Development of nuclear fuel material evaluation method using integral dosimeter; Basic data acquisition of babble detector

Terashima, Kenichi ; Kaburagi, Masaaki ; Sakamoto, Masahiro ; Matsumura, Taichi ; Fujita, Manabu*; Okumura, Keisuke

Bubble detector (BD) is neutron integral dosimeter with advantages of insensitivity to gamma ray, no power supply, visual confirmation and controllability of irradiation time according to neutron flux. Therefore, application of detection and nondestructive measurement for fuel debris is expected at Fukushima Daiichi Nuclear Power Station. Then, basic data of babble detector obtained by neutron irradiation experiment for applicability evaluation of BD.

Language	:	Japanese
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Meeting title	:	日本原子力学会2019年秋の大会
Held date	:	2019/09
Location (city)	:	富山
Location (country)	:	日本
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Keywords	:	福島第一原子力発電所事故; Fukushima Daiichi Nuclear Power Station Accident
Research Facility	:	FRS(放射線標準施設)
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Registration No. : BB20190628
JAEA Abstracts No. :
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