用直接中子法测量（n, 2n）反应截面的实验方法研究

在中国原子能科学研究院HI-13 串列加速器上的非常规多探测器快中子飞行时间谱仪上,采用直接中子法测量了14.3 MeV 中子与169Tm作用的(n,2n) 反应截面。用蒙特卡罗方法模拟了次级中子的产生,以对实验数据进行中子注量率衰减、多次散射和有限几何修正,同时结合SUNF 方法得到的评价能谱,给出了(n,2n) 反应截面的实验测量结果。测量截面以中子弹性散射微分截面作为标准截面来归一,并用反冲质子望远镜测量n-p 反应的反冲质子,以监视中子注量率。用直接中子法测量得到的结果与评价数据进行了比较,讨论了采用这种方法测量(n,2n) 反应截面的可行性。(n,2n) reaction cross section from 169Tm at 14.3 MeV was measured with the direct emittedneutron coincidence detecting method, using abnormal fast neutron TOF spectrometer on the HI-13 Tandem Accelerator at CIAE. Monte-Carlo method was used to simulate the generation of secondary neutron and correct the experimental data considering neutron flux attenuation, multiple scattering and finite geometry correction. Combining with evaluated spectra given by SUNF program, the experimental measurement results of the (n,2n) reaction cross sections were given. Cross sections of measurements were normalized by using neutron elastic scattering differential cross section as a standard section, and a recoil proton telescope was used to measure recoiling proton from the n-p reaction to monitor neutron flux rate. After comparing the experimental results with evaluated data, the feasibility of the direct emitted-neutron coincidence detecting method is discussed.     

中子注量率波动修正因子及其应用

在中子核反应研究中,尤其是在利用活化法进行中子核反应截面测量研究时,需要准确测量样品辐照的中子注量。监督反应标准截面法简便可行,在一些核反应截面测量研究中经常用来定量样品辐照的中子注量。在利用监督片核反应剩余核的放射性活度计算平均中子注量率时,中子注量率波动修正因子是一个很重要的参数。对中子注量率波动修正因子进行了详细阐述,通过理论推导给出了中子注量率波动修正因子的定义,从实际应用出发讨论了中子注量率波动修正因子的使用条件和监督反应的选择原则。Incident neutron flux has to be measured accurately in the neutron reaction study especially in the neutron reaction cross-section measurement with activation method. Average neutron flux in the irradiated sample is usually determined by the monitor reaction with reference cross-section values. However, the average incident neutron flux, based on the radioactivity of the residual nuclei produced in the monitor reaction, is dependent upon the neutron flux fluctuation. In the procedure of the average neutron flux calculation, the correction factor for the neutron flux fluctuation plays a key role. In this paper, definition of the neutron flux fluctuation correction factor is inferred heoretically. The selection principles of the monitor reaction and the utilization of the correction factor have been discussed.     

Study of neutron spectra in a water bath from a Pb target irradiated by 250 MeV protons

Spallation neutrons were produced by the irradiation of Pb with 250 MeV protons. The Pb target was surrounded by water which was used to slow down the emitted neutrons. The moderated neutrons in the water bath were measured by using the resonance detectors of Au, Mn and In with a cadmium (Cd) cover. According to the measured activities of the foils, the neutron flux at different resonance energies were deduced and the epithermal neutron spectra were proposed. Corresponding results calculated with the Monte Carlo code MCNPX were compared with the experimental data to check the validity of the code. The comparison showed that the simulation could give a good prediction for the neutron spectra above 50 eV, while the finite thickness of the foils greatly effected the experimental data in low energy. It was also found that the resonance detectors themselves had great impact on the simulated energy spectra.     

用于中子测量的俘获探测器研究

为了在弱中子场和有限小空间内测量绝对裂变率, 制作了俘获探测器, 研究了俘获探测器的性能。 介绍了用于中子测量的俘获探测器和铅屏蔽室, 以及该探测器系统在特定条件下测量裂变反应率的结果, 并与裂变室测量结果进行了比较。 探讨了铅屏蔽室大小对测量结果的影响。 To detect the absolute neutron flux in a weak neutron field and restricted space, the fission fragment trapping detector was fabricated and the properties of the detector were studied. In this paper, the detector and shielding chamber used in neutron detection were described and the experimental measurements of the fission rate in specific condition were performed with the detection system and the result has been compared with that obtained by fission chamber. The influence of the shielding chamber on the measured results was analyzed.     

中子源有源法核查技术研究

用有源 (主动 )方法研究了贫化铀组合系统的中子诱发裂变缓发中子探测技术 .在不同屏蔽和组合等条件下测量和比较了贫化铀系统的缓发裂变中子分布 ,进一步研究了实验系统的可核查性 .探讨了区分核与非核系统的方法. The technique for detecting the delayed neutrons from neutron induced fission in uranium systems was studied by using an active method with 3He proportional counting tube array and a 14 MeV D T neutron source. Under the conditions of different shielding and combination, the distributions of delayed fission neutrons from depleted uranium systems were measured and the reliability of the systems was studied. The method to distinguish a nuclear system from a non nuclear one was discussed.     

8.19 MeV中子与9Be作用的次级中子双微分截面测量

用中国原子能科学研究院HI13串列加速器上的多探测器快中子飞行时间谱仪, 测量了8.19 MeV中子与9Be作用时, 从20°到160°区间26个角度的次级中子双微分截面。测量截面以np散射截面作为标准进行归一。实验结果用Monte Carlo方法进行了中子注量率衰减、多次散射和有限几何修正, 并用MCNP4C程序对所用的Monte Carlo程序进行了验证。测量结果与评价数据以及其它实验室的数据进行了比较。The secondary neutron emission double differential cross section of 9Be induced by 8.19 MeV neutron was measured at 26 different angles from 20°to 150°by using the multi detector fast neutron TOF spectrometer at the HI 13 Tandem Accelerator at China Institute of Atomic Energy(CIAE). The results were normalized to np scattering measurement. A special Monte Carlo code which was validated with the MCNP 4C code was employed to analyze the measured data for the corrections of neutron flux attenuation, multiple scattering and finite geometry. The measured results were compared with the evaluated data and the other measurements.      

高压倍加器靶单元组件对源中子能谱影响研究

靶单元组件对中子有散射和吸收作用,与入射粒子也会发生反应,因此高压倍加器中子场在空间的分布除了由反应本身的角分布决定外,还受到靶单元组件的影响。实验利用飞行时间法测量了高压倍加器T(d,n)4He 中子源产生的实际中子场,测量角度为0°~95°,共8 个角度,采用伴随 粒子法对入射束流进行归一。借助蒙特卡罗方法模拟实验过程和靶单元组件等对中子场分布的影响,将实验结果同模拟计算得到的结果进行了比较与分析,为高压倍加器相关实验布局的合理布置和靶单元组件的优化提供了一定的依据。The spatial distribution of neutron field for the High Voltage Multiple Accelerator (HVMA) is not only determined by the angular distribution of the reaction itself, but also affected by scattering and absorption of the target unit. Meanwhile, undesired nuclear reactions of the incoming ions with the target and self-target build-up may contribute to this neutron background, which disturbs the primary neutron field. The spatial distribution of actual neutron field generated by T(d, n)4He on HVMA was measured using the flight-time method. The neutron emission energy spectra were measured at 8 different angles from 0° to 95°. The results were monitored by the accompanying-particle method. TARGET and MCNP (Monte Carlo simulation process) programs were used to simulate the experiment. The results of simulated calculation were compared with the experimental data. The analyzed results will give some qualitative and quantitative conclusions for target unit optimizing and provide some foundational works for physical measurement in HVMA.     

Study of neutron activation yields in spallation reaction of 400 MeV/u carbon on a thick lead target

The spallation-neutron yield was studied experimentally by bombarding a thick lead target with 400 MeV/u carbon beam. The data were obtained with the activation analysis method using foils of Au, Mn, Al, Fe and In. The yields of produced isotopes were deduced by analyzing the measured γ spectra of the irradiated foils. According to the isotopes yields, the spatial and energy distributions of the neutron field were discussed. The experimental results were compared with Monte Carlo simulations performed by the GEANT4+FLUKA code.     

加速器驱动次临界系统中堆外中子注量率监测方法（英文）

在加速器驱动的次临界（ADS）系统中,次临界反应堆的功率控制是通过控制束流强度来实现。监测堆外中子注量率,不仅提供了反应堆功率指示,也为反应堆保护系统在启动和运行阶段提供了重要的监测信息,因此,堆外中子注量率的监测在ADS系统的控制与保护中起着非常重要的作用。采用3套裂变室和3套非补偿电离室来监测ADS堆外中子注量率。由于裂变室有脉冲、电流和均方电压3种操作模式,1套裂变室可以监测源量程、中间量程和功率量程等宽范围的反应堆功率。所以,使用的监测方法有3个优点,即:增加了监测通道的冗余度,提高了保护系统的可靠性,以及能提供更多的轴向功率分布信息。由于这些中子探测器对中子能谱很敏感,提出了一种有效的校准方法,即先用一个标准的中子源校准这些中子探测器,然后再将中子注量率除以一个修正因素。基于Geant4仿真结果显示,所提取的裂变室和非补偿电离室的修正因素分别为5和42。In an accelerator driven sub-critical (ADS) system, power control in sub-critical reactor is achieved through the control of the beam current. Excore neutron flux monitoring in an ADS system, not only provides indication of reactor power, but also provides important inputs to reactor protection system during startup and power operation, and thus plays a very important role in the control and protection of ADS system. This paper presents the excore neutron flux monitoring method which uses three fission chambers (FCs) and three uncompensated ion chambers (UICs). With three operation modes, pulse mode, current mode, and mean square voltage mode, an FC can monitor reactor power over a wide range from the source range to the intermediate and power ranges. The proposed monitoring method increases the redundancy of independent monitoring channels, improves the reliability of the protection system, and provides more information on axial power distribution. Since these neutron detectors are sensitive to the neutron energy spectrum, we propose an effective calibration method to provide the exact value of neutron flux, i.e., these neutron detectors are calibrated with a standardized neutron source, and then, a correction factor is added in the calibration by comparing the neutron energy spectrum of the neutron source with that in ADS system. Based on Geant4 simulation, the correction factors of 5 and 42 are extracted for FCs and UICs, respectively.     

15N（p,n)15O反应中子源0°角激发函数测量

利用中国原子能科学研究院HI-13串列加速器上的多探测器快中子飞行时间谱仪, 测量了38个不同入射质子能量点下15N（p, n)15O反应0°角方向的激发函数。 测量数据用蒙特卡罗方法进行了模拟, 以进行中子注量衰减和入射窗厚度的不确定度修正。 实验在入射质子能量位于6.029—8.056 MeV之间时发现了3个共振峰, 这一点与DROSG 2000评价数据及PTB数据相符合, 但三家的截面数值存在差异, 对这些差异需要作进一步深入探讨。 The excitation function of 15N（p, n)15O reaction at 0 degree was measured at 38 energy points using the fast neutron Time of Flight (TOF) spectrometer at the HI 13 Tandem Accelerator in the China Institute of Atomic Energy（CIAE）. The measured data were analyzed by Monte Carlo simulation for the corrections of neutron flux attenuation and uncertainty of the thickness of the entrance foil. Three resonance peaks were observed in this experiment in the energy range from 6.029 to 8.056 MeV,which is comparable with the DROSG 2000 evaluated data and the PTB data. However,more experimental studies are needed since the cross sections deviate with each other.     

卵石材料在中子场下的次级放射性分析

由中国科学院近代物理研究所负责设计和建设的加速器驱动嬗变研究装置（CiADS）将建于广东省惠州市。作为一个核装置,CiADS在运行过程中会对环境造成次级放射性影响,因此评估CiADS对环境造成的次级放射性影响水平不仅对公众健康有重要意义,对屏蔽设计也具有一定的指导作用。利用241Am-Be中子源对兰州重离子加速器研究装置（HIRFL）附近的卵石材料进行了辐照实验,测量和分析了辐照后卵石样品内产生的24Na,54Mn,56Mn和27Mg的比活度等相关信息。通过对实验数据与利用蒙特卡罗程序Geant4模拟得到的各放射性核素比活度的比较,验证了Geant4模拟分析中子场下环境介质次级放射性这一方法的可靠性。进而利用Geant4模拟研究了CiADS质子加速器HEBT隧道底部屏蔽层外的中子能谱以及隧道底部屏蔽层外卵石层因中子活化产生的主要放射性核素的饱和比活度。分析结果表明,在合理的屏蔽设计条件下,CiADS运行期间泄露到屏蔽层外的中子活化环境中卵石材料造成的环境影响几乎可以忽略。The China initiative Accelerator Driven System (CiADS) is the first integrated ADS facility designed to study the safety disposal of nuclear waste. As a nuclear facility, it will cause radiological impact on the environment. Therefore, the assessment of radiological impact on the environment around this facility will not only meaningful to the public health, but also offers significant guides to the shielding design of CiADS. Pebble samplings were collected around the campus of the Heavy Ion Research Facility in Lanzhou (HIRFL) and irradiated by a 241Am-Be neutron source. Based on the γ-spectrum measured by a HPGe detector before and after the neutron irradiation, the specific activities of induced radionuclides 24Na,54Mn,56Mn and 27Mg in these samples were analyzed and compared with the Monte-Carlo simulation values obtained with the Geant4 toolkit. The comparison between the experimental and simulated results indicates that Geant4 toolkit is feasible for radiation impact assessment of nuclear facilities, such as CiADS. Then the neutron spectrum outside the concrete shielding of HEBT tunnel of the CiADS have been simulated by the Geant4 toolkit, and the saturation activities of the induced nuclides in the first 10 cm pebble layer have been predicted. The results show that the saturation activities of induced radionuclides in pebbles outside the CiADS shielding are much lower than their exemption values and their radiation impacts to the environment could be ignored.     

Heat Transfer from a dc Laminar Plasma—Jet Flow to Different Solid Surfaces

The beat flux distributions were measured by using transient method for an argon dc laminar plasma-jet flow impinging normally on a plate surface embedded with copper probes.Different powders were coated on the probe surfaces and the effect of powder coating on the heat transfer from jet flow to the probe surface was examined Experimental results show that the maximum values of the heat flux to the probe increase with the coating of fine metal powders,while for the surfaces coated with fine ceramic powders,the maximum values of heat flux decrease,compared with that to the bare copper probe surface.     

间接测量中重放射性核中子俘获截面——替代比率法

s过程中的放射性核素中子俘获截面对天体核合成和核素丰度有重大影响, 在直接测量异常困难的情况下, 替代比率法是获得放射性核素中子俘获截面数据的一种间接新方法。 简单介绍了替代比率法理论, 并简要论述了用替代比率法推导中重核区放射性核素中子俘获截面的可行性。 The radioactive nuclei neutron capture cross section is very important to nuclearsynthesis and nuclide abundance in s process, but it is difficult to be measured directly because of the target production. A new method, surrogate ratio method which is developed from surrogate method, could be used to determine the cross section of radioactive nuclei neutron capture. In this paper, the surrogate ratio method was introduced and the feasibility was discussed to deduce the desired neutron capture cross sections with surrogate ratio method.     

基于D-T紧凑型中子源的快中子照相准直屏蔽体设计及中子束特性模拟研究

中子照相是一种重要的无损检测技术,它能用于火工产品、毒品和核燃料元件等的检测。基于紧凑型D-T中子发生器,完成了一个用于快中子照相的准直屏蔽体系统（BSA）的物理设计。根据D-T中子源的能谱和角分布建立了中子源模型,采用MCNP4C蒙特卡罗程序,模拟了准直屏蔽体系统中中子和γ射线的输运,准直中子束相对于单位源中子的中子注量可以达到9.30×10-6 cm-2,准直中子束中主要是能量大于10 MeV的快中子;在设置的样品平面直径14 cm的照射视野范围,准直束中子注量的不均匀度为4.30%,准直束中中子注量与γ注量的比值为17.20,中子通量和中子注量比值J/Φ为0.992,说明准直中子束有好的平行性;准直屏蔽体外的泄露中子注量率与准直束中子注量率相比降低了2个量级。所设计的准直屏蔽体能满足快中子照相的要求。Neutron radiography is an important nondestructive testing technique. It can be used to detect the explosive devices, drug and the nuclear fuel element, etc. A beam-shaping-assembly (BSA) based on a compact D-T neutron generator is designed for fast neutron radiography in this paper. D-T neutron source model is constructed based on the neutron energy spectrum and angular distribution data. The transportation of neutron and γ-ray in the BSA is simulated using MCNP4C code. The neutron fluence of the collimated neutron beam with respect to the neutron source of the unit source is 9.30×10-6 cm-2. The collimated neutron beams is mainly fast neutrons with energies greater than 10 MeV. In the irradiation field range with a diameter of 14 cm, the neutron fluence uniformity of the collimated beam is 4.3%, the ratio of the neutron fluence to the gamma fluence in the collimated beam is 17.20, and the neutron flux and the neutron fluence ratio (J/Φ) is 0.992 which indicates that the collimated neutron beam has good parallelism. The leakage neutron fluence in outside of BSA is two orders of magnitude lower than that of the collimated neutron beam. The designed BSA can meet the need of fast neutron radiography.     

LS301快中子探测器的效率刻度

主要介绍了利用252Cf标准裂变中子能谱刻度快脉冲LS301型液闪中子探测器的探测效率的实验方法和结果, 简要介绍了实验数据的处理过程, 得到了阈值分别为0.5, 0.7, 1.0和1.6 MeV, 以及中子能量在10 MeV以下的探测器效率, 并对测量结果进行了误差分析。同时为了检验实验结果的准确性, 将实验结果与理论计算结果进行比较, 两者在不确定度范围内符合得很好。Neutron detection efficiency of LS301 fast neutron detector was calibrated by measuring the neutron energy spectrum of 252Cf source, which has a standard fission neutron spectrum. A low mass, fast ionization chamber is used as the fission fragments detector in the time of flight(TOF) spectrometer and afforded the start signal of neutron flight. The stop signal was offered by the anode of LS301. A measured TOF spectrum was turned to the neutron energy spectrum which will be compared with the standard one. Consequently, the fast neutron detection efficiency of LS301 was obtained. Calibration procedures of experimental and data processing was given. Relative detection efficiencies were obtained separately for threshold settings of 0.5, 0.7, 1.0 and 1.6 MeV for neutron energies under 10 MeV. Experimental results accorded with theoretical efficiency curves which were calculated with the Monte Carlo code NEFF50.     

体积填充率变化对球床钨颗粒散裂靶中子学特性影响的研究

应用MCNPX程序,构建质子束轰击球床钨颗粒散裂靶的物理模型,模拟散裂靶泄露中子产额、能谱、通量轴向分布以及散裂靶沉积能分布。针对不同钨颗粒直径和体积填充率,研究了不同钨颗粒直径下体积填充率变化对球床散裂靶中子学特性的影响。模拟结果表明,钨颗粒体积填充率增加,散裂靶的最大沉积能密度减小。在1～20 mm的范围内,钨颗粒的直径越小,散裂靶泄漏中子产额越大,散裂靶泄漏中子产额随钨颗粒体积填充率变化的波动越小,有利于维持CIADS系统反应堆功率稳定。The physical model of the high-energy proton bombarding the tungsten pebble bed spallation target is simulated by the MCNPX program. The effect of the filling rate on the neutronic characteristics with different particle diameters is studied, by calculating the leakage neutron yield, leakage neutron spectrum axial neutron flux distribution and the energy deposition of the target. The result shows that when the diameter increases from 1 to 20 mm,the maximum deposited energy density decreases in the target, but the leakage neutron yield increases. When the filling rate reaches 74%, leakage neutron yields are almost the same value with different particle diameters. When the target is piled up with 1 mm tungsten particles, neutron leakage yield changes smaller with the variation of the filling rate than the other diameter particles which is beneficial to maintain the reactor power stability in ADS.     

一种宽能谱多球中子谱仪的研制

利用蒙特卡罗程序MCNPX模拟计算了纯聚乙烯球和加入辅助材料的聚乙烯球对不同能量中子的响应函数曲线,使用计算出来的响应函数作为U-M-G软件解谱所需输入文件。研发了一套专门为此多球谱仪进行数据采集的放大甄别一体化电路,该电路可为SP9管提供900 V的工作高压,甄别阈设为0.5 V,总的放大倍数为200倍。使用研制的Bonner球谱仪对已知源强的Pu-Be中子源进行能谱测量,测量结果显示解出的能谱数据与实际Pu-Be源中子能谱较为符合,实验结果验证了该套多球谱仪可用于测量Pu-Be能区的中子谱。Neutron response of Bonner spheres which include pure polyethylene and polyethylene with auxiliary material was calculated with Monte Carlo code MCNPx, the calculated response was used as the input le of U-M-G code for neutronspectrum unfolding. A special screening of ampli cation integrated circuits was developed, which can provides high voltage 900 V working for the SP9 tube, the screening threshold is set to 0.5 V and total magni cation is 200. Neutron energy spectrum of a Pu-Be source were measured with the developed Bonner spheres spectrometer,good agreement was found in the measured result of the spectrum datasolutionand the real spectrum, which indicated that the multi-sphere spectrometer was reliable in the neutron measurement at energy region of Pu-Be neutron source.     

氘氚源中子穿过聚乙烯样品泄漏中子谱的测量与模拟

采用飞行时间技术测量了氘氚（D-T）源中子穿过不同厚度板状聚乙烯样品后40°方向的泄漏中子时间到达谱,样品的长和宽均为100 cm, 厚度分别为4.5, 9, 18和27 cm。 本底谱测量采用了无样本底测量和无样堵孔本底测量2种方案, 利用MCNP-4C程序模拟了相同实验条件下的泄漏中子时间到达谱, 模拟过程中考虑了源中子的能谱与角分布、脉冲中子束宽度、 探测器的效率以及样品的有效面积。通过比较发现, 采用无样测量谱作为本底时,计算值/实验值（C/E）值大于1, 并且随着样品厚度的增加而偏离1;而本底谱采用无样堵孔测量谱时, C/E小于1, 并且随着样品厚度的增加而接近1。通过对两套本底谱的分析, 并结合蒙特卡罗模拟, 计算求得了相应样品厚度下比较接近实际的本底谱,采用该模拟计算本底谱后,C/E值有了明显的改善。The neutron leakage spectrum were measured at 40° by time of flight method for polyethylene slabs with the thicknesses of 4.5, 9,18 and 27 cm,respectively. The experimental results were compared with the MCNP-4C simulations, which carefully considered many effects, such as the angle and energy distributions of the source neutrons,the width of the beam pulse,the detection efficiency and the effective measured area. The sample out and collimator filled spectra were measured as the background, and the results showed that C/E values were larger than 1 when using the sample out background spectra,but smaller than 1 when using the collimator filled background spectra. Combine these two different background spectra, a new method was used to calculate the background spectrum,and the results have a better agreement with the simulations.     

Additional acoustic attenuation of coastal turbid water—Measurements compared with predictions using particle size distributions techniques

Based on reverberation method,the viscous absorptions of 0.2-2.0kg/m~3 sediment and glass bead turbid seawater were measured.It is shown that the measurement results were more consistent with the prediction results using particle size distributions techniques instead of using average particle radius techniques.By comparison of the prediction results using particle size distributions techniques with that using average particle radius techniques,it was observed that the discrepancy is 2.3-2.6 dB every 100 meters for 1.0 kg/m~3 of sediment turbid seawater within the scope of experimental frequency.It was suggested that the particle size distributions should be considered in the predictions of viscous absorption in coastal turbid waters.     

Determination of neutron capture cross sections of ~(232)That 14.1 MeV and 14.8 MeV using the neutron activation method

The ~(232)Th(n,γ)~(233)Th neutron capture reaction cross sections were measured at average neutron energies of 14.1 MeV and 14.8 MeV using the activation method.The neutron flux was determined using the monitor reaction~(27)Al(n,α)~(24)Na.The induced gamma-ray activities were measured using a low background gamma ray spectrometer equipped with a high resolution HPGe detector.The experimentally determined cross sections were compared with the data in the literature,and the evaluated data of ENDF/B-Ⅶ.1,JENDL-4.0u+,and CENDL-3.1.The excitation functions of the ~(232)Th(n,γ)~(233)Th reaction were also calculated theoretically using the TALYS1.6 computer code.