Compensation scheme for online neutron detection using a Gd-covered CdZnTe sensor

Dumazert, Jonathan; Coulon, Romain; Kondrasovs, Vladimir; Boudergui, Karim

doi:10.1016/j.nima.2017.03.018

Cited by 18 publications

(9 citation statements)

References 20 publications

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“…However, their ruggedness and high-speed response make them an interesting option for safeguarding and security applications [114,115]. Semiconductor materials such as 4 H-SiC, diamond and CdZnTe have been investigated in literature for their applications in neutron detection [116,117,118,119]. 4 H-SiC and SiC semiconductors are promoted for their abilities to work in high temperature and high radiation environments along with other desirable properties such as high energy band gap and lower production cost, compared to diamond, which has similar properties [116].…”

Section: Passive Detection Systems Of Illicit Radioactive Materialsmentioning

confidence: 99%

“…Like SiC detectors, diamond detectors have a wide band gap, which makes them highly appealing for radiation detection applications at high temperatures [118,120]. CdZnTe with neutron converting layer such as Gd are proposed for portable thermal neutron detection systems [119,121]. Activation foils were suggested for safeguard applications such as practical neutron flux measurement tools [122].…”

Section: Passive Detection Systems Of Illicit Radioactive Materialsmentioning

confidence: 99%

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Passive Gamma-Ray and Neutron Imaging Systems for National Security and Nuclear Non-Proliferation in Controlled and Uncontrolled Detection Areas: Review of Past and Current Status

Hamrashdi

Monk

Cheneler

2019

Sensors

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Global concern for the illicit transportation and trafficking of nuclear materials and other radioactive sources is on the rise, with efficient and rapid security and non-proliferation technologies in more demand than ever. Many factors contribute to this issue, including the increasing number of terrorist cells, gaps in security networks, politically unstable states across the globe and the black-market trading of radioactive sources to unknown parties. The use of passive gamma-ray and neutron detection and imaging technologies in security-sensitive areas and ports has had more impact than most other techniques in detecting and deterring illicit transportation and trafficking of illegal radioactive materials. This work reviews and critically evaluates these techniques as currently utilised within national security and non-proliferation applications and proposes likely avenues of development.

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Section: Passive Detection Systems Of Illicit Radioactive Materialsmentioning

confidence: 99%

Section: Passive Detection Systems Of Illicit Radioactive Materialsmentioning

confidence: 99%

Passive Gamma-Ray and Neutron Imaging Systems for National Security and Nuclear Non-Proliferation in Controlled and Uncontrolled Detection Areas: Review of Past and Current Status

Hamrashdi

Monk

Cheneler

2019

Sensors

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“…Moreover, accuracy and decision threshold Q γ ffiffiffiffiffiffiffiffiffiffiffiffiffiffiffiffiffiffiffiffi ffi 2σ 2 b ρ * * C, i r associated with the particles of interest are optimized using an adaptive filter, smoothing individual channels while suppressing all negative or non-significant values. The approach described in the present section has been successfully implemented in varied applications, such as α/β contamination meters or gadolinium-based neutron detectors [20,21].…”

Section: Compensation Measurementmentioning

confidence: 99%

Recent Developments in Count Rate Processing Associated with Radiation Monitoring Systems

Coulon¹,

Dumazert²

2018

Ionizing Radiation Effects and Applications

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This chapter presents some recent data processing developments associated with radiation monitoring systems. Radiation monitors have to continuously provide count rate estimations with accuracy and precision. A filtering technique based on a Centered Significance Test coupled with a Brown's double exponential filter has been developed and used in compensation measurement and moving sources detection schemes.

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“…A Gd-covered CdTe diode has been developed and tested using both 113 Cd and 157 Gd isotopes [5]. Additionally, neutron detection has also been tested using a 25-m--thick Gd foil-covered small CdZnTe sensor (about 0.5 cm 3 ) in the low-energy range of 0-200 keV using the compensation mode [6]. To make a portable neutron detector, a 0.5 cm 3 CdZnTe diode has been successively used without converter, with Gd converter and Tb converter foils having thicknesses equal to 5 m.…”

Section: Introductionmentioning

confidence: 99%

Investigation of thermal neutron detection capability of a CdZnTe detector in a mixed gamma-neutron radiation field

et al. 2018

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The aim of this study was to investigate the thermal neutron measurement capability of a CdZnTe detector irradiated in a mixed gamma-neutron radiation field. A CdZnTe detector was irradiated in one of the irradiation tubes of a 241Am-Be source unit to determine the sensitivity factors of the detector in terms of peak count rate (counts per second [cps]) per neutron flux (in square centimeters per second) [cps/neutron·cm−2·s−1]. The CdZnTe detector was covered in a 1-mm-thick cadmium (Cd) cylindrical box to completely absorb incoming thermal neutrons via 113Cd(n,γ) capture reactions. To achieve, this Cd-covered CdZnTe detector was placed in a well-thermalized neutron field (f-ratio = 50.9 ± 1.3) in the irradiation tube of the 241Am-Be neutron source. The gamma-ray spectra were acquired, and the most intense gamma-ray peak at 558 keV (0.74 γ/n) was evaluated to estimate the thermal neutron flux. The epithermal component was also estimated from the bare CdZnTe detector irradiation because the epithermal neutron cutoff energy is about 0.55 eV at the 1-mm-thick Cd filter. A high-density polyethylene moderating cylinder box can also be fitted into the Cd filter box to enhance thermal sensitivity because of moderation of the epithermal neutron component. Neutron detection sensitivity was determined from the measured count rates from the 558 keV photopeak, using the measured neutron fluxes at different irradiation positions. The results indicate that the CdZnTe detector can serve as a neutron detector in mixed gamma-neutron radiation fields, such as reactors, neutron generators, linear accelerators, and isotopic neutron sources. New thermal neutron filters, such as Gd and Tb foils, can be tested instead of the Cd filter due to its serious gamma-shielding effect.

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Compensation scheme for online neutron detection using a Gd-covered CdZnTe sensor

Cited by 18 publications

References 20 publications

Passive Gamma-Ray and Neutron Imaging Systems for National Security and Nuclear Non-Proliferation in Controlled and Uncontrolled Detection Areas: Review of Past and Current Status

Passive Gamma-Ray and Neutron Imaging Systems for National Security and Nuclear Non-Proliferation in Controlled and Uncontrolled Detection Areas: Review of Past and Current Status

Recent Developments in Count Rate Processing Associated with Radiation Monitoring Systems

Investigation of thermal neutron detection capability of a CdZnTe detector in a mixed gamma-neutron radiation field

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