Analytical study for detection method of fuel debris derived from MOX fuel

Terashima, Kenichi ; Sakamoto, Masahiro ; Matsumura, Taichi ; Riyana, E. S. ; Kanno, Ikuo; Okumura, Keisuke

At the time of the Fukushima Daiichi Nuclear Power Station accident, mixed oxide (MOX) fuels were partially loaded in the core of Unit-3 while not in Unit-1 and Unit-2. Since the MOX fuel contain larger amount of plutonium even if its burnup degree is relatively smaller than that of UO $_{2}$ fuel, it is expected to distinguish whether fuel debris are originated from MOX or UO $_{2}$ . Therefore, we focused on $^{244}$ Cm and $^{154}$ Eu generated until the accident. From the burnup calculations, the possibility of a method for detecting the MOX-derived fuel debris was suggested.

Language	:	English
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Meeting title	:	International Topical Workshop on Fukushima-Daiichi Decommissioning Research 2024 (FDR2024)
Held date	:	2024/10
Location (city)	:	Naraha
Location (country)	:	Japan
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Keywords	:	福島第一原子力発電所事故; the Fukushima Daiichi Nuclear Power Station accident; fuel debris; MOX Fuel
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Registration No. : BB20241239
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