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Development of a new measurement method for fast breeder reactor fuel burnup using a shielded ion microprobe analyzer

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:6412951
A new method of burnup measurement using a shielded ion microprobe analyzer (SIMA) has been developed. The method is based on the isotope analysis of uranium, plutonium, and fission products in irradiated mixed oxide fuel by means of secondary ion mass spectrometry (SIMS). Fourteen samples irradiated in the Japanese experimental fast reactor JOYO were examined. The maximum local burnup of JOYO MK-I core fuels was about5.1 at. %. The axial burnup distribution of the fuel pin was in good agreement with that of the sibling pin in the same subassembly, measured by surface ionization mass spectrometry, which requires the chemical separation of fission products and heavy metals. The new method facilitates the rapid and accurate measurement of fast breeder reactor fuel burnup without human radiation exposure during sample preparation and analysis.
Research Organization:
Power Reactor and Nuclear Fuel Development Corporation, Oarai Engineering Center, Fuel and Materials Division, Analysis and Evaluation Section, Oarai, Higashi Ibaraki-gun, Ibaraki-ken
OSTI ID:
6412951
Journal Information:
Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 69:1; ISSN NUTYB
Country of Publication:
United States
Language:
English