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Journal Articles

Neutron/$$gamma$$-ray discrimination based on the property and thickness controls of scintillators using Li glass and LiCAF(Ce) in a $$gamma$$-ray field

Kaburagi, Masaaki; Shimazoe, Kenji*; Terasaka, Yuta; Tomita, Hideki*; Yoshihashi, Sachiko*; Yamazaki, Atsushi*; Uritani, Akira*; Takahashi, Hiroyuki*

Nuclear Instruments and Methods in Physics Research A, 1046, p.167636_1 - 167636_8, 2023/01

https://doi.org/10.1016/j.nima.2022.167636

We focus on the thickness and property controls of inorganic scintillators used for thermal neutron detection in intense $$gamma$$-ray fields without considering pulse shape discrimination techniques. GS20$$^{rm{TM}}$$ (a lithium glass) and LiCaAlF$$_6$$:Ce(LiCAF:Ce) cintillators with thicknesses of 0.5 and 1.0 mm, respectively, have been employed. Pulse signals generated by photomultiplier tubes, to which the scintillators were coupled, were inserted into a digital pulse processing unit with 1 Gsps, and the areas of waveforms were integrated for 360 ns. In a $$^{60}$$Co $$gamma$$-ray field, the neutron detection for GS20$$^{rm{TM}}$$ with a 0.5-mm thickness was possible at dose rates of up to 0.919 Gy/h; however, for LiCAF:Ce, neutron detection was possible at 0.473 Gy/h, and it failed at 0.709 Gy/h. Threfore, in a $$^{60}$$Co $$gamma$$-ray field, the neutron/$$gamma$$-ray discrimination of GS20$$^{rm{TM}}$$ was better than that of LiCAF:Ce due to its better energy resolution and higher detection efficiency.

Journal Articles

Identification and quantification of a $$^{60}$$Co radiation source under an intense $$^{137}$$Cs radiation field using an application-specific CeBr$$_3$$ spectrometer suited for use in intense radiation fields

Kaburagi, Masaaki; Shimazoe, Kenji*; Kato, Masahiro*; Kurosawa, Tadahiro*; Takahashi, Hiroyuki*

Journal of Nuclear Science and Technology, 59(8), p.983 - 992, 2022/08

https://doi.org/10.1080/00223131.2022.2026833
 Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)

Journal Articles

Improvement of analysis results from the GAGG scintillator Compton camera operated on an unmanned helicopter by selecting stable flight conditions

Shikaze, Yoshiaki; Shimazoe, Kenji*

Journal of Nuclear Science and Technology, 59(1), p.44 - 54, 2022/01

https://doi.org/10.1080/00223131.2021.1948452
 Times Cited Count：1 Percentile：25.87(Nuclear Science & Technology)

A Compton camera system for use on an unmanned helicopter was previously developed for characterizing the distribution of radioactive materials in highly contaminated areas. For this study, a small camera, a laser distance meter, an attitude angles sensor, temperature sensors, and real-time monitoring software were equipped to the Compton camera system to better measure flight parameters and to more precisely detect hot spot locations. To confirm if detection results were improved by the modifications, measurements were taken from hovering and programmed flights over a field in Okuma, Fukushima Prefecture (Japan). Ambient dose equivalent rate distributions at ground level were obtained by processing the flight data, then compared against measurements taken at ground level on foot using a survey meter. For one hovering flight, the correlation between the datasets was improved by selecting a period of stable flight position and attitude, and by restricting the deviation of the attitude angles. Between 6.0%-7.6% improvement in the position resolution was achieved by using the data from stable flight periods, even when using 1 minute data windows. The precision of hot spot detections and ambient dose equivalent rate distributions obtained from the Compton camera were thus improved by the aforementioned modifications to the system.

Journal Articles

Development of the multi-cubic $$gamma$$-ray spectrometer and its performance under intense $$^{137}$$Cs and $$^{60}$$Co radiation fields

Kaburagi, Masaaki; Shimazoe, Kenji*; Kato, Masahiro*; Kurosawa, Tadahiro*; Kamada, Kei*; Kim, K. J.*; Yoshino, Masao*; Shoji, Yasuhiro*; Yoshikawa, Akira*; Takahashi, Hiroyuki*

Nuclear Instruments and Methods in Physics Research A, 1010, p.165544_1 - 165544_9, 2021/09

https://doi.org/10.1016/j.nima.2021.165544
 Times Cited Count：0 Percentile：0.02(Instruments & Instrumentation)

The number of nuclear facilities being decommissioned has been increasing worldwide, in particular following the accident of the Tokyo Electric Power Company Holdings' Fukushima Daiichi Nuclear Power Station in 2011. In these nuclear facilities, proper management of radioactive materials is required. Then, A $$gamma$$-ray spectrometer with four segmentations using small volume CeBr$$_{3}$$ scintillators with a dimension of $$5 times 5 times 5$$ $$rm{mm}^3$$ was developed. The four scintillators were coupled to a multi-anode photomultiplier tube specific to intense radiation fields. We performed the $$gamma$$-ray exposure study under $$^{137}$$Cs and $$^{60}$$Co radiation fields. Under the $$^{137}$$Cs radiation field, the relative energy resolution at 1375 mSv/h was the relative energy resolution at 1375 mSv/h was 9.2$$pm$$0.05%, 8.0$$pm$$0.08%, 8.0$$pm$$0.03%, and 9.0$$pm$$0.04% for the four channels, respectively.

Journal Articles

Gamma-ray spectroscopy with a CeBr$$_3$$ scintillator under intense $$gamma$$-ray fields for nuclear decommissioning

Kaburagi, Masaaki; Shimazoe, Kenji*; Kato, Masahiro*; Kurosawa, Tadahiro*; Kamada, Kei*; Kim, K. J.*; Yoshino, Masao*; Shoji, Yasuhiro*; Yoshikawa, Akira*; Takahashi, Hiroyuki*; et al.

Nuclear Instruments and Methods in Physics Research A, 988, p.164900_1 - 164900_8, 2021/02

https://doi.org/10.1016/j.nima.2020.164900
 Times Cited Count：6 Percentile：79.86(Instruments & Instrumentation)

An increasing number of nuclear facilities have been decommissioned worldwide following the 2011 accident of the TEPCO' Fukushima Daiichi Nuclear Power Station. During the decommissioning, radioactive materials have to be retrieved under proper management. In this study, a small cubic CeBr$$_3$$ spectrometer with dimensions of 5 mm $$times$$ 5 mm $$times$$ 5 mm was manufactured to perform $$gamma$$-ray spectroscopy under intense $$gamma$$-ray fields. Furthermore, thanks to a fast digital process unit and a customized photomultiplier, the device could perform $$gamma$$-ray spectroscopy at dose rates of over 1 Sv/h. The energy resolution (FWHM) at 662 keV ranged from 4.4% at 22 mSv/h to 5.2% at 1407 mSv/h for a $$^{137}$$Cs radiation field. Correspondingly, at 1333 keV, it ranged from 3.1% at 26 mSv/h to 4.2% at 2221 mSv/h for a $$^{60}$$Co radiation field, which suggested to realize $$gamma$$-ray assessment of $$^{134}$$Cs, $$^{137}$$Cs, $$^{60}$$Co, and $$^{154}$$Eu at dose rates of over 1 Sv/h.

Journal Articles

A Cubic CeBr$$_{3}$$ gamma-ray spectrometer suitable for the decommissioning of the Fukushima Daiichi Nuclear Power Station

Kaburagi, Masaaki; Shimazoe, Kenji*; Otaka, Yutaka*; Uenomachi, Mizuki*; Kamada, Kei*; Kim, K. J.*; Yoshino, Masao*; Shoji, Yasuhiro*; Yoshikawa, Akira*; Takahashi, Hiroyuki*; et al.

Nuclear Instruments and Methods in Physics Research A, 971, p.164118_1 - 164118_8, 2020/08

https://doi.org/10.1016/j.nima.2020.164118
 Times Cited Count：6 Percentile：70.41(Instruments & Instrumentation)

Journal Articles

Gamma-ray imaging system for Fukushima Daiichi Nuclear Power Plant using silicon strip detector

Kaburagi, Masaaki; Sato, Yuki; Yoshihara, Yuri*; Shimazoe, Kenji*; Takahashi, Hiroyuki*; Torii, Tatsuo

Reactor Dosimetry; 16th International Symposium on Reactor Dosimetry (ISRD-16) (ASTM STP 1608), p.405 - 414, 2018/11

https://doi.org/10.1520/STP160820170070
 Times Cited Count：0 Percentile：0.05

Journal Articles

Field test around Fukushima Daiichi Nuclear Power Plant site using improved Ce:Gd$$_{3}$$(Al,Ga)$$_{5}$$O$$_{12}$$ scintillator Compton camera mounted on an unmanned helicopter

Shikaze, Yoshiaki; Nishizawa, Yukiyasu; Sanada, Yukihisa; Torii, Tatsuo; Jiang, J.*; Shimazoe, Kenji*; Takahashi, Hiroyuki*; Yoshino, Masao*; Ito, Shigeki*; Endo, Takanori*; et al.

Journal of Nuclear Science and Technology, 53(12), p.1907 - 1918, 2016/12

https://doi.org/10.1080/00223131.2016.1185980
 Times Cited Count：31 Percentile：95.74(Nuclear Science & Technology)

The Compton camera was improved for use with the unmanned helicopter. Increase of the scintillator array from 4$$times$$4 to 8$$times$$8 and expanse of the distance between the two layers contributed to the improvements of detection efficiency and angular resolution, respectively. Measurements were performed over the riverbed of the Ukedo river of Namie town in Fukushima Prefecture. By programming of flight path and speed, the areas of 65 m $$times$$ 60 m and 65 m $$times$$ 180 m were measured during about 20 and 30 minutes, respectively. By the analysis the air dose rate maps at 1 m height were obtained precisely with the angular resolution corresponding to the position resolution of about 10 m from 10 m height. Hovering flights were executed over the hot spot areas for 10-20 minutes at 5-20 m height. By using the reconstruction software the $$gamma$$-ray images including the hot spots were obtained with the angular resolution same as that evaluated in the laboratory (about 10$$^{circ}$$).

Oral presentation

Development of energy recognizable type gamma camera mounted on the unmanned helicopter, 3; Field test around the Fukushima Daiichi NPP site

Shikaze, Yoshiaki; Torii, Tatsuo; Shimazoe, Kenji*; Jiang, J.*; Takahashi, Hiroyuki*; Kurosawa, Shunsuke*; Kamada, Kei*; Yoshikawa, Akira*; Yoshino, Masao*; Ito, Shigeki*; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of energy recognizable type gamma camera mounted on the unmanned helicopter II, 2; Field test around the Fukushima Daiichi NPP site

Shikaze, Yoshiaki; Torii, Tatsuo; Nishizawa, Yukiyasu; Yoshida, Mami*; Shimazoe, Kenji*; Jiang, J.*; Takahashi, Hiroyuki*; Kurosawa, Shunsuke*; Kamada, Kei*; Yoshikawa, Akira*; et al.

no journal, , 

no abstracts in English

Oral presentation

Study on silicon semiconductor detector for visualization the pollution distribution in the Fukushima Daiichi Nuclear Power Plant

Yoshihara, Yuri*; Shimazoe, Kenji*; Takahashi, Hiroyuki*; Kaburagi, Masaaki; Torii, Tatsuo

no journal, , 

The accident of Fukushima Daiichi Nuclear Power Plant (FDNPP) was occurred on March 11th and the decommissioning of Unit 1-4 of FDNPP has been started since December 2011. Portable radiation imaging technologies are necessary for monitoring the pollution distribution of the inside of the reactor buildings because the measurement environment is highly contaminated and the detector should be mounted on remote-controlled robots. However, existing radiation-imaging systems mainly adopt mechanical collimation to estimate the inserted direction of $$gamma$$ ray by using lead or tungsten, which make the systems heavy and limit the operation range of the robots. We have been investigated a stacked edge-on silicon strip detector based on hetero-junction technology, which has directivity without any mechanical collimations for imaging The directivity of the 6-layer stacked silicon strip detector was evaluated. The source of 1 MBq Cs-137 was put on the distance of 10 cm from the front of the detector and rotated with the angles of 0, 15, 30, 60, 90 degree, and the detection counts of each rotate angle were measured with thresholds of 180/360 keV.

Oral presentation

$$gamma$$-ray imaging system for Fukushima Daiichi Nuclear Power Plant using silicon strip detector

Kaburagi, Masaaki; Sato, Yuki; Yoshihara, Yuri*; Shimazoe, Kenji*; Takahashi, Hiroyuki*; Torii, Tatsuo

no journal, , 

Oral presentation

Fundamental study of fast high energy gamma-ray spectrometer

Kaburagi, Masaaki; Shimazoe, Kenji*; Otaka, Yutaka*; Foong, W. S.*; Uenomachi, Mizuki*; Kamada, Kei*; Kin, J. Y.*; Yoshino, Masao*; Yoshikawa, Akira*; Takahashi, Hiroyuki*; et al.

no journal, , 

https://f-archive.jaea.go.jp/dspace/handle/faa/184143

no abstracts in English

Oral presentation

CeBr$${}_3$$ gamma-ray spectrometer toward the decommissioning of the Fukushima Daiichi Nuclear Power Station

Kaburagi, Masaaki; Shimazoe, Kenji*; Otaka, Yutaka*; Foong, W. S.*; Uenomachi, Mizuki*; Kamada, Kei*; Yoshino, Masao*; Shoji, Yasuhiro*; Yoshikawa, Akira*; Takahashi, Hiroyuki*; et al.

no journal, , 

no abstracts in English

Oral presentation

Introduction to multi Cubic high energy gamma-ray spectrometer

Kaburagi, Masaaki; Shimazoe, Kenji*; Otaka, Yutaka*; Uenomachi, Mizuki*; Kamada, Kei*; Kim, J.*; Yoshino, Masao*; Shoji, Yasuhiro*; Yoshikawa, Akira*; Takahashi, Hiroyuki*; et al.

no journal, , 

Oral presentation

Investigation on distribution of radioactive substances in Fukushima, 4; Improvement of the GAGG scintillator gamma camera mounted on the unmanned helicopter

Shikaze, Yoshiaki; Shimazoe, Kenji*

no journal, , 

no abstracts in English

Oral presentation

Performance study of multi cubic high energy $$gamma$$-ray spectrometric system for the decommissioning of the Tokyo Electric Power Company Fukushima Daiichi Nuclear Power Station

Kaburagi, Masaaki; Shimazoe, Kenji*; Otaka, Yutaka*; Uenomachi, Mizuki*; Kamada, Kei*; Kim, K. J.*; Yoshino, Masao*; Shoji, Yasuhiro*; Yoshikawa, Akira*; Takahashi, Hiroyuki*; et al.

no journal, , 

The retrieval of the nuclear fuel debris, which is the substance including melted nuclear fuel and structural materials, will be started from fiscal 2021. Then, as a non-destructive analysis technology of the nuclear fuel debris, a $$gamma$$-ray spectroscopy system is being developed to measure high energy $$gamma$$ rays due to $$^{154}$$Eu and nuclear reactions under high dose rate, which was composed of a CeBr$$_{3}$$ cubic, photomultiplier tube, and fast signal processing unit. This presentation reports that the exposure study of the detector system was performed for a $$_{60}$$Co field at the dose rates of up to 750 mSv/h, and the detector response was investigated at each dose rate.

Oral presentation

Development of $$gamma$$-ray spectrometry system specific to high dose-rate radiation fields for the retrieval of nuclear fuel debris in Tokyo Electrical Power Company Holdings' Fukushima Daiichi Nuclear Power Station

Kaburagi, Masaaki; Shimazoe, Kenji*; Kato, Masahiro*; Kurosawa, Tadahiro*; Kamada, Kei*; Kim, K. J.*; Yoshino, Masao*; Shoji, Yasuhiro*; Yoshikawa, Akira*; Takahashi, Hiroyuki*; et al.

no journal, , 

The retrieval of nuclear fuel debris will be started at Tokyo Electrical Power Company Holdings' Fukushima Daiichi Nuclear Power Station. Because of high dose-rate fields on the surface of nuclear fuel debris and these inhomogeneous elements, non-destructive analysis is required during the retrieval. Here, it is presented that a $$gamma$$-ray spectrometry system specific to high dose-rate fields was developed and its performance under intense $$gamma$$-ray fields was evaluated for the retrieval of nuclear fuel debris.

Oral presentation

Development of $$gamma$$-ray spectrometry system suited in high dose-rate radiation fields for use in non-destructive assay of nuclear fuel debris

Kaburagi, Masaaki; Shimazoe, Kenji*; Kurosawa, Tadahiro*; Kato, Masahiro*; Takahashi, Hiroyuki*

no journal, , 

no abstracts in English

Oral presentation

Development of non-destructive assay for nuclear fuel debris; Development of $$gamma$$-ray sepctrometry system for use at high dose rates

Kaburagi, Masaaki; Takahashi, Hiroyuki*; Shimazoe, Kenji*; Kurosawa, Tadahiro*; Kato, Masahiro*

no journal, , 

no abstracts in English

Oral presentation

Remote control technology for monitoring inside RPV pedestal during retrieval of fuel debris

Matsuhira, Nobuto*; Komatsu, Ren*; Nakashima, Shinsuke*; Yamashita, Atsushi*; Fukui, Rui*; Takahashi, Hiroyuki*; Shimazoe, Kenji*; Woo, H.*; Tamura, Yusuke*; Takashi, Takayuki*; et al.

no journal, , 

21 (Records 1-20 displayed on this page)