A neutron detector on the basis of a boron-containing plastic scintillator

Britvich, G.I.; Vasil’chenko, V.G.; Gilitsky, Yu.; Chubenko, A. P.; Kushnirenko, A. E.; Mamidzhanyan, E.A.; Pavluchenko, V. P.; Pikalov, V. A.; Romakhin, V. A.; Soldatov, A. P.; Sumaneev, Oleg; Chernichenko, S.; Shein, I.; Shepetov, A. L.

doi:10.1016/j.nima.2005.04.083

Cited by 11 publications

(5 citation statements)

References 18 publications

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“…These photoelectric events are particularly enhanced for X-rays/low energy gamma rays, enabling possible spectrometry for these types of radiations. Lithium ( 6 Li), 16,17 boron ( 10 B) [18][19][20][21] and gadolinium 22,23 were employed for thermal neutron detection due to their high capture cross-section.…”

Section: Introductionmentioning

confidence: 99%

Understanding the behaviour of different metals in loaded scintillators: discrepancy between gadolinium and bismuth

Bertrand¹,

Dumazert²,

Sguerra³

et al. 2015

J. Mater. Chem. C

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Organometallic chemistry has recently gained a lot of attention in the domain of plastic scintillators.Homogenously dispersed metal complexes in a polymer matrix can afford plastic scintillators with unseen abilities. Heavy atom loading is very attractive as it gives access to plastics with increased sensitivity towards elusive radiations such as gamma and neutron. But this comes with a drawback, as heavy atoms tend to quench fluorescence, hence decreasing the scintillation yield. We present here a comprehensive study of this phenomenon with bismuth and gadolinium complexes. We investigate the influence of the ligand nature by varying organometallic and fluorophore concentration to probe their interaction. We also propose an explanation of the difference in behavior between these two metals. These results were applied to the fabrication of large volume loaded plastic scintillators (4100 cm 3 ). Bismuth loaded scintillators displayed characteristics equivalent to lead loaded commercial materials, and gadolinium samples proved to be able to capture thermal neutrons and release gamma rays. of our optimization, large scale loaded PSs (4100 cm 3 ) were synthesized and characterized.

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Section: Introductionmentioning

confidence: 99%

Understanding the behaviour of different metals in loaded scintillators: discrepancy between gadolinium and bismuth

Bertrand¹,

Dumazert²,

Sguerra³

et al. 2015

J. Mater. Chem. C

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“…Since the 1950s, boron-based scintillators have been proposed [5] and their improved detection efficiency has been proven [6]. Boron-based scintillators have been deployed in the form of glass [7][8][9] and plastic scintillators [10][11][12][13]. However, in previous attempts at creating boron-based scintillator screens [14][15][16], mixtures of boron-containing powders and ZnS powder had grain sizes on the order of many micrometers, so the reaction products hardly had a chance to escape their grain if they were not created close to the surface.…”

Section: Boron-based Screensmentioning

confidence: 99%

Performance of borated scintillator screens for high-resolution neutron imaging

Schillinger

Chuirazzi

Craft

et al. 2022

J Radioanal Nucl Chem

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The most commonly used screens for neutron imaging consist of 6LiF + ZnS. This type of screen yields the highest light output per detected neutron. For high resolution, gadolinium oxysulfide (GOS, Gadox) screens are employed, which have a much higher detection efficiency, but a light output so much lower than LiF + ZnS that measurements are often limited by photon statistics. Historically, screens using boron as a neutron-sensitive material have not been very successful. However, a new preparation method was introduced recently that produces light output higher than Gadox with detection efficiency greater than LiF + ZnS. Measurements of these new borated screens were performed at the NeXT facility at ILL, Grenoble, in comparison to a high resolution Gadox screen.

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“…[1,5]. Notable new developments, subsequent to 1979, are the boron-loaded plastic scintillator [14] (detector 3 in Table 1) and the lithium-loaded liquid scintillator [15][16][17][18] (detector 6). ].…”

Section: Low-energy Neutron Detectorsmentioning

confidence: 99%

“…Another method that uses response functions for full energy deposition by neutrons within the detector is the double-pulse [20] or capture-gated neutron spectrometer. This spectrometer is based on the combination of neutron moderation in an organic scintillator and capture of the thermalised neutrons in either the same scintillator or an associated separate scintillator [14,28,163,164]. The scintillator in which neutron capture takes place incorporates a small concentration of a nuclide such as 6 Li, 10 B and/or 155,157 Gd, which has a large capture cross section for thermal neutrons.…”

Section: Present Status and Future Trends 41 Present Status And Applmentioning

confidence: 99%