The Possible use of short half-life noble gas fission products for measurement of criticality and identification of plutonium in fuel debris canister

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

Fuel debris has inherent neutron sources due to mostly spontaneous fissions. Therefore, the fuel debris inside a canister can be seen as a subcritical system with fixed neutron sources. A depletion calculation for the fuel debris inside the canister has been performed. The calculation results show the activity ratio of $^{88}$ Kr-to- $^{135}$ Xe in the fuel debris canister depending on the material compositions and effective neutron multiplication factor.

Language	:	English
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Meeting title	:	日本原子力学会2021年秋の大会
Held date	:	2021/09
Location (city)	:	札幌(online)
Location (country)	:	日本
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Keywords	:	Depletion Calculation; Subcritical System; Fuel Debris Canister; Mixed Oxide Fuel; Monte Carlo Calculation; Short Half-life Fission Products; MOX Fuel; Fukushima Daiichi Nuclear Power Station Accident; 福島第一原子力発電所事故
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Registration No. : BB20210308
JAEA Abstracts No. :
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