A plastic scintillator gas detector designed for radioxenon isotopes measurement with a high electron detection efficiency

Boron-containing plastic scintillator detectors have a high detection efficiency for low-intensity thermal neutrons and fast neutrons which is currently the preferred types of neutron detector. This article is based on Monte Carlo method, studied boron-containing plastic scintillator for neutron detection performance, and analysis the energy deposition flux characteristics and detection efficiency when low intensity fission neutron incident to the boron plastic scintillator. We obtain the low-flux neutron detector performance in a variety of neutron source energy, boron-containing plastic scintillator diameter and length. Results showed that, when the boron-containing plastic scintillator lengths increase, the energy deposition flux will increase. When the length and diameter is constant, increasing source strength can increase the energy deposition flux brought by the recoil proton to a certain extent. When the source intensity over after thermal neutrons, due to the decrease of the cross section, the energy deposition fluxes brought by the react of neutrons and will decrease. The results provide help for low intensity fission neutron radiation detection technology with high sensitivity.

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High Electron Gain from Forests of Multi-Walled Carbon Nanotubes

MRS Proceedings ◽

10.1557/proc-1258-r10-21 ◽

2010 ◽

Vol 1258 ◽

Author(s):

Mario Michan ◽

Alireza Nojeh

Keyword(s):

Carbon Nanotubes ◽

Mechanical Stability ◽

High Electron ◽

Free Standing ◽

Beam Electron ◽

Field Emitters ◽

Electron Detection ◽

Multi Walled Carbon Nanotubes ◽

Electron Field ◽

Walled Carbon Nanotubes

AbstractCarbon nanotubes are attractive candidates for electron field-emitters due to their high aspect ratio, mechanical stability, and electrical conductivity. It has previously been shown that an electron beam hitting the tip of a carbon nanotube biased near the threshold of field-emission can stimulate the emission of a large number of electrons from the nanotube tip. Here we report on similar experiments on arrays of free-standing multi-walled carbon nanotubes (nanotube forests) interacting with a scanning electron microscope's primary beam. Electron gains of up to 19,000 were obtained. This can enable applications such as electron detection and multiplication, and vacuum transistors.

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Neutron-Gamma Discrimination Using Zero-Crossing Method for BC454 Boron Loaded Plastic Scintillator

18th International Conference on Nuclear Engineering: Volume 3 ◽

10.1115/icone18-29223 ◽

2010 ◽

Author(s):

Dong Wang ◽

Bin He ◽

Quanhu Zhang

Keyword(s):

Gamma Rays ◽

Cross Sections ◽

Plastic Scintillator ◽

Detection Efficiency ◽

Discrimination Performance ◽

Slow Neutron ◽

Fast Neutrons ◽

Zero Crossing ◽

High Detection Efficiency ◽

Slow Neutrons

Boron loaded plastic scintillator could detect both fast neutrons (thanks to hydrogen) and slow neutrons (thanks to 10B). The large cross sections of both reactions lead to high detection efficiency of incident neutrons. However, gamma rays must be rejected first as the scintillator is also sensitive to them. In the present research zero crossing method was used to test neutron-gamma discrimination performance of BC454 boron loaded plastic scintillator. Three contrast experiments were carried out and different thermalization degrees lead to different time spectra in the MCA. Further analysis proved that three Gaussian curves could be used to fit the spectra; they corresponded to gamma rays, fast neutrons and slow neutrons respectively. The slow neutron curve could be clearly separated from the gamma curve. Discrimination performance for fast neutrons became poor, but their peaks could also be separated.

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A compilation of n-p and n-C cross sections and their use in a Monte Carlo program to calculate the neutron detection efficiency in plastic scintillator in the energy range 1–300 MeV

Nuclear Instruments and Methods ◽

10.1016/0029-554x(76)90181-6 ◽

1976 ◽

Vol 135 (2) ◽

pp. 337-352 ◽

Cited By ~ 64

Author(s):

A. Del Guerra

Keyword(s):

Monte Carlo ◽

Energy Range ◽

Cross Sections ◽

Plastic Scintillator ◽

Detection Efficiency ◽

Neutron Detection ◽

Monte Carlo Program ◽

Neutron Detection Efficiency

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Wireless Backpack System for Detection of Radioactive Cesium on Contaminated Soil Using Portable Plastic Scintillator with Efficient Readout Device

Electronics ◽

10.3390/electronics10222833 ◽

2021 ◽

Vol 10 (22) ◽

pp. 2833

Author(s):

Sujung Min ◽

Kwang-Hoon Ko ◽

Bumkyung Seo ◽

JaeHak Cheong ◽

Changhyun Roh ◽

...

Keyword(s):

Contaminated Soil ◽

Plastic Scintillator ◽

Detection Efficiency ◽

Detection System ◽

Radiation Detectors ◽

Radioactive Cesium ◽

Efficiency Performance ◽

Portable System ◽

Gamma Radiations ◽

Wireless System Design

The miniaturization and usability of radiation detectors make it increasingly possible to use mobile instruments to detect and monitor gamma radiations. Here, a Bluetooth-based mobile detection system for integrated interaction in a backpack was designed and implemented to smart equipment for the detection of radioactive cesium on contaminated soil. The radiation measurement system was demonstrated in the form of a backpack using a quantum dot (QD)-loaded plastic scintillator manufactured and prepared directly in this study, and it can be measured by a person in the wireless framework of integrated interaction. The QD-loaded plastic scintillator was measured after setting the distance from the contaminated soil to 20, 50, and 100 mm. As a result, the detection efficiency of the commercial plastic scintillator (EJ-200) was calculated to be 11.81% and that of the QD-loaded plastic scintillator was 15.22%, which proved the higher detection efficiency performance than the commercial plastic scintillator. The measurement result was transmitted to a personal computer using Bluetooth as a portable system. In the future, this wireless system design could be expanded as a wireless communication system equipped with a global positioning system to detect and measure radioactively contaminated environments.

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Characteristics of 3D Printed Plastic Scintillator

EPJ Web of Conferences ◽

10.1051/epjconf/202022501005 ◽

2020 ◽

Vol 225 ◽

pp. 01005

Author(s):

Dong-geon Kim ◽

Sangmin Lee ◽

Junesic Park ◽

Jaebum Son ◽

Yong Hyun Kim ◽

...

Keyword(s):

3D Printing ◽

Energy Resolution ◽

Decay Time ◽

Plastic Scintillator ◽

Detection Efficiency ◽

Single Photon ◽

Radiation Detector ◽

Time Profile ◽

Fast Time ◽

Digital Light Processing

Digital Light Processing (DLP) 3D printing technique can be a powerful tool to fabricate plastic scintillator with a geometrically desired shape in innovatively fast time. Plastic scintillator with the size of 30 mm × 30 mm × 10 mm was fabricated by using the plastic resin and the DLP 3D printer (ASIGA, Pico2HD). The characteristics of decay time, energy resolution, intrinsic detection efficiency were analyzed and compared between the fabricated 3D printing plastic scintillator and a commercial plastic scintillator BC408 (Saint-Gobain Crystal). Decay time profile of the tested plastic scintillators was measured for 137Cs Compton maximum electron 477 keV by using a modified time correlated single photon counting (TCSPC) setup. The time profile was fitted by reconvolution function, and each decay time component and contribution was analyzed. For energy resolution of plastic scintillator, the Gaussian spectrum for 137Cs Compton maximum electron 477 keV was selectively measured by using the γ-γ coincidence experimental setup. As a result, it was confirmed that the 3D printing plastic scintillator showed average decay time 15.6 ns and energy resolution 15.4%. These characteristics demonstrates the feasibility of 3D printing plastic scintillator as a radiation detector.

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