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

[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.