Method for measuring prompt γ-rays generated by D-T neutrons bombarding a depleted uranium spherical shell

The prompt γ-ray spectrum from depleted uranium(DU) spherical shells induced by 14 Me V D-T neutrons is measured. Monte Carlo(MC) simulation gives the largest prompt γ flux with the optimal thickness of the DU spherical shells 3–5 cm and the optimal frequency of neutron pulse 1 MHz. The method of time of flight and pulse shape coincidence with energy(DC-TOF) is proposed, and the subtraction of the background γ-rays discussed in detail. The electron recoil spectrum and time spectrum of the prompt γ-rays are obtained based on a 2 ×2 BC501 A liquid scintillator detector. The energy spectrum and time spectrum of prompt γ-rays are obtained based on an iterative unfolding method that can remove the influence of γ-rays response matrix and pulsed neutron shape.The measured time spectrum and the calculated results are roughly consistent with each other. Experimental promptγ-ray spectrum in the 0.4–3 Me V energy region agrees well with MC simulation based on the ENDF/BVI.5 library,and the discrepancies for the integral quantities of γ-rays of energy 0.4–1 Me V and 1–3 Me V are 9.2% and 1.1%,respectively.     

CeF3闪烁探测器对DD中子的相对灵敏度

 用国内近年新研制的CeF₃闪烁体和常用闪烁体ST401分别配特性相同的光电倍增管，构成两种闪烁体探测器，在强度不随时间变化的DD中子源场中测量了这两种闪烁探测器的相对灵敏度，测量结果表明：CeF₃闪烁探测器对DD中子的灵敏度比同尺寸ST401的灵敏度低一个量级以上。     

A telescope detection system for direct and high resolution spectrometry of intense neutron fields

A high energy- and spatial-resolution telescope detector was designed and constructed for neutron spectrometry of intense neutron fields. The detector is constituted by a plastic scintillator coupled to a monolithic silicon telescope (MST), in turn consisting of a ΔE and an E stage. The scintillator behaves as an “active” recoil-proton converter, since it measures the deposited energy of the recoil-protons generated across. The MST measures the residual energy of recoil-protons downstream of the converter and also discriminates recoil-protons from photons associated to the neutron field. The lay-out of the scintillator/MST system was optimized through an analytical model for selecting the angular range of the scattered protons. The use of unfolding techniques for reconstructing the neutron energy distribution was thus avoided with reasonable uncertainty (about 1.6% in neutron energy) and efficiency (of the order of 10⁻⁶ counts per unit neutron fluence). A semi-empirical procedure was also developed for correcting the non-linearity in light emission from the organic scintillator. The spectrometer was characterized with quasi-monoenergetic and continuous fields of neutrons generated at the CN Van De Graaff accelerator of the INFN-Legnaro National Laboratory, Italy, showing satisfactory agreement with literature data.     

Characteristics of a stilbene scintillation crystal in a neutron spectrometer

Various organic scintillators are commonly used as the detecting material for neutrons, but these detectors are less sensitive to gamma rays. In particular, stilbene crystals and BC501A (NE213, EJ301) have good pulse-shape discrimination (PSD) between neutron and gamma-ray events, and have been selected as the media for fast-neutron detection among the organic, inorganic and plastic materials in a mixed radiation field. Although some of the scintillation characteristics of stilbene crystals have been studied, the detailed scintillation characteristics of the crystal are not completely understood. In this study, the light yield, decay time and pulse shape discrimination capability of a stilbene crystal were measured because this crystal is an optimized detector in a large flux of neutrons such as those might be found in cyclotron and charged particle accelerator facilities. The pulse-shape discrimination of neutrons and gamma rays with a stilbene crystal was measured using a ²⁵²Cf neutron source at room temperature. A neutron tagger module was used for the neutron and gamma separation using the charge comparison method in real time. The total pulse width for the charge integration and the delay from the peak-to tail start time were optimized for a better neutron and gamma separation. The relative light yield and decay time of the stilbene crystal scintillator were also measured.     

Investigation of Fe+3 and Fe+2 properties in calcium aluminoborate glasses

Two types of silicon detectors are reported (ion implantation and surface barrier detector) for the detection of neutrons in high gamma-background. The purpose is to find an optimal design of silicon detector combined with the neutron converter, which is efficient enough to neutron flux and with low sensitivity to %-rays. The experiments show that for fabrication of effective Si detectors for neutrons (using the (n,!) reactions) in the presence of an intensive %-field one must optimise the resistivity of the Si substrate and the active area of the detector, at which the detector has a maximum efficiency to the charged particles and is relatively insensitive to the %-rays.     

Measurement with Bonner spheres spectrometer in pulsed neutron fields

Paper presents results of measurements of neutron spectra with Bonner spheres spectrometer around radiotherapeutic linac producing undesirable photoneutrons and around plasma focus device PF-1000 in which neutrons are generated in ²H + ²H → n + ³He reaction. In the Bonner spheres an active detector, proportional counter filled with ³He, was replaced by passive one to avoid overloading of the active detector during very short period of neutrons generation. For the measurements around linac track detectors with ¹⁰B radiator were used and around plasma focus device pairs of TLDs (⁶LiF and ⁷LiF).     

On possible role of neutrons in appearance of delayed muons in MUON-T setup at the Tien Shan high-altitude station

The MUON-T setup operated at the Tien Shan high-altitude station of the Lebedev Physical Institute (3340 m above sea level) at a soil depth of ∼10 m (∼20 m m.w.e.). Muons with delay times of 30–150 ns with respect to the extensive air shower front were observed at this setup. Calculations showed that delay times of relativistic muons, taking into account their deviations in the geomagnetic field, do not exceed ∼30 ns. To elucidate the possible role of neutrons in the appearance of delayed events due to the n-p reaction in the plastic scintillator material, the problem of neutron transport in a medium with a density of 2 g/cm³ and a humidity of 10% was solved by the Monte Carlo method. Calculations for a point source of neutrons with energies of 5, 10, and 20 MeV (such neutrons can be generated, in particular, in cascades in soil from hadrons of the shower core) showed that the neutron flux decreases more than by a factor of 10⁴ at a distance of 2.8 m of soil from the source. Neither neutron crosses the boundary of 3m at the total statistics of 3 · 10⁵ events. Since the MUON-T setup is at a depth of 10 m, it is clear that neutrons from the atmosphere and soil upper layer are absorbed, scattered, and do not reach the detector. Thus, the formation of delayed muons in the MUON-T setup cannot be explained by these neutrons.     

Experimental study of neutrino oscillations at a fission reactor

The electron-antineutrino spectrum has been measured at a position 8.75 m from the “point-like” core of the ILL ²³⁵U fission reactor, using the reaction $\text{ν}$_e + p → e⁺ + n. Positrons and neutrons were detected in coincidence by means of a low-background liquid scintillator and a ³He detector system. The observed neutron correlated positron spectrum is consistent with theoretical predictions assuming no neutrino oscillations. Upper limits for the oscillation parameter are presented.     

Modeling the efficiency of neutron detection scintillators in the energy range of 5–70 MeV

The instrumental functions for neutron godoscope detectors used in studying the nd-breakup reaction are obtained. The effect on light output of contributions from different processes that occur in a scintillator under the effect of neutrons is examined at different energies of the incident neutrons. The relationship between the detector??s efficiency and neutron energies ranging from 5 to 70 MeV is obtained for different thresholds.     

ST-401薄塑料闪烁体中子能量响应测量技术研究

利用中国原子能科学研究院核工业放射性计量测试中心的5SDH-2串列加速器进行了ST-401薄塑料闪烁体的能量响应实验.选用T(p,n)³He反应和D(d,n)³He反应作为中子源，子源，中子束流采用复合屏蔽体进行准直，源强采用正比计数管和半导体望远镜进行监测，实验测量了厚度从0.16mm到2.00mm的八种规格薄闪烁体的能量响应曲线，对实验的结果的不确定度进行了分析.结果表明探测器的灵敏度随着晶体厚度的增加而增加，对于一定厚度的薄闪烁体，随着中子能量的增加，探测器的能量响应曲线坡度不大. 关键词： 塑料闪烁体 能量响应 正比计数器 半导体反冲质子望远镜     

Nucleation efficiency of R134a as a sensitive liquid for superheated drop emulsion detector

Superheated emulsion detector is known to detect neutrons, γ-rays and other charged particles. The present work includes the study of nucleation efficiency of superheated drops of one of the CFC-free liquids, R134a (C₂H₂F₄), to fast neutrons, its response to γ-rays from ²⁴¹Am and ¹³⁷Cs and compare its nucleation efficiency with that of R12. The observation indicates that because of the presence of hydrogen, the nucleation efficiency is less in R134a than in R12 in the present neutron energy range of consideration. R134a is one of the most environment-friendly, commercially available liquid that is suitable for superheated drop detector, specially in neutron dosimetry and one needs to investigate it in detail.     

Low-background EN-detector for the investigation of the neutron component of EASs

Thermal neutrons are detected using a scintillator compound based on ZnS(Ag) with B₂O₃ added to it. The pulse height generated by single charged particles in a scintillator of small thickness (50 mg/cm²) is not larger than that of a noise signal due to a low sensitivity to single charged particles. As a result, the detector satisfies the requirements of a low-background one in the context of cosmic-ray experiments. The detector is to be used for neutron detection in extensive air showers.     

BC501A中子探测器的能量刻度及其在聚乙烯中子学积分实验中的应用

利用标准放射伽玛源（22Na,137Cs）测量了尺寸为Φ5.08 cm×2.54 cm的BC501A中子探测器的脉冲幅度谱,并利用MCNP软件进行了模拟,详细考虑了探测器的几何尺寸、材料、以及能量分辨函数,计算结果很好地再现了实验数据,精确地确定了康普顿边缘的位置,完成了BC501A中子探测器的能量刻度。并采用14.8 MeV的T（d,n）4He中子源对聚乙烯样品开展了中子学积分实验,结果表明,BC501 A中子探测器的能量刻度过程以及聚乙烯中子学积分实验数据的处理过程是完全合理并且可靠的。The pulse-height spectra of the BC501A scintillator (Φ5.08 cm×2.54 cm) were measured using 22Na, 137Cs γ-ray source, in which MCNP simulation was applied. The simulated pulse-height spectra show a good agreement with the measured data considering the geometry, material and energy resolution function of the scintillator. The position of the Compton edge has been precisely determined and an accurate energy calibration of BC501A scintillator was also achieved. An neutronics integral experiment of polythene with 14.8 MeV T(d, n)4He neutron source was carried out. The results indicate that the procedures of the energy calibration experiment of BC501A scintillator and the data analyzing in the polythene integral experiment are reasonable and reliable.     

An apparatus of the NBC type and the physics results obtained

A nonbubble chamber (NBC) setup, especially designed to perform a series of experiments, is described. The setup consists of a neutron missing-mass spectrometer coupled with a system of large electromagnetic shower detectors. In spite of its large dimensions (the sensitive surface and volume are 2.16 × 10⁴ cm² and 7.8 × 10⁵ cm³, respectively), the neutron spectrometer has a time resolution of ±0.70 nsec FWHM, with ∼25% detection efficiency in the range (70–390 MeV) neutron kinetic energy. The time equalization between the various components of the neutron spectrometer has been established to within ±0.1 nsec. At present this is the most powerful and the most accurate high-energy neutron detector. The electromagnetic shower detector is based on the principle of simultaneous measurements of the spatial development of the electromagnetic cascade and of its energy release. This is obtained with nine elements of lead foil — spark chamber — plastic scintillator, all sandwiched together. The sensitive surface and volume of the electromagnetic shower detector are 1.45 × 10⁴ cm² and 7.2 × 10⁵ cm³, respectively.     

Measurement of fast neutron induced fission cross section of thorium using Lexan plastic track detector

Fission-track registration characteristics of Lexan solid state nuclear track detectors have been used to measure the fast neutron induced fission cross section of²³²Th. The fast neutrons (?14.2MeV) were produced with the help of an AN-400 model Van-de-Graaff accelerator at Banaras Hindu University laboratory using³H(²H,n)⁴He reaction and were used to irradiate the fissile target deposited on the plastic detector. The track densityT, registered on the plastic detector is related to the fission cross sectionσ _f, through the relationT=knσ _føt wheren is the number of fissile atoms per cm² in the deposit, ø is the neutron flux,k is fission track registration efficiency andt is the time of irradiation. The fission cross sectionσ _f of²³²Th, relative to the well measured fission cross section of²³⁸U, was found to be 0.36±0.04 barn.     

Response functions of Cs2LiYCl6: Ce scintillator to neutron and gamma radiation

Research into advanced screening technologies has become high priority in all aspects of occupational nuclear safety and environmental radiation protection. Neutrons are a fundamental part of radiation encountered in various fields of nuclear science and technology and their detection is still employing detectors with a high thermal neutron response embedded in a thermalizing medium where helium based devices have been a dominant choice in many applications. Recently, there have been newly developed sensors based on multi-elements that include ⁶Li and ³⁵Cl isotopes to detect neutrons and gamma radiation. Among these new sensors one can cite the elpasolite scintillator, known as CLYC. This sensor contains two neutron sensitive isotopes and may serve as a dual detector for gamma as well as for neutron radiation. In this paper, the response functions of this sensor have been investigated in different fields of neutron and gamma-radiation. The sensor responses have been simulated using Monte Carlo N-Particle MCNPX code and a series of experiments have been carried out to validate the simulated data. Both sets of data are presented and discussed.     

Neutron response study using poly allyl diglycol carbonate

The results of an experimental work aimed at improving the performance of the CR-39 nuclear track detector for neutron dosimetry applications are reported. A set of CR-39 plastic detectors was exposed to ²⁵²Cf neutron source, which has the emission rate of 0.68 × 10⁸ s⁻¹, and neutron dose equivalent rate 1 m apart from the source is equal to 3.8 mrem/h. The detection of fast neutrons performed with CR-39 detector foils, subsequent chemical etching and evaluation of the etched tracks by an automatic track counting system was studied. It is found that the track density increases with the increase of neutron dose and etching time. The track density in the detector is directly proportional to the neutron fluence producing the recoil tracks, provided the track density is in the countable range. This fact plays an important role in determining the equivalent dose in the field of neutron dosimetry. These results are compared with previous work. It is found that our results are in good agreement with their investigations.      

Measurements of neutron yields and spatial distributions in U/Pb, Pb and Hg thick targets bombarded by 0.5 and 1.0 GeV protons

Measurements have been carried out on neutron yields and spatial distributions in U/Pb, Pb and Hg thick targets and the surrounding paraffin moderators bombarded by 0.533 and 1.0 GeV protons. CR-39 detectors were deployed on the surfaces of targets and moderators to record the neutrons produced in the targets. The measurements show that:

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基于10B4C转换体的多层多丝正比室中子探测器模拟

随着国内高通量中子源及中子散射谱仪的快速发展,对高探测效率、高位置分辨、低伽玛灵敏度的位置灵敏型热中子探测器需求日益迫切。目前国际上中子散射谱仪大多数采用了基于3He的热中子探测器,由于当前3He价格昂贵,寻求3He替代型热中子探测器的相关研究任务紧迫。提出了一种基于10B₄C转换体的多层多丝正比室新型二维位置灵敏型热中子探测器,并利用蒙特卡罗模拟软件Geant4和Garfield++对其探测效率、位置分辨、n/γ抑制比等性能展开了详细的模拟研究。结果表明,当多丝正比室单元为40层,阈值为200 keV时,热中子（E=0.025 eV）探测效率可达到~54%,位置分辨为2.6 mm （FWHM）,n/γ抑制比为~107,可以满足大多数中子散射谱仪的需求,为此类探测器设计及实验研究提供了理论依据。As the development of high flux neutron sources and neutron scattering spectrometers in China, more and more neutron detectors with high detection efficiency, high position resolution, high time resolution and low gamma sensitivity are need ungently. 3He based neutron detector is one of the best options. Recently, because of the 3He gas shortage and its expensive price, we must find a new replacement of 3He. A two-dimensional position sensitive neutron detector based on multi-layer Multi Wires Proportional Chambers (mMWPC) with 10B₄C converter was proposed in this paper. The neutron detection efficiency, position resolution and γ compression were simulated with Geant4 and Garfield++. The results show that with 40 layers of neutron convertor, high themal neutron (E=0.025 eV) detection of~54%, best position resolution of 2.6 mm (FWHM) and high n/γ rejection ratio of~107 with the threshold of 200 keV can be achieved, which can meet the requirements of most spectrometers. This simulation results lay a good foundation for the next step of detector construction and test.     

Neutron detector array at IUAC: Design features and instrumentation developments

The characteristics and performance of the newly commissioned neutron detector array at IUAC are described. The array consists of 100 BC501 liquid scintillators mounted in a semi-spherical geometry and are kept at a distance of 175 cm from the reaction point. Each detector is a 5^″ × 5^″ cylindrical cell coupled to 5^″ diameter photomultiplier tube (PMT). Signal processing is realized using custom-designed home-made integrated electronic modules which perform neutron – gamma discrimination using zero cross timing and time-of-flight (TOF) technique. Compact custom built high voltage power supply developed using DC–DC converters are used to bias the detector. The neutrons are recorded in coincidence with fission fragments which are detected using multi-wire proportional counters mounted inside a 1 m diameter SS target chamber. The detectors and electronics have been tested off-line using radioactive sources and the results are presented.