Fast neutron spectra determination by threshold activation detectors using neural networks

Neural network method was used for fast neutron spectra unfolding in spectrometry by threshold activation detectors. The input layer of the neural networks consisted of 11 neurons for the specific activities of neutron-induced nuclear reaction products, while the output layers were fast neutron spectra which had been subdivided into 6, 8, 10, 12, 15 and 20 energy bins. Neural network training was performed by 437 fast neutron spectra and corresponding threshold activation detector readings. The trained neural network have been applied for unfolding 50 spectra, which were not in training sets and the results were compared with real spectra and unfolded spectra by SANDII. The best results belong to 10 energy bin spectra. The neural network was also trained by detector readings with 5% uncertainty and the response of the trained neural network to detector readings with 5%, 10%, 15%, 20%, 25% and 50% uncertainty was compared with real spectra. Neural network algorithm, in comparison with other unfolding methods, is very fast and needless to detector response matrix and any prior information about spectra and also the outputs have low sensitivity to uncertainty in the activity measurements. The results show that the neural network algorithm is useful when a fast response is required with reasonable accuracy.     

快Z箍缩中子源混合堆界面研究进展

评述了快Z箍缩中子产生及诊断的最新进展,介绍了聚变裂变混合堆原理与结构。概述了混合堆界面的磁绝缘传输线(MITL)和碎片防护罩设计,提出了MITL电流压力建模思路,提出了PTS装置上MITL翻转柱孔汇流结构(PHC)及同轴延伸方式,这两种配置方式简便、易行。     

基于时标系统的条纹相机动态畸变

针对神光Ⅲ原型实验中出现的动态畸变现象,开展了条纹相机动态成像特性研究。结合实验图像,利用CST Particle Studio软件模拟了强信号下变像管的成像过程,结果表明:在强信号下,变像管的空间电荷效应会造成电子束聚焦点与理想成像面距离减小,使得图像的放大倍数变小,产生信号弯曲现象,并且这一现象随着电流强度的增加更为明显。     

Prompt fission neutron spectra of U above emissive fission threshold

Statistical model calculations of prompt fission neutron spectra (PFNS) from ²³⁵U(n,F) reaction were performed for incident neutron energies up to E_n20 MeV. Exclusive spectra of the pre-fission (pre-saddle) (n,xnf) reaction neutrons, were calculated with Hauser–Feshbach statistical model, fission and (n,xn) reaction cross section data being described consistently. Spectra of neutrons, evaporated from the fission fragments, were approximated as a sum of two Watt distributions. The reduced neutron velocity in the center-of-mass system due to the neutron emission during fragment acceleration was assumed. PFNS component due to pre-saddle neutrons is evidenced in the shape of the measured PFNS data. We show it to be strongly correlated with the emissive fission contributions to the observed fission cross sections.     

Slow and fast neutron detection using bare CN-85 cellulose nitrate detectors

We report on the application of CN-85 cellulose nitrate track detectors to neutron dosimetry. CN-85 has the ability to register proton tracks and therefore can be used for neutron detection via neutron-induced recoil events within the detector matrix. The CN-85 detectors were used to study the distribution of the weakly moderated spallation neutrons, produced in the irradiation of an extended Pb-target with 1 GeV protons. The results obtained are compared with Monte Carlo simulations using the MCNPX-2.5.c code. The thermal and epithermal neutrons can also be detected by CN-85 detectors without the need for a neutron converter via the ¹⁴N(n, p)¹⁴C reaction, which has a positive Q-value of 626 keV.     

Measurements of effective delayed neutron fraction in a fast neutron reactor using the perturbation method

A perturbation method is proposed to obtain the effective delayed neutron fraction β_(eff) of a cylindrical highly enriched uranium reactor.Based on reactivity measurements with and without a sample at a specified position using the positive period technique,the reactor reactivity perturbation △ρ of the sample in β_(eff) units is measured.Simulations of the perturbation experiments are performed using the MCNP program.The PERT card is used to provide the difference dκ of effective neutron multiplication factors with and without the sample inside the reactor.Based on the relationship between the effective multiplication factor and the reactivity,the equation β~(eff)=dκ/△ρ is derived.In this paper,the reactivity perturbations of 13 metal samples at the designable position of the reactor are measured and calculated.The average β_(eff) value of the reactor is given as 0.00645,and the standard uncertainty is 3.0%.Additionally,the perturbation experiments for β_(eff) can be used to evaluate the reliabilities of the delayed neutron parameters.This work shows that the delayed neutron data of ~(235)U and ~(238)U from G.R.Keepin's publication are more reliable than those from ENDF-B6.0.ENDF-B7.0,JENDL3.3 and CENDL2.2.     

Preliminary investigations of Monte Carlo simulations of neutron energy and let spectra for fast neutron therapy facilities

No fast neutron therapy facility has been built with optimized beam quality based on a thorough understanding of the neutron spectrum and its resulting biological effectiveness. A study has been initiated to provide the information necessary for such an optimization. Monte Carlo studies will be used to simulate neutron energy spectra and LET spectra. These studies will be bench-marked with data taken at existing fast neutron therapy facilities. Results will also be compared with radiobiological studies to further support beam quality optimization. These simulations, anchored by this data, will then be used to determine what parameters might be optimized to take full advantage of the unique LET properties of fast neutron beams.This paper will present preliminary work in generating energy and LET spectra for the Fermilab fast neutron therapy facility.     

Assessment of fast and thermal neutron ambient dose equivalents around the KFUPM neutron source storage area using nuclear track detectors

A set of five ²⁴¹Am–Be neutron sources are utilized in research and teaching at King Fahd University of Petroleum and Minerals (KFUPM). Three of these sources have an activity of 16 Ci each and the other two are of 5 Ci each. A well-shielded storage area was designed for these sources. The aim of the study is to check the effectiveness of shielding of the KFUPM neutron source storage area. Poly allyl diglycol carbonate (PADC) Nuclear track detectors (NTDs) based fast and thermal neutron area passive dosimeters have been utilized side by side for 33 days to assess accumulated low ambient dose equivalents of fast and thermal neutrons at 30 different locations around the source storage area and adjacent rooms. Fast neutron measurements have been carried out using bare NTDs, which register fast neutrons through recoils of protons, in the detector material. NTDs were mounted with lithium tetra borate (Li₂B₄O₇) converters on their surfaces for thermal neutron detection via and nuclear reactions. The calibration factors of NTD both for fast and thermal neutron area passive dosimeters were determined using thermoluminescent dosimeters (TLD) with and without a polyethylene moderator. The calibration factors for fast and thermal neutron area passive dosimeters were found to be 1.33 proton tracks and 31.5 alpha tracks , respectively. The results show variations of accumulated dose with the locations around the storage area. The fast neutron dose equivalents rates varied from as low as up to whereas those for thermal neutron ranged from as low as up to . The study indicates that the area passive neutron dosimeter was able to detect dose rates as low as 7 and from accumulated dose for thermal and fast neutrons, respectively, which were not possible to detect with the available active neutron dosimeters.     

The effect of fast neutron irradiation on the optical modulation spectra of GaAs

The electroreflectance and wavelength-modulated reflectance spectra of GaAs were measured before and after several reactor irradiation periods. High resistivity n type GaAs crystals were irradiated at a temperature between 300 and 310 K up to a fast neutron fluence of 3.3 × 10¹⁷n/cm². The E₀ and E₀+Δ_o peaks shift nonlinearly toward lower energy, the change reaching a maximum value of about ? 50 meV at 10¹⁷n/cm². At this fluence an additional peak appears at 1.33 eV. The E₁ and E₁+Δ₁ peaks move almost linearly toward higher energy with increasing fast neutron fluence, the shift being about + 25 meV at 2 × 10¹⁷n/cm². The results are discussed taking into account infrared absorption measurements and the calculations made by McNichols, Hayes and Ginell concerning the metallic GaAs precipitates. The effect of possible internal stress produced by the fast neutron bombardment on the modulation spectra is also discussed.     

基于FLUKA计算压力容器快中子注量的可行性研究

基于知识产权的考虑,通过与蒙特卡罗程序MCNP计算结果比对,研究使用FLUKA程序替代MCNP程序进行反应堆压力容器快中子注量计算的可行性。通过修改和调用子程序对次级粒子堆栈进行操作,解决了关闭裂变中子这一关键问题,FLUKA程序的计算结果与MCNP程序的计算结果相对偏差在5%以内,符合得较好,证明使用FLUKA程序替代MCNP程序用于计算反应堆压力容器快中子注量在技术上是可行的。     

Beta-delayed neutron spectra for application in reactor technology,nuclear physics and astrophysics

Recent developments in ß-delayed neutron (DN) spectroscopy are reviewed, and the importance of DN energy spectra for various problems in reactor physics, nuclear physics and astrophysics is discussed.     

Efficiency of detection for neutron detectors with different geometries

The response of neutron detectors to the flux of secondary cosmic radiation particles incident on the detectors is simulated mathematically and detection efficiencies are found for neutron detectors of various designs.     

Measuring fluence of fast neutrons with planar silicon detectors

The results of measurements of 1-MeV (Si) equivalent fast neutron fluence with silicon planar detectors are reported. The measurement method is based on the linear dependence of the reverse detector current increment on the neutron fluence: ΔI = α _I × Φ × V. This technique provides an opportunity to measure the equivalent fluence in a wide dynamic range from 108 to 10¹⁶ cm^–2 with an unknown neutron energy spectrum and without detector calibration. The proposed method was used for monitoring in radiation resistance tests of different detector types at channel no. 3 of IBR-2 and for determining the fluence of fission and leakage neutrons at the KVINTA setup.     

Stand for testing scintillation neutron detectors

A stand for studying the characteristics of time-of-flight neutron detectors is described. Plastic scintillation detectors in the form of rectangular prisms with cross sections of 100 × 100 and 100 × 200 mm² and lengths of 300, 400, and 500 mm are viewed through by photomultipliers from the two ends. The detectors are irradiated with a collimated 14-MeV neutron beam produced in the d + t → n+ ⁴He reaction. The collimated beam makes it possible to investigate the spatial resolution of long detectors. The interaction point is determined either from the arrival time of light pulses to the opposite ends of the scintillators or from the ratio of the amplitudes of the signals at the ends of the scintillators. The stand proposed also makes it possible to measure the absolute efficiency of detectors of different length at a neutron energy of 14 MeV.     

Investigating fast neutron interaction with chromium nuclei

A new technique based on a Frisch grided ionization chamber and digital signal processing unit is used for low-background measurements of a cross section of the (n, α) reaction proceeding on a solid target mounted on a cathode. Measurements of the (n, α) reaction cross section for the ⁵⁰Cr and ⁵²Cr isotopes are carry out. It is shown that the data for ⁵⁰Cr differ from the ENDFB-VII evaluation by a factor of 20. The excitation function reveals a structure missing from our assessment. The ⁵²Cr(n, α) reaction cross section is measured for neutrons with energies of less than 14 MeV for the first time.     

Application of solid state track recorders for neutron spectra measurements in a reactor irradiation facility

Abstract

In connection with the IAEA-neutron seed irradiation Programme, a standard neutron irradiation facility has been constructed. The application of solid state track recorders for fast neutron spectra measurements inside this facility is discussed. Fissionable targets of ²³⁵U, ²³⁹Pu, ²³⁷Np, ²³⁸W and ²³²Th will be used, an approximative solution for the incident neutron spectrum will be obtained by a five-group method.     

Investigation of fast neutron interaction with235U

The angular distribution of neutrons emitted by elastic, inelastic and fission processes on²³⁵U were measured at the incident neutron energies of 1.5, 1.9, 2.3, 4.0, 4.5, 5.0 and 5.5 MeV using nanosecond time-of-flight technique. The differential elastic scattering cross sections and their angular distributions at all the seven energies are presented. The total elastic scattering cross sections, angle and energy integrated cross sections for the inelastically scattered neutrons in energy bands of 200 keV, fission cross sections and the angular distributions of fission neutrons were extracted at 1.5, 1.9 and 2.3 MeV incident neutron energies. The energy distributions of the prompt fission neutrons and of the inelastically scattered neutrons are given at the incoming neutron energies of 1.5, 1.9 and 2.3 MeV; and the average fission neutron energies and the inelastic neutron evaporation temperatures were also evaluated at these energies.     

A joint UAB-IReS-IPNO neutron comparison exercise with nuclear track detectors

The response of PN3 and CR-39 personal dosemeters with different configurations, developed by the IReS (Strasbourg), the IPNO (Orsay) and the UAB (Barcelona) groups, is investigated in this study. Both dosemeters were mounted on a water-filled phantom and were simultaneously exposed under different incidence angles (0, 30 and 60) to the following: (i) three ISO neutron sources (²⁴¹Am-Be, bare ²⁵²Cf and moderated ²⁵²Cf with Cd shielding), and (ii) two realistic neutron sources (SIGMA and moderated ²⁵²Cf) at the IRSN (Cadarache) facilities. After irradiation, the plastic detectors were etched and evaluated according to local routine procedures and corrections for the effect of source-to-detector distance were taken into account. A comparison of the average background, the minimum detectable dose equivalent and the field calibration factor is performed as well.