Application research on neutron-gamma discrimination based on BC501A liquid scintillator

Kerntechnik ◽  
2021 ◽  
Vol 86 (6) ◽  
pp. 437-444
Author(s):  
J. Luo ◽  
S. Hou
Keyword(s):  
Fast Neutron ◽  
Figure Of Merit ◽  
Gamma Ray ◽  
Liquid Scintillator ◽  
Comparison Method ◽  
Mean Value ◽  
Neutron Multiplicity ◽  
Nuclear Disarmament ◽  
Zero Crossing ◽  
Non Destructive

Abstract Liquid organic scintillators are widely used in non-destructive analysis, which plays an important role in nuclear disarmament verification. This paper focused on studying the neutron-gamma discrimination technology in the fast neutron multiplicity measuring counter based on BC501A liquid scintillation detector. First, the charge comparison method, the zero-crossing time method and the rise time method were compared via the Geant4 and Matlab algorithm, and the result shows that charge comparison has the highest Figure of Merit. Then, a neutron-gamma discrimination system based on the six-probe fast neutron multiplicity counter was built and tested with a conclusion that the mean value of Figure of merit is 1.08, which verify the satisfactory neutron-gamma discriminating capability of the system. Finally, for the uranium samples, the mass are detected by fast neutron multiplicity counter, and the enrichment are measured by the characteristic gamma-ray signals using the system. The experimental results are in good agreement with the actual data.

Nuclear Material Measurement Based on Fast Neutron Multiplicity Counter

2020 ◽  
Author(s):  
Xianghua Su ◽  
Quanhu Zhang ◽  
Suxia Hou ◽  
Sufen Li ◽  
Jianqing Yang ◽  
...  
Keyword(s):  
Fast Neutron ◽  
Detection Efficiency ◽  
Mass Range ◽  
Nuclear Material ◽  
Neutron Multiplicity ◽  
Analytical Equation ◽  
Analysis Method ◽  
Sample Mass ◽  
Mechanism Of Interaction ◽  
Non Destructive

Abstract Fast neutron multiplicity counting (FNMC) analysis method, as a new non-destructive analysis method for nuclear materials, plays an increasingly important role in the measurement of nuclear material properties. Based on the derivation of the FNMC analytical equation of Pu material, the method of solving the sample parameters was given. By analyzing the mechanism of interaction of neutrons and matter, the model used by Geant4 (version 10.4) software was determined, and a set of three-layer, fast neutron multiplicity counters with six liquid scintillation detectors per layer was constructed. Using the fast neutron multiplicity counter to analyze the measured parameters, the detection efficiency variation was less than 0.4% within the 150g sample mass range, and the PuO2 fluctuation was less than the metal Pu. By studying the detection efficiency and the multiplicity counting rate as a function of sample mass, within the 150g sample mass range, both basically meet the model assumptions of the FNMC analytical equation. The metal Pu and PuO2 samples were set separately, and the FNMC analysis equation was solved. When the sample mass was within 150g, the sample mass solution deviation was less than 10%. The results show that the built-in fast neutron multiplicity counter can better measure Pu sample properties.

scholarly journals Manufacture of a fast neutron detector using EJ-301 liquid scintillator

2019 ◽  
Vol 2 (2) ◽  
pp. 76-81
Author(s):  
Chuan Van Phan ◽  
Hoa Duc Nguyen ◽  
Hai Xuan Nguyen ◽  
Tan Duy Nguyen
Keyword(s):  
Energy Range ◽  
Fast Neutron ◽  
Gamma Rays ◽  
Neutron Detector ◽  
Figure Of Merit ◽  
Liquid Scintillator ◽  
Neutron Detection ◽  
Fast Neutrons ◽  
252Cf Source ◽  
Electron Equivalent

A fast neutron detector using the EJ- 301 scintillator was manufactured for study on detecting fast neutrons and gamma-rays. Detector characteristics include the energy linearity, the efficiency response and the neutron/gamma discrimination were guaranteed for neutron detection in the energy range from 50 to 3000 keVee. The ability discrimination of neutrons/gamma-rays of the detector was evaluated by the charge comparison (CC) method using an 252Cf source. The total efficiencies when measured on 22Na, 137Cs, 60Co and 252Cf sources were obtained 17.8%, 3.9%, 9.8% and 14.8%, respectively. The Figure of Merit (FoM) values of CC method were 0.4–1.55 for the range of energy 50–1000 keVee (keV electron equivalent).

Development of SiO2 based doped with LiF, Cr2O3, CoO4 and B2O3 glasses for gamma and fast neutron shielding

2020 ◽  
Vol 0 (0) ◽  
Author(s):  
Bünyamin Aygün ◽  
Erdem Şakar ◽  
Abdulhalik Karabulut ◽  
Bünyamin Alım ◽  
Mohammed I. Sayyed ◽  
...  
Keyword(s):  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
Fast Neutron ◽  
Cross Sections ◽  
Gamma Ray ◽  
Absorbed Dose ◽  
Neutron Shielding ◽  
Shielding Properties ◽  
Effective Neutron ◽  
Simulation Codes

AbstractIn this study, the fast neutron and gamma-ray absorption capacities of the new glasses have been investigated, which are obtained by doping CoO,CdWO4,Bi2O3, Cr2O3, ZnO, LiF,B2O3 and PbO compounds to SiO2 based glasses. GEANT4 and FLUKA Monte Carlo simulation codes have been used in the planning of the samples. The glasses were produced using a well-known melt-quenching technique. The effective neutron removal cross-sections, mean free paths, half-value layer, and transmission numbers of the fabricated glasses have been calculated through both GEANT4 and FLUKA Monte Carlo simulation codes. Experimental neutron absorbed dose measurements have been carried out. It was found that GS4 glass has the best neutron protection capacity among the produced glasses. In addition to neutron shielding properties, the gamma-ray attenuation capacities, were calculated using newly developed Phy-X/PSD software. The gamma-ray shielding properties of GS1 and GS2 are found to be equivalent to Pb-based glass.

Plutonium measurements with a fast-neutron multiplicity counter for nuclear safeguards applications

2014 ◽  
Vol 763 ◽  
pp. 565-574 ◽  
Author(s):  
Jennifer L. Dolan ◽  
Marek Flaska ◽  
Alexis Poitrasson-Riviere ◽  
Andreas Enqvist ◽  
Paolo Peerani ◽  
...  
Keyword(s):  
Fast Neutron ◽  
Neutron Multiplicity ◽  
Nuclear Safeguards

scholarly journals Timing Characterization of Helium-4 Fast Neutron Detector with EJ-309 Organic Liquid Scintillator

2018 ◽  
Vol 170 ◽  
pp. 07005 ◽  
Author(s):  
Yinong Liang ◽  
Ting Zhu ◽  
Andreas Enqvist
Keyword(s):  
Fast Neutron ◽  
Time Resolution ◽  
High Speed ◽  
Liquid Scintillator ◽  
Moving Average ◽  
Organic Liquid ◽  
Scintillation Detectors ◽  
Arrival Times ◽  
Helium 4 ◽  
Constant Fraction Discriminator

Recently, the Helium-4 gas fast neutron scintillation detectors is being used in time-sensitive measurements, such time-of-flight and multiplicity counting. In this paper, a set of time aligned signals was acquired in a coincidence measurement using the Helium-4 gas detectors and EJ-309 liquid scintillators. The high-speed digitizer system is implanted with a trigger moving average window (MAW) unit combing with its constant fraction discriminator (CFD) feature. It can calculate a “time offset” to the timestamp value to get a higher resolution timestamp (up to 50 ps), which is better than the digitizer's time resolution (4 ns) [1]. The digitized waveforms were saved to the computer hard drive and post processed with digital analysis code to determine the difference of their arrival times. The full-width at half-maximum (FWHM) of the Gaussian fit was used as to examine the resolution. For the cascade decay of Cobalt-60 (1.17 and 1.33 MeV), the first version of the Helium-4 detector with two Hamamatsu R580 photomultipliers (PMT) installed at either end of the cylindrical gas chamber (20 cm in length and 4.4 cm in diameter) has a time resolution which is about 3.139 ns FWHM. With improved knowledge of the timing performance, the Helium-4 scintillation detectors are excellent for neutron energy spectrometry applications requiring high temporal and energy resolutions.

scholarly journals A Comprehensive Study on Gamma Rays and Fast Neutron Sensing Properties of GAGOC and CMO Scintillators for Shielding Radiation Applications

2017 ◽  
Vol 2017 ◽  
pp. 1-9 ◽  
Author(s):  
Shams A. M. Issa ◽  
M. I. Sayyed ◽  
M. H. M. Zaid ◽  
K. A. Matori
Keyword(s):  
Energy Range ◽  
Fast Neutron ◽  
Gamma Ray ◽  
Mean Free Path ◽  
Nuclear Radiation ◽  
Space Technology ◽  
Effective Electron ◽  
Geometrical Progression ◽  
Broad Energy Range ◽  
Removal Cross Section

The WinXCom program has been used to calculate the mass attenuation coefficients (μm), effective atomic numbers (Zeff), effective electron densities (Nel), half-value layer (HVL), and mean free path (MFP) in the energy range 1 keV–100 GeV for Gd3Al2Ga3O12Ce (GAGOC) and CaMoO4 (CMO) scintillator materials. The geometrical progression (G-P) method has been used to compute the exposure buildup factors (EBF) and gamma ray energy absorption (EABF) in the photon energy range 0.015–15 MeV and up to a 40 penetration depth (mfp). In addition, the values of the removal cross section for a fast neutron ∑R have been calculated. The computed data observes that GAGOC showed excellent γ-rays and neutrons sensing a response in the broad energy range. This work could be useful for nuclear radiation sensors, detectors, nuclear medicine applications (medical imaging and mammography), nuclear engineering, and space technology.

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