Descriptors DEC
- ACTINIDES; CHEMICAL ANALYSIS; CHROMATOGRAPHY; ELEMENTS; ENERGY SOURCES; EQUIPMENT; FLUIDS; FUELS; LABORATORY EQUIPMENT; MATERIALS; METALS; NUCLEAR FUELS; REACTOR MATERIALS; SEPARATION PROCESSES; SOLID FUELS; TRANSURANIUM ELEMENTS