Irradiation and penetration tests of boron-doped low activation concrete using 2.45 and 14 MeV neutron sources

Morioka, A.; Sato, Satoshi; Kinno, M.; Sakasai, A.; Hori, Jun‐ichi; Ochiai, Kentaro; Yamauchi, M.; Nishitani, T.; Kaminaga, A.; Masaki, K.; Sakurai, S.; Hayashi, Takao; Matsukawa, M.; Tamai, Hiroshi; Ishida, S.

doi:10.1016/j.jnucmat.2004.04.143

Cited by 12 publications

(4 citation statements)

References 8 publications

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“…The cryostat consists of the 220 mm thickness of the concrete between two SS304 panels of 34 mm (inboard) and 6 mm (outboard) thicknesses. The low activation concrete contaminated with B 4 C (Boron: 2 wt %) is adopted to improve the shielding efficiency of the thermal neutrons through the vacuum vessel 8) .…”

Section: Radiation Shieldingmentioning

confidence: 99%

Neutronic Analysis of Fusion Tokamak Devices by PHITS

Sukegawa

Takiyoshi

Amano

et al. 2011

Progress in Nuclear Science and Technology

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A complete 3D neutronic analysis by PHITS (Particle and Heavy Ion Transport code System) has been performed for fusion tokamaku devices such as JT-60U device and JT-60 Superconducting tokamak device (JT-60 Super Advanced). The mono-energetic neutrons (E n =2.45 MeV) of the DD fusion devices are used for the neutron source in the analysis. The visual neutron flux distribution for the estimation of the port streaming and the dose rate around the fusion tokamak devices has been calculated by the PHITS. The PHITS analysis makes it clear that the effect of the port streaming of superconducting fusion tokamak device with the cryostat is crucial and the calculated neutron spectrum results by PHITS agree with the MCNP-4C2 results.

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Section: Radiation Shieldingmentioning

confidence: 99%

Neutronic Analysis of Fusion Tokamak Devices by PHITS

Sukegawa

Takiyoshi

Amano

et al. 2011

Progress in Nuclear Science and Technology

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“…The low activation concrete contaminated with B 4 C (Boron: 2 wt%) is adopted to improve the shielding efficiency of the thermal neutrons through the vacuum vessel [11]. As shown in Fig.…”

Section: Cryostat Designmentioning

confidence: 99%

Safety design of radiation shielding for JT-60SA

Sukegawa¹,

Sakurai²,

Masaki³

et al. 2007

Fusion Engineering and Design

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“…As such, many groups have used fast, high energy neutrons from spontaneous fission radioisotopes [14] and beam-on-target nuclear fusion [15] for imaging. Deuterium-tritium (D-T) fusion neutrons at 14.1 MeV provide the highest penetration possible for a portable, commercial-off-the-shelf neutron generator [16].…”

Section: Introductionmentioning

confidence: 99%

Scalable Detector Design for a High-Resolution Fast-Neutron Radiography Panel

Young

Browning

Thurber

et al. 2023

Preprint

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Development of a scalable flat-panel neutron radiography device is needed to meet the nondestructive testing needs of a growing industrial market. Flood field images from a Cs-137 gamma source and a Cf-252 fission neutron source were generated using a detector composed of a 3-mm-thick sheet of EJ-200, and 3-mm-thick sheet of acrylic light spreader, an 8 × 8 array of SensL MICROFJ-60035-TSV SiPMs, and an IDEAS ROSSPAD readout module. The readout module can be tiled together with similar systems to create a panel of any size, and is only limited by the number of available Ethernet ports in a switching system. A collimated gamma line image demonstrated a 90% spatial resolution of approximately 0.47 line pairs per centimeter and a 10% spatial resolution of approximately 2.32 line pairs per centimeter. A neutron edge image demonstrated a 90% spatial resolution of approximately 0.70 line pairs per centimeter and a 10% spatial resolution of approximately 3.35 line pairs per centimeter. Both of these images show the ability to generate radiographs with sub-SiPM spatial resolution. Using these readout modules, a large-scale radiographic panel can be developed by tiling ROSSPAD modules together.

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Irradiation and penetration tests of boron-doped low activation concrete using 2.45 and 14 MeV neutron sources

Cited by 12 publications

References 8 publications

Neutronic Analysis of Fusion Tokamak Devices by PHITS

Neutronic Analysis of Fusion Tokamak Devices by PHITS

Safety design of radiation shielding for JT-60SA

Scalable Detector Design for a High-Resolution Fast-Neutron Radiography Panel

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