2017 Annual Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 301-1 Reactor Physics, Utilization of Nuclear Data, Criticality Safety

[2F09-12] Analysis Method Development and V&V 2

Tue. Mar 28, 2017 2:45 PM - 3:50 PM Room F (16-206 Building No.16)

Chair: Tadafumi Sano (Kyoto Univ.)

2:45 PM - 3:00 PM

[2F09] Feasibility study on burn-up estimation technique of spent LWR-MOX fuel by simple passive gamma spectrometry

*Yonosuke Nabeta1, Hiroshi Sagara2 (1. Department of nuclear engineering Tokyo Institute of Technology , 2. Laboratory for Advanced Nuclear Energy Institute for Innovative Research Tokyo Institute of Technology)

Keywords:Passive gamma spectrometry, Burn-up, MOX, Lanthanoid

The aim of this study was to evaluate the adaptability of a new burn-up estimation technique insensitive to Cs retention to LWR-MOX spent fuel, and to clarify the applicable ranges and conditions quantitatively. The burn-up estimation technique, using 134Cs/137Cs, 154Eu/144Ce, 154Eu/137Cs, 154Eu/134Cs, was validated, adapting to post irradiation examination results of nuclide inventory of LWR-MOX fuel, and to calculation results of nuclide inventory spatial distribution and gamma-ray source spectrum of LWR-MOX assembly.