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The crystal Cs2LiYCl6:Ce (CLYC) is a very interesting scintillator material because of its excellent energy resolution and its capability to identify gamma rays and fast/thermal neutrons. In this work, the response to gamma, thermal and fast neutrons of two CLYC 1“x1” crystals was measured: the first one, enriched with 6Li at 95% is ideal for thermal neutron measurements while the second one, enriched...
Proton therapy facilities use high-energy proton beams to destroy cancerous cells. In this approach, secondary radiation is produced due to proton interactions with the patient and surrounding materials. This secondary radiation field, which includes both neutrons and photons, must be accurately characterized in order to determine its effect on patients and medical personnel. The MCNPX-PoliMi code...
The separation of neutron and gamma-ray events in organic-liquid scintillators is of significant importance for nonproliferation applications. Typically pulse shape discrimination (PSD) technique is used to differentiate neutron distribution from gamma-ray distribution. However, one of the challenges remains whether the scintillator's PSD is affected with respect to the particle interaction position...
Radiation hard SiPMs are strongly demanded for the application in the LHC detectors. Examples are the LHCb fiber tracker, the CMS outer calorimeter, and for future application in detectors for ILC, as well as for space detectors. Radiation doses up to a few times 1012neq/cm2 are expected at the positions of the SiPMs at LHC. Dedicated studies on the effects of radiation on SiPMs are required to improve...
Microstructured semiconductor neutron detectors (MSNDs) have long been investigated as a replacement for inefficient thin-film-coated semiconductor neutron detectors. Thin-film-coated semiconductor thermal neutron detection efficiency is restricted to 4–5%. MSNDs improved upon these devices with etched perforations into the diode backfilled with neutron conversion material. Neutron absorption and...
The dual-particle imaging system being developed at the University of Michigan was used at the Joint Research Centre in Ispra, Italy for measurements on samples of special nuclear material. A 1,150-g mixed-oxide (MOX) fuel sample was measured with various shielding configurations to determine how the presence of lead and/or polyethylene shielding degrades the system's ability to localize a source...
A series of experiments and numerical simulations using thermal-neutron time-correlated measurements has been performed to determine the neutron multiplication, M, of assemblies of highly-enriched uranium available at Idaho National Laboratory. The experiments used up to 14.4 kg of highly-enriched uranium, including bare assemblies and assemblies reflected with high-density polyethylene, carbon steel,...
Foam materials saturated with neutron sensitive compounds are of interest as a viable replacement for 3He-based neutron detectors. Previous studies have shown the feasibility of 6LiF-saturated foam detectors as a valid replacement both experimentally and theoretically. However, the random geometry of foam material has previously limited the effective theoretical considerations for such materials to...
Microstructured semiconductor neutron detectors with large aspect-ratio, straight trenches backfilled with neutron sensitive material exhibit superior detection efficiencies over traditional thin-film-coated diodes for solid-state thermal neutron detection. The detectors operate as partial-conformal diffused pin-junction diodes with low leakage current and capacitance. The solid-state silicon substrate...
The aim of this work is to provide the characteristics of MPPC as a part of neutron detector based on scintillators with n/γ discrimination capabilities. Measurements presented in the work cover: characterization of n/γ discrimination properties by means of Figure of Merit (FOM); comparison of scintillation light pulse shape measured with MPPC and PMT (rise time and fall time) and its influence on...
Certain scintillating materials are sensitive to both gamma and neutron radiation and can give information about the type of interacting radiation due to differences in the light output response. By collecting the light pulses and converting them to electrical signals the nature of the radiation can be determined by measuring the amount of electrical charge in the pulse tail - for neutrons, the pulses...
The R3B High-Resolution Neutron Time-of-Flight Spectrometer consists of up to 30 double planes each containing 100 sub modules of plastic scintillators which are read out on the far ends by two PMTs. For these 6000 channels a new compact and modular readout system has been developed. The electronics setup is divided into 16 channel amplifier and fast comparator boards. Digitization units using FPGA...
We have developed a He-3 alternative neutron detector using ceramic scintillator sheets for nuclear safeguards. The alternative detector tube consists of four components: an aluminum regular square envelop tube, a light reflecting tube put on the inner surface of the square tube, a rectangular scintillator sheet sintered on a glass plate, and two PMTs provided at both ends of the tube. It permits...
The reduced availability of 3He is a motivation for developing alternative neutron detectors. 6Li-enriched CLYC (Cs2LiYCl6), a scintillator, is a promising candidate to replace 3He. The neutron and gamma ray signals from CLYC have different shapes due to the slower decay of neutron pulses. Some of the well-known pulse shape discrimination techniques fail to produce the desired results in a mixed radiation...
Epitaxial Silicon Carbide Schottky devices were characterized with the aim of using them for neutron detection at elevated temperatures. Current Voltage (I/V), capacitance Voltage (C/V) and alpha spectroscopy measurements were carried out at temperatures up to 500K. The resistivity dependance on temperature follows an exponential behaviour with an activation energy of 0.15meV. Ideality factor show...
We are developing a new type of manganese bath for determination of neutron emission rate of a radioactive neutron source. The manganese bath gas a multilayered structure composed of polyethylene plates and manganese alloy plates containing 70 % manganese. In measurements of neutron emission rate, a neutron source is set in the center of the manganese bath at first. 56Mn is produced by the 55Mn(n,γ)56Mn...
A quasi-monoenergetic high-energy neutron field produced via 7Li(p,n) reaction consists of a high-energy peak and a continuum down to the low-energy region. The continuum is a background for the measurement for the peak neutrons. Spectral information is necessary to estimate the effect of it. Using a new beam chopping system, the spectral neutron fluence above ∼150 keV was measured by the TOF method...
The ZnS scintillator-based two-dimensional detector was developed for time-of-flight neutron imaging with a high spatial resolution and with a low gamma-ray sensitivity. The developed detector based on neutron counting method exhibited a high spatial resolution of less than 100 µm in full width at half maximum with a moderate count rate capability of several tens kcps. Its low gamma-ray sensitivity...
This work compares the PSD performance of two systems: one digital (NI PXI-5124) and one analog (Mesytec MPD4). Both systems were optimized for the best possible PSD performance, when using the same data acquisition system: PXI-5124, having 12 bit resolution, 10 V pulse-height dynamic range, and a 200 MHz sampling rate. Measurement conditions were kept identical between systems. A 5×5″ Organic-Liquid...
The present work employs MSND technology as a 3He gas-tube direct-replacement technology. The MSND-based Helium Replacement (HeRep) is a single instrument utilizing thirty 4-cm2 active area MSNDs to directly replace 3He-based proportional neutron counters. The HeRep Mk II prototype yielded 102.71±0.84% of the neutron detection efficiency of a 4-atm Reuter Stokes 3He gas-filled detector with the same...
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