Silicon carbide neutron detector testing at the JS']JSI TRIGA reactor for enhanced border and port security

被引:22
|
作者
Radulovic, Vladimir [1 ]
Yamazaki, Yuichi [2 ]
Pastuovic, Zeljko [3 ]
Sarbutt, Adam [3 ]
Ambrozic, Klemen [1 ]
Bernat, Robert [4 ]
Eres, Zoran [4 ]
Coutinho, Jose [5 ,6 ]
Ohshima, Takeshi [2 ]
Capan, Ivana [4 ]
Snoj, Luka [1 ,7 ]
机构
[1] Jozef Stefan Inst, Jamova Cesta 39, SI-1000 Ljubljana, Slovenia
[2] Natl Inst Quantum & Radiol Sci & Technol, 1233 Watanuki, Takasaki, Gunma 3701292, Japan
[3] Australian Nucl Sci & Technol Org, 1 New Illawarra Rd, Lucas Heights, NSW 2234, Australia
[4] Rudjer Boskovic Inst, Bijenicka 54, Zagreb 10000, Croatia
[5] Univ Aveiro, Dept Phys, P-3810193 Aveiro, Portugal
[6] Univ Aveiro, I3N, P-3810193 Aveiro, Portugal
[7] Univ Ljubljana, Fac Math & Phys, Jadranska Cesta 19, Ljubljana 1000, Slovenia
关键词
Silicon carbide; Neutron detection; Neutron converter; !text type='JS']JS[!/text]I TRIGA reactor; FLUX DISTRIBUTION; VALIDATION; SYSTEM;
D O I
10.1016/j.nima.2020.164122
中图分类号
TH7 [仪器、仪表];
学科分类号
0804 ; 080401 ; 081102 ;
摘要
In 2016, the NATO Science for Peace and Security Programme funded research project "Engineering Silicon Carbide for Border and Port Security" - E-SiCure was launched, its objective being the development of radiation-hard silicon carbide (SiC) based detectors of special nuclear materials (SNM), with the aim to enhance border and port security barriers. Detector prototypes based on SiC Schottky Barrier Diodes (SBDs) and neutron converter films were developed. This paper presents the results of a dedicated experimental testing campaign performed at the Jozef Stefan Institute (JSI) TRIGA reactor in which several SiC detector prototypes equipped with B-10 and (LiF)-Li-6 converter films were irradiated in the Dry Chamber of the reactor. The obtained results demonstrate a clearly measurable neutron response, which varies linearly with the neutron flux. The measured particle spectra from the SiC detectors exhibit a clear structure, attributable to the nature and energy of secondary particles originating as reaction products from nuclear reactions involving B-10 and Li-6 isotopes. The determined sensitivity of the detectors, their active volume being 1 mm x 1 mm x 25 mu m, 1 mm x 1 mm x 69 mu m and 1 mm x 1 mm x 170 mu m, was of the order of 2 x 10(-5) counts per second, per unit of neutron flux [counts s(-1) per n cm(-2)s(-1)] (for neutron energies between 0 and 5 eV). Scaling the detection sensitivity by a factor of 10(5), i.e. to an array with a surface of around 20 cm x 2 m, comparable to large BF3 or He-3 detectors, would theoretically enable an overall sensitivity of around 2 counts s(-1) per n cm(-2)s(-1), which is already comparable to typical neutron sensitivity values of gas detectors, in the range from several to over 100 counts s(-1) per n cm(-2)s(-1). Due to its outstanding tolerance to harsh environments (including high temperatures and radiation fields) and superior electronic properties when compared to other semiconductors, SiC is a promising base material for the fabrication of solid-state detectors with stable and long life-time. Improvements in sensitivity combined with the capability of fabricating large modules (SiC arrays), could make SiC an important detection technology, applicable also in the context of border and port security barrier monitoring.
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页数:8
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