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Journal Articles

Improvement of detection limit in differential die-away analysis system for nuclear non-proliferation and nuclear security

Ozu, Akira; Maeda, Makoto; Komeda, Masao; Toh, Yosuke

Proceedings of 2019 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC 2019), Vol.1, p.101 - 104, 2020/08

Journal Articles

A Large area position-sensitive scintillation neutron detector for upgrading SENJU diffractometer

Nakamura, Tatsuya; To, Kentaro; Ebine, Masumi; Birumachi, Atsushi; Sakasai, Kaoru

Proceedings of 2019 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC 2019), Vol.1, p.735 - 736, 2020/08

 Times Cited Count:0 Percentile:0.09

A large area, position-sensitive scintillation neutron detector was developed for upgrading the SENJU, time-of-flight Laue single crystal neutron diffractometer, in J-PARC MLF. The detector has a neutron-sensitive area of 512 $$times$$ 512 mm with a pixel size of 4 $$times$$ 4 mm. The detector was developed for upgrading of the SENJU instrument. The large area detector is to be installed below the vacuum tank to enlarge a covering solid angle. A $$^{6}$$Li:ZnS (Ag) scintillator and wavelength-shifting fiber technologies are employed. Each fiber channel is read out individually with photon counting mode. The electronics boards are implemented at the backside of the detector, enabling the detector depth as short as 20 cm. The detector exhibited a detection efficiency of 45% for thermal neutron. No degradation in fiber position and in neutron sensitivity has been observed over one year after production. In this paper, detector design and detector performances are presented.

Journal Articles

Real-time data display and storage device for pulsed neutron scattering experiment

To, Kentaro; Nakamura, Tatsuya; Sakasai, Kaoru; Yamagishi, Hideshi*

Proceedings of 2019 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC 2019), Vol.1, p.447 - 449, 2020/08

 Times Cited Count:0 Percentile:0.09

A real-time data display and storage device was developed for pulsed neutron scattering experiments using the time-of-flight method. The device contains two sets of field programmable gate arrays and on-board microcomputers for data display and storage. The developed device can determine the time-of-flight and time-resolved neutron position data with a time range from 0 to 40 ms using a beam of pulsed neutrons at 25 Hz from an experimental facility. Operation tests were performed using test signals that simulate the neutron detector output signals. It was found that the device could separate double pulses with a time interval of 1 $$mu$$s; furthermore, it could measure the continuous pulses with a frequency of 1 MHz. Consequently, it was confirmed that the developed device demonstrated a counting rate capability of beyond 1 Mcps.

Journal Articles

JENDL project and related activities

Tada, Kenichi; Iwamoto, Osamu

Proceedings of 2019 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC 2019), Vol.2, p.1622 - 1624, 2020/08

 Times Cited Count:0 Percentile:0.09

JAEA has published the evaluated nuclear data library JENDL to improve the prediction accuracy of nuclear calculations. JENDL is now one of the most famous evaluated nuclear data libraries in the world. This presentation explains the recent activity of the JENDL project and overview of the next version of general-purpose file JENDL-5. Nuclear calculation codes cannot treat the evaluated nuclear data library. This presentation also explains the nuclear data processing system FRENDY which is used to generate cross section library for a nuclear calculation code.

Oral presentation

System development and challenges for delayed gamma-ray nondestructive assay in safeguard verification of nuclear material

Rossi, F.; Rodriguez, D.; Seya, Michio; Takahashi, Tone; Koizumi, Mitsuo; Abbas, K.*; Crochemore, J.-M.*; Pedersen, B.*; Bogucarska, T.*; Varasano, G.*; et al.

no journal, , 

Oral presentation

Radon measurements in a small chamber using compact organic scintillator-based alpha/beta spectrometer

Morishita, Yuki; Ye, Y.*; Mata, L.*; Pozzi, S.*; Kearfott, K.*

no journal, , 

A compact organic scintillator-based $$alpha beta$$ spectrometer was developed and tested for radon measurements. The spectrometer was composed of a Through Silicon Via (TSV) silicon photomultiplier or SiPM and a 6 mm $$times$$ 6 mm $$times$$ 6 mm stilbene cube crystal. Analog signals from the SiPM were sent to a digitizer. The detector was placed in a light-tight box and a stacked air filter was embedded on the side surface of the light-tight box. A continuous radon monitor, the AlphaGUARD, and $$^{226}$$Ra sources were placed in a small radon chamber constructed using a cylindrical 0.57 m diameter, 0.88 m tall steel drum. By applying a pulse shape discrimination technique, alpha and beta spectra were simultaneously clearly separated and quantitatively measured. Two peaks were registered in the measured alpha spectrum: $$^{218}$$Po was registered in the lower peak and $$^{214}$$Po was registered in the higher peak. A linear relationship was observed between radon counts from the AlphaGUARD and count-rates from the stilbene-SiPM detector. The thickness of the stilbene-SiPM detector was less than 10 mm, thus easy increases insensitivity should be possible with future construction. Thus, the compact organic scintillator-based alpha/beta spectrometer shows promise for use in novel radon detection systems.

Oral presentation

Detection of alpha particle emitters originating from nuclear fuel inside reactor building of Fukushima Daiichi Nuclear Power Station

Morishita, Yuki; Torii, Tatsuo; Usami, Hiroshi; Kikuchi, Hiroyuki*; Utsugi, Wataru*; Takahira, Shiro*

no journal, , 

We measured alpha emitters obtained from a reactor building in the Fukushima Daiichi Nuclear Power Plant (FDNPP) by using an alpha particle imaging detector. For developing the detector, we used a very thin (0.05-mm-thick) a cerium-doped Gd$$_{3}$$(Ga,Al) $$_{5}$$O$$_{12}$$ (Ce GAGG) scintillator and silicon photomultiplier (SiPM) arrays as the photodetector. The floor of the reactor building in FDNPP was wiped off by using smear papers, and the radioactivity of these papers was measured by the alpha particle imaging detector. In addition, we measured a Plutonium (Pu) sample (mainly 5.5 MeV alpha particles from $$^{238}$$Pu) obtained from a nuclear fuel facility by using of the same detector for comparison with the smear papers. The alpha spectrum was in the energy range of 5-6 MeV, which corresponds to the alpha particle energy of $$^{238}$$Pu (5.5 MeV). The correlation coefficient of the alpha spectra of the smear papers and the Pu sample had a strong positive linear relation. Moreover, the peak of $$^{241}$$Am was identified by gamma spectrum measurement. Based on these results, it is highly likely that the alpha emitters in the reactor building of FDNPP are $$^{238}$$Pu and $$^{241}$$Am, which originated from the nuclear fuel. The surface contamination level of alpha emitters exceeded 4 Bq/cm$$^{2}$$.

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