Detection Efficiency Of Fast Neutrons Research Articles

Response of LaBr2.85Cl0.15:Ce, LaBr[formula omitted]:Ce and NaI:Tl crystals to fast and thermal neutrons

This communication reports the measurement of direct response for fast and thermal neutrons of a newly marketed scintillation crystal LaBr2.85Cl0.15:Ce, along with the widely used LaBr3:Ce and NaI:Tl crystals. It continues our investigation on the possible utility of LaBr2.85Cl0.15:Ce crystal for the detection of high-energy γ-rays and neutrons. This is the first report of the neutron response of the LaBr2.85Cl0.15:Ce crystal. The neutron response was measured for the three detectors using a calibrated Am-Be source, which emits both neutrons and γ-rays. To eliminate the events due to the interaction of the 4.4 MeV γ-ray emitted from Am-Be, the γ-ray response of all three crystals was simulated using the Monte Carlo simulation toolkit GEANT4. Events due to 2.22 MeV γ-ray produced by the capture of thermal neutrons in the paraffin moderator were also eliminated with the aid of simulations. In addition, the response due to fast neutrons was also simulated using GEANT4 and compared with the measured spectrum. This is the first report of the simulation of fast neutron response of LaBr2.85Cl0.15:Ce using GEANT4. The fast neutron detection efficiency of the three detectors has been obtained from the measured spectra.

Front-End Design for SiPM-Based Monolithic Neutron Double Scatter Imagers.

Neutron double scatter imaging exploits the kinematics of neutron elastic scattering to enable emission imaging of neutron sources. Due to the relatively low coincidence detection efficiency of fast neutrons in organic scintillator arrays, imaging efficiency for double scatter cameras can also be low. One method to realize significant gains in neutron coincidence detection efficiency is to develop neutron double scatter detectors which employ monolithic blocks of organic scintillator, instrumented with photosensor arrays on multiple faces to enable 3D position and multi-interaction time pickoff. Silicon photomultipliers (SiPMs) have several advantageous characteristics for this approach, including high photon detection efficiency (PDE), good single photon time resolution (SPTR), high gain that translates to single photon counting capabilities, and ability to be tiled into large arrays with high packing fraction and photosensitive area fill factor. However, they also have a tradeoff in high uncorrelated and correlated noise rates (dark counts from thermionic emissions and optical photon crosstalk generated during avalanche) which may complicate event positioning algorithms. We have evaluated the noise characteristics and SPTR of Hamamatsu S13360-6075 SiPMs with low noise, fast electronic readout for integration into a monolithic neutron scatter camera prototype. The sensors and electronic readout were implemented in a small-scale prototype detector in order to estimate expected noise performance for a monolithic neutron scatter camera and perform proof-of-concept measurements for scintillation photon counting and three-dimensional event positioning.

Gamma-blindness & neutron detection efficiency assessments with centrifugally tensioned metastable fluid detectors in low-scatter environment

A range of tests and associated analyses were performed in a state-of-art low scatter environment to demonstrate and validate the performance of the (Medium) Centrifugally Tensioned Metastable Fluid Detector (MCTMFD) for gamma blind detection of fast and epithermal neutrons for a variety of configurations, using Cf-252 and Am-Li isotope neutron sources. All measurements were performed in the Low Scatter Room (LSR) of Radiological Exposures & Metrology Laboratory at Pacific Northwest National Laboratory (PNNL). Experiments were performed to evaluate intrinsic neutron detection efficiency, ɛint n, the intrinsic gamma-neutron detection efficiency, ɛintγn, and the gamma absolute rejection ratio for neutrons (GARRn) as a function of tensioned metastable state negative pressure, Pneg, varying from 2.5 bar towards 9 bar. The specific embodiment of the MCTMFD utilized for the experiments at PNNL included a 16 cm 3 sensitive volume configured for either fast neutron detection using Decafluoropentane (DFP) as the detection medium, or fast and thermal neutron detection (using DFP with a chemical mixture composed of natural boron). Experiments were performed with Cf-252 neutron sources ranging in intensity from 1 × 104 n/s to 3.45 × 105 n/s, an Am-Li neutron source with intensity of 2.5 × 104 n/s, used in both a bare configuration and in combination with a 30 cm OD moderating sphere of D2O, with and without a 0.5 mm Cd shell, and intense Cs-137 and Co-60 gamma sources offering dose rates ranging from 27 mR/h to 53 R/h. It was found that the MCTMFDs remained gamma-blind (ɛintγn < 10−11) even under 53 R/h gamma background; the associated intrinsic fast neutron detection efficiency (ɛint n) varied from ∼0.2% for Pneg ∼2.5 bar, ∼10% for Pneg ∼5.5 bar and, ∼30% for Pneg ∼9 bar for a Cf-252 fission spectrum. In comparison, for the softer (Am-Li) spectrum, the ɛint n varied from ∼1% for Pneg ∼5.5 bar and approached the ɛint n values for Pneg states above 7 bar. The same MCTMFD when using a borated detection fluid with 20% B-10, offered a ×10–20 improvement in ɛint n for Pneg states ranging from 4.5–5 bar, for detecting epithermal neutrons from the Am-Li source (placed within a 30 cm OD, D2O moderator with and without a 0.5 mm Cd shield).

Counting Efficiency and Neutron/Gamma Ratio for KDP: Tl+ and UPS-923A Scintillators in a Single Photone Detection Mode

This research related to registration of the fast neutrons with a detector based on the inorganic KDP: TL+ mono crystal (KH2PO4 potassium dihydrogen phosphate) and plastic UPS-923A. The crystal of the KDP: TL+ detector grown from a water solution by the method of lowering the temperature. The high concentration of hydrogen nuclei in the KDP: TL+ crystal grid makes it possible to detect neutron radiation with an efficiency comparable to polystyrene scintillators. KDP: TL+ crystals have a high radiation resistance (up to 1010 neutrons/cm2), which significantly expands the spectrum of their application in high-energy physics applications, intense neutron fields. In this work, we used a technique for recording the detector response in the photon counting mode and pulse filtering mode. Since the detector operates on the principle of detecting gamma quanta from the reactions (n, n 'γ), (n, n' γ)res, (n, γ)cap and others, this makes it possible (in a filtering mode) to isolate the mechanisms of cascade generation processes in the volume of the detector caused by secondary gamma quanta from excited states of compound nuclei. The gamma quanta of the elastic scattering reaction (n, n' γ) for the KDP: TL+ scintillator nuclei are the start of the cascade process of the discharge of excited isomeric states of the input, intermediate, and final nuclei. Measurements of the detection efficiency of fast neutrons were carried out with a KDP: TL+ crystal of size 18x18x42 mm in spherical geometry. The obtained detector reviews in units of impulse / particle for sources and 239Pu-Be and 137Cs were 3.57 and 1.44. In this case, a broadband path with a speed of 7 ns was used. In addition, the counting efficiency of the narrow-band tract measured simultaneously with a processing time of 1 μs and 6.4 μs. The received response from the KDP: TL+ detector (in units of impulse/particle) for both sources 239Pu-Be and 137Cs was 0.09 and 0.00029. The n/γ ratio coefficient was 310. The given measurements of a polystyrene-based scintillator size of 40×40×40 mm. The received response in a single photon-counting mode from the plastic detector (in units of impulse/particle) for both sources 239Pu-Be and 137Cs was 19.4 and 3.9. The n/γ ratio coefficients for detectors are also given: KDP: TL+ - 2.47 and UPS-923A - 4.97 in the 7 ns mode. The statistical error in measurements of the neutron detection efficiency was about ~ 5%.

Direct Fast-Neutron Detection with Diamond Homoepitaxial Me–p––p+ Structures

The results of studies on fast-neutron detectors application of homoepitaxial Me–p––p+ structures are reported. Epitaxial boron doped (NA = (4–8) × 1014 cm–3) layers 65 μm thick were grown on highly boron doped HPHT diamond plates by CVD. The Schottky contact on epitaxial layer with 17 mm2 area was fabricated by 30 nm Pt deposition. The Ti(30 nm)/Pt(30 nm)/Au(50 nm) metallization scheme was used as an ohmic contact on the backside of the p+ HPHT diamond plate. The fast-neutron detection efficiency measured on 241Am–Be source at operational bias of 75 V (the depletion region is 10.6 µm) amounted to 6 × 10–5 puls./neutron.

Fast neutron detection efficiency of 6Li and 7Li enriched CLYC scintillators using an Am-Be source

The fast neutrons produced by a calibrated 241Am-Be source were detected by two different Cs2LiYCl6:Ce (CLYC) scintillator detectors. The two cylindrical crystals (1′′× 1′′ in size) were enriched with more than 99% of 7Li (C7LYC) and with about 95% of 6Li (C6LYC), respectively. Both crystals can detect fast neutrons whereas only C6LYC can also detect thermal neutrons, due to the presence of 6Li. The measurement was performed at the L.A.S.A . Laboratory of INFN and University of Milano (Italy). To identify the neutron events, the Pulse-Shape-Discrimination technique was used. The values of 1.41 ± 0.16 for C6LYC and 1.16 ± 0.21 for C7LYC for the detection efficiency of the 241Am-Be emitted neutrons, with energy up to 10 MeV, were deduced.

Advanced Multilayer Composite Heavy-Oxide Scintillator Detectors for High-Efficiency Fast Neutron Detection

We have developed and evaluated a new approach to fast neutron and neutron–gamma detection based on large-area multilayer composite heterogeneous detection media consisting of dispersed granules of small-crystalline scintillators contained in a transparent organic (plastic) matrix. Layers of the composite material are alternated with layers of transparent plastic scintillator material serving as light guides. The resulting detection medium—designated as ZEBRA—serves both as an active neutron converter and a detection scintillator which is designed to detect both neutrons and gamma quanta. The composite layers of the ZEBRA detector consist of small heavy-oxide scintillators in the form of granules of crystalline ZWO, BGO, GSO(Ce), and other materials. We have produced and tested the ZEBRA detector of sizes $100 \mathrm{mm} \times 100 \mathrm{mm} \times 41 \mathrm{mm}$ , and determined that they have very high efficiency of fast neutron detection (up to 49% or greater), comparable to that which can be achieved by large sized heavy-oxide single crystals of about $\varnothing 40 \times 80 \mathrm{cm}^3$ volume. We have also studied the sensitivity variation of fast neutron detection by using different types of multilayer ZEBRA detectors of 100-cm2 surface area and 41-mm thickness (with a detector weight of about 1 kg) and found it to be comparable to the sensitivity of a 3He-detector representing a total cross section of about 2000 cm2 (with a weight of detector, including its plastic moderator, of about 120 kg). The measured count rate in response to a fast neutron source of 252Cf at 2 m for the ZEBRA-GSO(Ce) detector of size $100 \mathrm{mm} \times100 \mathrm{mm} \times41 \mathrm{mm}$ was 2.84 Hz/ng of 252Cf isotope, and this count rate can be doubled by increasing the detector height (and area) up to $200 \mathrm{mm} \times100 \mathrm{mm}$ . In summary, the ZEBRA detectors represent a new type of high efficiency and low-cost large-area solid-state neutron detector that can be used for stationary neutron/gamma portals. They may represent an interesting alternative to expensive, bulky gas counters based on 3He or 10Bneutron detection technologies.

A high-efficiency, low-Ĉerenkov Micro-Layered Fast-Neutron Detector for the TREAT hodoscope

This paper presents an enabling technology for high-efficiency fast-neutron detection for the Transient Reactor Test (TREAT) Facility hodoscope. The hodoscope is currently outfitted with 25.4-mm long Hornyak buttons for fast-neutron detection. However, they require improvements, as they suffer from low detection efficiency, Ĉerenkov radiation contaminating the signal, and non-linearity of detector response at large transients. To address these issues, a layered ZnS:Ag device has been constructed. The layered design provides various advantages: it incorporates greater scintillation volume, Ĉerenkov background is significantly reduced by eliminating the need for additional light guides, and the detection process is simplified by achieving gamma-ray rejection using only pulse-height discrimination. The result is a greater number of fast neutron counts with reduced background noise contaminating the signal. On being irradiated with a 252Cf source (whose neutron energy spectrum closely mimics a reactor fission spectrum), a 25.4-mm long layered device was found to exhibit an intrinsic fast-neutron detection efficiency of 8.1% for neutrons with an average energy of 2 MeV, while a 43-mm long device allows for a greater number of fast neutron to be detected, increasing the efficiency to 9.1%. Further lengthening of the device up to 20 cm has been numerically predicted to exhibit even higher efficiencies. The detectors can be mass-produced easily and inexpensively.

Fast neutron detection at near-core location of a research reactor with a SiC detector

The measurable charged-particle produced from the fast neutron interactions with the Si and C nucleuses can make a wide bandgap silicon carbide (SiC) sensor intrinsically sensitive to neutrons. The 4H-SiC Schottky detectors have been fabricated and tested at up to 500 °C, presenting only a slightly degraded energy resolution. The response spectrum of the SiC detectors were also obtained by exposing the detectors to external neutron beam irradiation and at a near-core location where gamma-ray field is intense. The fast neutron flux of these two locations are ∼4.8×104cm−2⋅s−1 and ∼2.2×107cm−2⋅s−1, respectively. At the external beam location, a Si detector was irradiated side-by-side with SiC detector to disjoin the neutron response from Si atoms. The contribution of gamma ray, neutron scattering, and charged-particles producing reactions in the SiC was discussed. The fast neutron detection efficiencies were determined to be 6.43×10−4 for the external fast neutron beam irradiation and 6.13×10−6 for the near-core fast neutron irradiation.

Advanced Multilayer Composite Heavy-Oxide Scintillator Detectors for High Efficiency Fast Neutron Detection

We have developed and evaluated a new approach to fast neutron and neutron-gamma detection based on large-area multilayer composite heterogeneous detection media consisting of dispersed granules of small-crystalline scintillators contained in a transparent organic (plastic) matrix. Layers of the composite material are alternated with layers of transparent plastic scintillator material serving as light guides. The resulting detection medium – designated as ZEBRA – serves as both an active neutron converter and a detection scintillator which is designed to detect both neutrons and gamma-quanta. The composite layers of the ZEBRA detector consist of small heavy-oxide scintillators in the form of granules of crystalline BGO, GSO, ZWO, PWO and other materials. We have produced and tested the ZEBRA detector of sizes 100x100x41 mm and greater, and determined that they have very high efficiency of fast neutron detection (up to 49% or greater), comparable to that which can be achieved by large sized heavy-oxide single crystals of about Ø40x80 cm3 volume. We have also studied the sensitivity variation to fast neutron detection by using different types of multilayer ZEBRA detectors of 100 cm2 surface area and 41 mm thickness (with a detector weight of about 1 kg) and found it to be comparable to the sensitivity of a 3He-detector representing a total cross-section of about 2000 cm2 (with a weight of detector, including its plastic moderator, of about 120 kg). The measured count rate in response to a fast neutron source of 252Cf at 2 m for the ZEBRA-GSO detector of size 100x100x41 mm3 was 2.84 cps/ng, and this count rate can be doubled by increasing the detector height (and area) up to 200x100 mm2. In summary, the ZEBRA detectors represent a new type of high efficiency and low cost solid-state neutron detector that can be used for stationary neutron/gamma portals. They may represent an interesting alternative to expensive, bulky gas counters based on 3He or 10B neutron detection technologies.

SCINTILLATION MONOCRYSTALS OF KDP:Tl AND KDP:Ce DOPED BY THALLIUM AND CERIUM FOR SELECTIVE DETECTION OF FAST NEUTRONS

This research is going to explain the fast neutrons and gamma radiation registration by the new inorganic single crystals of the KDP (Potassium Dihydrogen Phosphat) group that was grown from the water solutions and activated by the thallium Tl+ or cerium Ce3+. The appearance of the luminescence upon KDP:Tl crystals irradiation with the fast neutrons is explained by secondary ionizing radiation (recoil protons and oxygen recoil nuclei) with excitation of the activator under ionization losses for inhibition. Also the recombination mechanism with the radiation defects of the hydrogen sublattice going to transmit electron excitations to the region of the Tl+ luminescence center. In the KDP:Ce crystals the excitation mechanism of the activator has a similar character, but the luminescence itself is due to the 5d ® 4f transition in Ce3+ ions. The detection efficiency for activated KDP:Tl and KDP:Ce crystals to the fast neutrons in comparisons with organic (plastic) scintillators were calculated theoretically and experimentally. For the crystal volume about 10x10x10 mm3 with the optimal activator concentration the fast neutron detection efficiency under irradiation of 239Pu-Be is 12% for KDP:Tl and 16% for KDP:Ce, which is in a consistent with the theoretical calculation and is not lower according to the parameters of typical organic scintillators. A high natural selectivity of the KDP scintillators to the fast neutrons due to their low sensitivity to gamma radiation was detected. Herewith the internal discrimination of n/γ signals (the ratio of detection efficiencies for the fast neutrons and gamma quants) for activated KDP crystals is 7-8 times higher than of regular plastic scintillators.

Investigation of enhancement in planar fast neutron detector efficiency with stacked structure using Geant4

Geant4 based Monte Carlo study has been carried out to assess the improvement in efficiency of the planar structure of Silicon Carbide (SiC)-based semiconductor fast neutron detector with the stacked structure. A proton recoil detector was simulated, which consists of hydrogenous converter, i.e., high-density polyethylene (HDPE) for generating recoil protons by means of neutron elastic scattering (n, p) reaction and semiconductor material SiC, for generating a detectable electrical signal upon transport of recoil protons through it. SiC is considered in order to overcome the various factors associated with conventional Si-based devices such as operability in a harsh radiation environment, as often encountered in nuclear facilities. Converter layer thickness is optimized by considering 109 neutron events of different monoenergetic neutron sources as well as 241Am-Be neutron spectrum. It is found that the optimized thickness for neutron energy range of 1–10 MeV is ~ 400 μm. However, the efficiency of fast neutron detection is estimated to be only 0.112%, which is considered very low for meaningful and reliable detection of neutrons. To overcome this problem, a stacked juxtaposition of converter layer between SiC layers has been analyzed in order to achieve high efficiency. It is noted that a tenfold efficiency improvement has been obtained—1.04% for 10 layers stacked configuration vis-a-vis 0.112% of single converter layer detector. Further simulation of the stacked detector with respect to variable converter thickness has been performed to achieve the efficiency as high as ~ 3.85% with up to 50 stacks.

Fast neutron detectors and portal monitors based on solid-state heavy-oxide scintillators

We have developed and fabricated large-sized scintillation blocks for detection of fast neutrons based on the heavy-oxide single crystals СWO, ZWO, BGO (diameter 40–50 mm, length 80–100 mm). These crystals demonstrate fast neutron detection efficiencies of not less than 50% without using an external plastic moderator. Based on these new detectors, we have created an experimental prototype of a portal monitor to detect mixed neutron/gamma radiation. The measured sensitivity for fast neutron detection was equal to or better than that of traditional 3Не gas discharge counters, with weight and size being lower by as much as an order of magnitude. It can be expected that this will also result in reduced production and operational costs. The interaction of fast neutrons with the heavy oxide scintillators was studied, and the respective contributions of the mechanisms of inelastic scattering of fast neutrons, resonance scattering of intermediate neutrons, and radiative capture of slow neutrons were determined. We have also developed an improved spectrometric “3-windows” method for separate detection of fast neutrons against the background of gamma-radiation.

Semi-insulating GaAs based detector of fast neutrons produced by D–T nuclear reaction

We have examined semi-insulating (SI) GaAs detectors with high density polyethylene (HDPE) conversion layer by a mono-energetic neutrons with kinetic energy of 16.755 MeV generated by a deuterium—tritium nuclear reaction. First, the influence of HDPE layer thickness on the relative detection efficiency of fast neutrons was studied. The MCNPX (Monte Carlo N-particle eXtended) code has been used to support the analysis of the experiment. The theoretical optimum thickness of the conversion layer was determined to 1.9 mm using the MCNPX code. The HDPE conversion layers of various thicknesses, in the range from 50 μ m to 3200 μ m, were glued on the top Schottky contact of SI GaAs detector in the experiment. The neutron detection efficiency was evaluated from measured spectra and compared to results from simulations. The experimental data showed very good agreement with simulation results. Then the effect of active detector thickness modified by detector reverse bias on neutron detection efficiency was studied. Finally, the effect of the angle of irradiation on neutron detection efficiency was evaluated exhibiting decreasing tendency with increasing deviation from perpendicular direction of impinging neutrons.

Measurement of fast neutron detection efficiency with 6Li and 7Li enriched CLYC scintillators

The CLYC (Cs2LiYC6:Ce) crystal belongs to the elpasolite scintillator family, discovered about 15 years ago. It is a very interesting material because of its good energy resolution and its capability to identify and measure gamma rays and fast/thermal neutrons. In the present work, the fast neutron detection efficiency for two different CLYC cylindrical samples has been measured. These two crystals, both with dimension (thickness x diameter) 1”×1”, were respectively enriched with more than 99% of 7Li (CLYC-7) and with ∼ 95% of 6Li (CLYC-6). The presence of the 6Li isotope makes the CLYC-6 ideal to detect thermal neutrons. In order to compare the two scintillators, only the detection efficiency for fast neutrons was considered, neglecting the energy region associated to thermal neutrons in both the crystals. The measurement was performed at the L.A.S.A. Laboratory of INFN and University of Milano (Italy), using a 241Am-Be source.

Detection of fast neutrons from shielded nuclear materials using a semiconductor alpha detector

The response of a semiconductor alpha detector to fast (>1MeV) neutrons was investigated by using measurements and simulations. A polyethylene converter was placed in front of the detector to register recoil protons generated by elastic collisions between neutrons and hydrogen nuclei of the converter. The developed prototype equipment was tested with shielded radiation sources. The low background of the detector and insensitivity to high-energy gamma rays above 1MeV are advantages when the detection of neutron-emitting nuclear materials is of importance. In the case of a 252Cf neutron spectrum, the intrinsic efficiency of fast neutron detection was determined to be 2.5×10−4, whereas three-fold greater efficiency was obtained for a 241AmBe neutron spectrum.

Stilbene composite scintillators as detectors of fast neutrons emitted by a 252Cf source

The results of the measurements are presented of the relative efficiency ε for 252Cf fast neutron detection by composite detectors based on stilbene crystalline grains. The effects of the grain size and height of the composite detector on its scintillation properties were studied. It is shown that the efficiency of fast neutron detection of stilbene composite scintillators ranges up to 60% of that of bulk single crystals. The results are also presented for relative light output measurements of stilbene composite detectors irradiated by gamma photons of 137Cs, as well as transmittance data of samples in the range of their transparency absorption.

Detection of fast neutrons using detectors based on semi-insulating GaAs

Detectors with AuZn square Schottky contact of the area of 2.5 × 2.5 mm2 were fabricated. On the back side, the whole area AuGeNi eutectic ohmic contact was evaporated. The thickness of the base material (semi-insulating GaAs) was 220 μm. The connection of 4 detectors in parallel was tested to get the detection area of 25 mm2. The 239Pu-Be fast neutron source with energies between 0.5 and 12 MeV was used in experimental measurements. We have investigated the optimal thickness of HDPE (high-density polyethylene) conversion layer for fast neutron detection. The spectra of the neutrons were measured by detectors covered by HDPE converter of different thicknesses. The fast neutron detection efficiency proved experimentally was compared with results from simulations performed by MCNPX (Monte Carlo N-Particle eXtended) code.

Fast neutron detection efficiency of ATLAS-MPX detectors for the evaluation of average neutron energy in mixed radiation fields

Within the framework of the ATLAS-MPX project, the ATLAS-MPX detectors (based on Medipix2 silicon devices) are covered with converting layers of 6LiF and polyethylene (PE) to make them sensitive to thermal and fast neutrons, respectively. Two ATLAS-MPX reference detectors were exposed to two calibrated neutron sources, 252Cf (2.2 MeV mean neutron energy) and 241AmBe (4.08 MeV mean neutron energy), in order to determine their fast neutron detection efficiency. Measurements were performed at low energy threshold (∼8 keV) and high energy threshold (∼230 keV). Fast neutron detection efficiency is primarily achieved via the use of a 1.3 mm thick polyethylene (PE) converter. Recoil protons from the elastic collision between neutron and hydrogen are detected from their tracks in the 300 μm thick silicon pixel detector. Calibrated neutron sources were placed at different distances from the detectors, both separately and simultaneously in order to obtain single and superposed neutron energy spectra. As expected, the neutron detection efficiency in the PE layer increases when the neutron mean energy increases due to the decrease of proton self-absorption in the PE converter itself. The variation of the cluster size as a function of the proton and alpha energy (at low energy threshold) was also studied for better understanding of the neutron response using the PE converter. The determination of the ratio of the fast neutron responses in each detector region at high energy threshold made it possible to establish a relation between the ratios and the mean neutron energy. At low energy threshold, a relation between the neutron energy spectrum and the cluster size distribution of heavy charged particles has been established.

Detection efficiency of ATLAS-MPX detectors with respect to neutrons

Fifteen ATLAS-MPX devices are installed in the ATLAS detector and cavern by the ATLAS-MPX collaboration. This network of sensors provides a real-time measurement of the composition of the radiation field inside the ATLAS detector and its cavern. This article reports calibration measurements of the thermal and fast neutron detection efficiency of the ATLAS-MPX devices. In order to detect neutrons, the 300-μm-thick silicon sensor of each device was covered with mask of 6LiF and polyethylene (PE) converters. Efficiency measurements were performed with calibrated natural thermal neutron source, calibrated 252Cf and 241AmBe sources. Fast neutrons with monochromatic energy of 14 MeV were delivered by a Van de Graaff (VDG) accelerator beam. The devices showed a mean efficiency of 1.02×10 −2 for thermal neutrons ( 6LiF–Si region), 3.17×10 −4 for 252Cf, 7.51×10 −4 for 241AmBe and 1.81×10 −3 for 14 MeV neutrons (PE-Si region) while all background signals generated by X-rays, gamma-rays and electrons were fully suppressed by appropriate discrimination level. These data allow the estimation of the neutron fluxes in ATLAS and provide initial data for precise simulation of the detector environment at the ATLAS-MPX devices locations.