厚活化箔群截面的加工制作方法

在利用活化法进行中子能谱的测量过程中，需要使用活化探测箔的多群截面。许多时候，由于设备、装置本身所能提供的中子注量率水平非常低，为了在合理的时间内使活化箔活化后的活度达到一定水平，需要采用较厚的活化箔。而目前在原始评价截面数据库来源中，都是ENDF格式的数据库。为此，需要首先将此ENDF格式的数据库转化为无限稀释多群截面，然后根据实验所采用的活化探测箔的厚度，将此无限稀释多群截面转换为解谱所需的相应厚度的活化箔多群截面。     

中子学实验近期进展

文章作者采用核活化法和核裂变法实验研究了加速器D-T中子、D-D中子以及~(252)Cf自发裂变中子在纯水泥体上的反射中子,获得了反射中子引起的6种高阈能活化箔的活化反应率以及~(235)U(包镉)和~(238)U裂变反应率.采用反冲质子法测量了4种厚度(4.5,9,18,27cm)聚乙烯板的角度中子谱.获得了聚乙烯铁铍组合壳体内距装置中心0,9.7,12.8和17.3cm 4个位置1MeV以上的中子能谱.采用铝核素标准截面相对测量法,获得了~(175)Lu、~(89)Y核素的(n,2n)反应截面.文章还分析了实验的不确定度.     

一种测量次级中子能谱的新方法

采用双飞行时间法创建了一台非常规快中子飞行时间谱仪，排除了用D（d,n)^3He中子源测量8－13MeV能区次级中子双微分截面时源中破裂中子群对次级中子能谱测量的干扰，结合常规快中子飞行时间谱仪的测量，实现了用D（d,n)^3He中子源开展8－13MeV中子能区次级中子双微分截面的测量。     

一种测量次级中子能谱的新方法

采用双飞行时间法创建了一台非常规快中子飞行时间谱仪,排除了用D(d,n)3He中子源测量8-13MeV能区次级中子双微分截面时源中破裂中子群对次级中子能谱测量的干扰.结合常规快中子飞行时间谱仪的测量,实现了用D(d,n)3He中子源开展8-13MeV中子能区次级中子双微分截面的测量.     

ITER产氚试验包层模块中子诊断系统的初步设计

1封装薄箔活化片分析系统 此种方法己广泛用于裂变堆的中子强度测量，现己用于几乎所有大型托卡马克的中子产额测量，利用中子辐照某些高纯材料薄箔（样品），被中子活化的样品辐射某种能量的γ射线，经高分辨能力的半导体探测器[如HP—Ge或Si（Li）]测量，得到辐照到样品上的中子的中子数。     

准单能中子单粒子效应研究现状

对国际上用于单粒子效应(SEE)研究的准单能中子源进行了相关调研,对产生准单能中子源的7Li(p, n)7Be核反应、装置布局以及表征中子场性质的中子注量率、中子能谱、中子束流轮廓及其均匀性、热中子本底等参数的理论计算及实验测量进行了系统的介绍。进行准单能中子SEE实验要求中子源有较高的中子注量率水平、较大的束流轮廓、较好的束流均匀性以及较低的热中子本底,并且能测量出精确的中子能谱。对准单能中子SEE实验过程以及三种中子SEE截面的尾部修正方法进行了介绍。     

CFETR水冷陶瓷包层中子学试验模块初步设计与分析

针对中国聚变工程实验堆(CFETR)水冷陶瓷增殖剂包层(WCCB)基本方案,进行了中子学试验模块初步设计与分析。试验模块由3个氚增殖区、2个中子倍增区、3个冷却板以及第一壁、钨保护层、背板组成,并在试验模块中放置碳酸锂探测器进行氚测量。通过MCNP输运程序和IAEA发布的聚变评价核数据库FENDEL-2.1对试验模块中子学性能进行评估,获得了试验模块各区域的中子能谱以及氚产生率(TPR)值;各个区域中子径向通量以及由中子能谱所得到的边缘效应,表明内部区域能谱最能代表原包层的中子能谱;加反射层能提高试验模块的TPR值,综合考虑能谱,TPR以及经济等因素,加钢反射层是较好的选择。     

氘氘中子产额铟活化诊断方法

提出了活化法测量DD中子产额的实验方法,该方法可提高DD中子产额测量的精度。方法基于铟同位素115In与DD中子的非弹性散射反应,活化反应释放的射线被HPGe探测器记录,根据活化系统标定灵敏度推算出中子产额。分析了探测器记录的活化射线数与中子产额间的关系。介绍了一套活化测量的系统设计。通过蒙特卡罗方法模拟了活化样品出射的射线数与样品厚度的关系,模拟结果表明:样品厚度取为1 cm可兼顾活化效率和测量精度。在加速器上对铟活化样品进行了标定实验,实验结果表明:在聚变中子产额大于2109的实验中可使用铟活化诊断方法,中子产额测量的相对标准误差在10%以内。随着聚变中子产额的不断提高,铟活化测量中子产额的精度可进一步提高。     

HCSB DEMO 中子通量谱分析及活化片法测量系统概念设计研究

利用蒙特卡罗粒子输运程序(MCNP)对氦冷固态增殖剂包层聚变示范堆(HCSB DEMO)做了中子通量谱分析。根据中子通量谱特点选出活化片材料,根据跑兔系统和活化片法测中子通量的原理设计出适用于测量HCSB DEMO 增殖包层中子的活化片法测量系统,并对其各组成部分及功能做了说明。计算了活化片在测量系统辐照端辐照时的活化反应率、活化片特征γ 射线发射率及特征γ 计数率,并得到一套合理的测量方案,用于HCSB DEMO 包层中子的测量。     

铟活化诊断氘氘中子产额不确定度分析

介绍了铟活化诊断氘氘中子产额的测量原理,分析了中子产额测量不确定度的来源及评定方法。中子产额测量不确定度主要由灵敏度标定不确定度、活化射线净计数不确定度、立体角测量不确定度及测量系统的随机误差等构成。评估了灵敏度标定过程中加速器中子与聚变中子能量差异、大厅散射中子本底等因素对灵敏度标定的影响,并评估了宇宙射线本底对活化射线净计数测量的影响。分析了中子产额处于不同量级时起主要作用的不确定度分量,提出了减小灵敏度标定不确定度的方法。以实验数据为基础,对具体的实验数据进行了分析计算。结果表明:利用伴随粒子法在加速器中子源上标定出铟活化测量系统灵敏度的相对标准不确定度为4.3%。中子产额低于1010时,产额测量不确定度大于7%,活化射线净计数误差是产额测量误差的主要来源;产额大于1010时,测量不确定度好于7%,中子产额测量不确定度主要由灵敏度标定不确定度引起。     

Neutron fluence spectrometry using disk activation

A simple and robust detector for spectrometry of environmental neutrons has been developed. The technique is based on neutron activation of a series of different metal disks followed by low-level gamma-ray spectrometry of the activated disks and subsequent neutron spectrum unfolding. The technique is similar to foil activation but here the applied neutron fluence rates are much lower than usually in the case of foil activation. The detector has been tested in quasi mono-energetic neutron fields with fluence rates in the order of 1000–10000 cm⁻² s⁻¹, where the obtained spectra showed good agreement with spectra measured using a Bonner sphere spectrometer. The detector has also been tested using an AmBe source and at a neutron fluence rate of about 40 cm⁻² s⁻¹, again, a good agreement with the assumed spectrum was achieved.     

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.     

2.8MeV中子诱发238U裂变的瞬发中子谱高能段实验测量

在中国原子能科学研究院的高压倍加器上利用中子飞行时间方法测量了2.8 MeV中子引起238U裂变的瞬发中子能谱,通过增大样品量和设计合适的屏蔽体提高了效应/本底比,使得测量数据的不确定度满足预期目标（在5.5～14 MeV能区内,能量间隔为0.5 MeV条件下能谱的不确定度小于10%）。将实验几何、中子源能量分布及角分布、探测效率、束流的时间结构等实验条件输入到MCNP程序里,模拟了出射的中子谱,模拟结果与测量结果在不确定度范围内一致,验证了在入射中子能量较低时238>U的裂变瞬发中子谱评价数据的可靠性。The Prompt Fission Neutron Spectrum (PFNS) of 238U induced by 2.8 MeV neutron was measured using the Cockcroft-Walton accelerator in China Institute of Atomic Energy (CIAE). The signal/background ratio was improved by increasing the amount of sample mass and using an appropriate shielding system. The final uncertainty of neutron energy spectrum in 5.5～14 MeV region is less than 10% with a bin size of 0.5 MeV which has reached this project's anticipation. The experimental geometry, the angular distribution and energy distribution of neutron source, the detection efficiency and time structure of deuteron beam were inputted into the MCNP code to simulate the outgoing neutron spectrum. The simulated results agree with the experimental ones within the uncertainty. The result indicates that the evaluated PFNS for 238U at low neutron energy is reliable.     

单能中子源中低能成份对活化截面测量的影响

对用单能中子源作活化截面测量时低能中子干扰的影响作了分析研究,并从测量的两种常用中子源T(d,n)⁴He和D(d,n)³He的中子源能谱中验证了这种定性分析.最后给出了两个比较典型的反应⁵⁸Ni(n,P)⁵⁸Co和⁶⁴Zn(,P)⁶⁴Cu反应的截面测量结果.     

Measuring Neutron Lifetime on an IBR-2 Pulsed Neutron Source

A new method of measuring neutron lifetimes on pulsed neutron sources based on changes in the neutron spectrum during the time of the neutron transit along a rather large path length due to their decay is proposed. The main advantage of this method is the use of relative measurements. Simulating the experiment made it possible to explore the influence of background and neutron losses caused by both the interaction with residual gas and the different level of detector efficiency on the systematic errors. All parameters can be measured experimentally.     

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.     

Neutron,photon and proton energy spectra at high altitude measured using a phoswich-type neutron detector

Neutron energy spectrum from 7 to 180 MeV, photon energy spectrum from 4 to 50 MeV and proton energy spectrum from 94 to 145 MeV were measured simultaneously using a phoswich-type neutron detector with particle discrimination methods at atmospheric depth of 249 g/cm², a vertical cut-off rigidity of 10.2 GV and at a heliocentric potential of 312 MV. We compared our results with other measured and calculated particle energy spectra. Our measured results give a large, sharp neutron peak around 70 MeV, although Bonner balls show a broad peak around 100 MeV due to low energy resolution. The measured photon and proton spectra are between the calculated energy spectra. This onboard study provides the first experimental neutron energy spectrum over 10 MeV with a high-energy resolution.     

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.     

锂玻璃探测器中子探测效率的刻度

为了精确测量keV能区的中子俘获截面,中国原子能科学研究院正在建造一台4π 全吸收型γ 探测装置---GTAF,锂玻璃探测器将会作为中子束流监视器测量中子能谱。利用5SDH-2 加速器刻度了锂玻璃探测器在两个入射中子单能点(250 和565 keV) 的探测效率,并使用EANT4 和MCNP 程序模拟计算了锂玻璃探测器的相对探测效率。通过归一化实验数据和模拟结果,得到了锂玻璃探测器在10keV~1 MeV 能区的中子探测效率曲线。对于把锂玻璃探测器测量得到的飞行时间谱转化为中子束流能谱,是一项非常重要的工作,同时为探测器效率刻度提供了新方法。In order to accurately measure the neutron capture cross section in the energy range of keVMeV, 4 πgamma-ray total absorption facility (GTAF) is being constructed at China Institute of Atomic Energy (CIAE). The lithium glass detector will be used as a neutron beam monitor for GTAF. The detection efficiency of the lithium glass detector at two incident neutron energy points (250, 565 keV) was calibrated in 5SDH-2 accelerator, and the relative detection efficiency was simulated by GEANT4 and MCNP code. By the normalization of the experimental data and simulation result, the neutron detection efficiency curve of the lithium glass detector between 10 keV and 1 MeV was obtained. This work will be important to convert the Time-of-flight spectrum that be measured by Li-glass detector to the energy spectrum of neutron beam, and provide the new method for calibration of detection efficiency.     

Neutron emission from a 100 joule plasma focus

A neutron yield of } 5×10⁵ D-D neutrons/discharge was obtained when 0.1 KJ of energy was pumped into a plasma focus of Mather type. The neutron yield was measured by a high sensitivity silver activation counter. The results are compared with those of other laboratories and it is found that neutron yield scales asE ^1.73 orI ^4.29 in the 0.1–500 KJ region.