Gamma全吸收型BaF2探测装置中子屏蔽体与吸收体的研究

中国原子能科学研究院已经建造完成了我国第一套全吸收型BaF₂探测装置，采用瞬发γ测量法，精确测量中子俘获反应截面。中子源是利用HI-13串列加速器产生的脉冲化质子束，通过7Li(p, n)7Be反应建立。为了有效降低周围环境材料和探测器产生的散射中子本底，约束中子束流的形状，使用MCNP程序模拟设计了屏蔽体，采用含硼聚乙烯(B₄C质量分数为5%)包裹5 cm铅的方案，以及准直器采用平行孔的方案。该设计使样品处的中子束斑平整均匀，直径约为2 cm，束斑外的中子注量降低5个数量级，γ注量降低3个数量级。同时设计了中子吸收体(外半径为10 cm，厚度为7 cm)用于吸收待测样品产生的散射中子。MCNP和GEANT4程序的模拟结果表明:选择含硼聚乙烯(10B₄C质量分数为10%)作为中子吸收体的加工材料，其中子吸收率达到了80%，并设置1 MeV的能量加和阈，能够满足在线测量中子俘获反应截面的实验要求。     

Development of a Spin-Exchange Optical Pumping-Based Polarized ~3He System at the China Spallation Neutron Source(CSNS)

Polarized ~3He neutron spin filters(NSFs) can be used as a vital tool for neutron polarization production and analysis.The China Spallation Neutron Source(CSNS),as one of the major neutron facilities in China,has committed resources to the development of a polarized ~3He NSF program to support its growing polarized neutron research.A spin-exchange optical pumping(SEOP)-based polarized ~3He system and other necessary hardware for NSF transport has been recently developed.The performance of the system is benchmarked using an in-house developed cell named "Trident".Neutron beam measurements yield a ~3 He polarization of 77% with over 200 h of on-beam relaxation time.Combining this newly developed SEOP system with the recently reported cell fabrication station,CSNS is now capable of the fully self-sustained production of ~3He NSFs that shall support its future neutron polarization research.     

快中子照相胶片成像法的初步实验

利用9Be(d,n)反应在北京大学4.5MV静电加速器上产生小于7MeV能区的快中子,采用胶片法进行了快中子照相的初步实验.对快中子胶片成像法的基本性能进行了初步的测试和研究.用国产的原材料研制了一种适用于快中子照相的关键部件－快中子转换屏.实验结果表明研制的快中子转换屏能够满足快中子照相的需要.A preliminary experiment is conducted with direct film method under the condition that fast neutron is generated by the reaction of 9Be (d,n) on the Peking University 4.5 MV Van de Graff, whose energy is lower than 7 MeV.Basic characteristics of direct-film neutron radiography system is researched with the help of samples in different materials, different thickness and holes of different diameter. The fast neutron converter, which is vital for fast neutron imaging, is produced with the materials made in china. The result indicates that fast neutron converter can meet the requirment of fast neutron imaging; what's more, further research of fast neutron imaging can be conducted on the accelerator and neutron-generator in China.     

The neutron texture diffractometer at the China Advanced Research Reactor

The first neutron texture diffractometer in China has been built at the China Advanced Research Reactor,due to strong demand for texture measurement with neutrons from the domestic user community. This neutron texture diffractometer has high neutron intensity, moderate resolution and is mainly applied to study texture in commonly used industrial materials and engineering components. In this paper, the design and characteristics of this instrument are described. The results for calibration with neutrons and quantitative texture analysis of zirconium alloy plate are presented. The comparison of texture measurements with the results obtained in HIPPO at LANSCE and Kowari at ANSTO illustrates the reliability of the texture diffractometer.     

The pilot experimental study of 14 MeV fast neutron digital radiography

14 MeV Fast neutrons has good penetrability and the 14 MeV fast neutron radiography can meet the need of Non-Destructive Test of the structure and lacuna of heavy-massive sample, whose shell is made of heavy metal and in which there are some hydrogen materials, and the study of fast neutron digital radiography just begins in China. By the use of a D-T accelerator, a digital imaging system made up of a fast neutron scintillation screen made of ZnS(Ag) and polypropylene, lens and a scientific grade CCD, the experimental study of fast neutron radiography has been done between 4.3×10¹⁰−6.8×10¹⁰ n/s of neutron yield. Some 14 MeV fast neutron digital radiographs have been gotten. According to experimental radiographs and their data, the performance of the fast neutron scintillation screen and the basic characters of 14 MeV fast neutron radiography are analyzed, and it is helpful for the further research. Supported by the Science and Technology Fund of China Academy of Engineering Physics (Grant No. 251)     

First neutron Bragg-edge imaging experimental results at CSNS

The neutron Bragg-edge imaging is expected to be a new non-destructive energy-resolved neutron imaging technique for quantitatively two-dimensional or three-dimensional visualizing crystallographic information in a bulk material, which could be benefited from pulsed neutron source. Here we build a Bragg-edge imaging system on the General Purpose Powder Diffractometer at the China Spallation Neutron Source. The residual strain mapping of a bent Q235 ferrite steel sample has been achieved with a spectral resolution of 0.15% by the time-of-flight neutron Bragg-edge imaging on this system. The results show its great potential applications in materials science and engineering.     

大型激光原型装置低燃料面密度诊断技术

由于某大型激光原型装置内爆实验的燃料面密度很低,提出了利用充纯D燃料内爆产生的初级DD中子和次级DT中子的产额比值来诊断燃料面密度的方法。在该原型装置的首轮内爆实验中,利用研制的高灵敏塑料闪烁体探测器对初级DD中子产额和次级DT中子产额进行了测量。通过实验发现,当初级DD中子产额高于108时,可以测得次级DT中子实验数据。建立了均匀内爆模型,用初级和次级中子产额比值法对燃料面密度进行计算,获得的该原型装置首轮内爆实验燃料压缩的平均面密度小于4.0 mg/cm2。     

MOC/SN耦合三维中子输运程序KYCORE开发与初步验证

KYCORE程序是中国核动力研究设计院开发的径向MOC（特征线方法）与轴向SN耦合三维中子输运程序。KYCORE将二维MOC与一维SN通过角通量实现高精度耦合,并通过粗网有限差分实现快速收敛,是目前可工程化应用于三维中子输运计算中精度最高的方法之一。介绍了2D/1D计算与加速理论,并通过与蒙特卡罗程序的计算对比,数值验证了KYCORE三维中子计算的准确性与高效性。     

小直径石油测井中子发生器研制

为满足国内油田石油测井的迫切需要, 对小直径测井中子发生器进行了研发。 该发生器离子源采用微型化冷阴极Penning离子源, 离子光学采用结构简单的单极加速系统。 经实验室测试和用户现场刻度及测井表明, 研制的中子发生器具有耐高温、 产额高、 稳定性好等特点, 是目前国内研制的最小直径的工业测井中子发生器。 所测数据与其它测井方法相比较, 地质资料符合性好, 满足了用户测井要求, 现已用于油田生产测井。 A small neutron generator has been developed for meeting the need of well logging in oil fields. The miniature cold cathode Penning ion source and single electrode ion optics system are used in neutron generator. The good performance of the generator has been proved in the laboratory test and well logging in oil field. The generator has good characteristics, such as small diameter, high temperature resistant,high neutron output and good stability. At present, the neutron generator is the smallest logging generator in China, which has been used in oil field generally for conforming the geological data.     

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.     

CSNS反角白光中子源束线控制系统研制

中国散裂中子源(CSNS)反角白光中子源束线主要由中子束窗、中子开关、中子准直器和真空管道等组成。为了保证CSNS反角白光中子源束线安全、稳定、可靠地运行,研制了基于EPICS(Experimental Physics and Industrial Control System)软件架构的控制系统。该系统主要由中子束窗、中子开关及中子准直器的运动控制系统、真空控制系统和控制室三部分组成,实现了对反角白光中子源束线主要设备的远程监测和控制。测试结果表明,该系统具有稳定可靠性高、人机交互友好的特点,很好地满足了反角白光中子源束线运行的需要。     

强中子本底辐射屏蔽体优化设计技术研究

在国内首次采用高强度窄脉冲DPF中子源,采用直照法测量零功率堆瞬发中子时间常数α。由于外中子源本底太强,导致直照中子和散射中子产生的干扰信号比测量信号高三个量级。为有效地抑制外本底,针对不同能量的干扰中子,采用不同材料进行屏蔽。通过数值模拟的方法优化辐射屏蔽体设计,在屏蔽中子的同时也对散射γ 进行了有效屏蔽,使测量信噪比达到了7.5:1,并与实验结果相符合,实验中所采用的新型无机晶体也有效抑制了中子本底。The value of prompt neutron multiplication, α, is measured under the condition of using a denser plasma focus(DPF) neutron-source irradiating zero power assembly for the first time in China. The acquired signal is lower three orders of magnitudes than that of the noise caused by direct and scattered neutrons from the extra-high-intensity neutron-source. Using different kinds of material to decrease the noise caused by neutron with different kinds of energies, an optimized design for radiation shielding is developed by the method of numerical simulation to suppress noise signal. Both neutron and γ-ray are shielded simultaneously. The Signal/Noise Ratio (SNR) with the optimal design was up to 7.5:1 and was consistent with the experimental results. The noise of neutron is decreased effectively by the new kind of unorganic crystals used.     

对加速器驱动洁净核能系统散裂靶问题的探讨

简述了加速器驱动洁净核能靶系统的研究现状和存在的问题，对进一步可开展的工作提出了建议． The present status of the study on the neutron production rate, the neutron energy spectrum and the radiative nuclear production from the target spallation in accelerator driven clean nuclear system is presented. The Monto Carlo simulation and the related physics are also discussed. Their further improvement and the suggestions for the work to be done in China are proposed.     

中国先进研究堆中子科学平台发展现状及展望

依托中国先进研究堆(CARR)高通量中子源，建成了初具规模的中子科学平台，具备中子散射、中子成像和中子活化分析等多种研究技术。其中，中子散射技术包括中子衍射、小角中子散射及中子反射、非弹性中子散射，可以用于分析材料微观结构和动力学性质；热中子成像和冷中子成像可以用于材料内部缺陷等无损检测；中子活化分析系统可以用于物质内核素成分分析。目前已建成和在建中子谱仪共计19台，并初步配备了样品环境装置，为相关应用研究提供了条件基础，可为我国物理、化学、材料科学、生命科学、能源和环境等领域基础研究及工业应用提供重要技术支撑。CARR中子科学平台始终坚持合作共享对外开放的宗旨，将继续为国内外用户提供优质中子技术，服务基础科学前沿和国家重大创新需求研究。     

Physical design of target station and neutron instruments for China Spallation Neutron Source

The China Spallation Neutron Source(CSNS)is the first accelerator-based multidiscipline user facility to produce pulsed neutrons by tungsten target under collision of a pulsed proton beam with a beam power of 100 kW at a repetition rate of 25 Hz.In this paper,we focus on the physical design of CSNS target station and neutron instruments.Under optimized design,the flat tungsten target and the compact target-moderator-reflector coupling enhance effective cold and thermal neutron output from moderators.Three wing-type moderators supply four different characteristics of neutrons to 19 beamlines primarily for neutron scattering applications.Layout of neutron instruments are conceptually planned for total 20 beamlines,the configuration and specification have been determined for three day-one neutron instruments.All designs are optimized for the Phase I of 100 kW with a upgradable capacity to 500 kW.     

Design of the thermal neutron detection system for CJPL-Ⅱ

A low background thermal neutron flux detection system has been designed to measure the ambient thermal neutron flux of the second phase of the China Jinping Underground Laboratory(CJPL-Ⅱ),right after completion of the rock bolting work.A ~3He proportional counter tube combined with an identical ~4He proportional counter tube was employed as the thermal neutron detector,which has been optimised in energy resolution,wall effect and radioactivity of construction materials for low background performance.The readout electronics were specially designed for long-term stable operation and easy maintenance in an underground laboratory under construction.The system was installed in Lab Hall No.3 of CJPL-Ⅱ and accumulated data for about 80 days.The ambient thermal neutron flux was determined under the assumption that the neutron field is fully thermalized,uniform and isotropic at the measurement position.     

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.     

B4C_Al材料中子吸收性能检测设备研制

当前基于燃耗信任制的乏燃料密集贮存方式,对乏燃料水池格架中子吸收材料的可靠性和有效性,都提出了更高的要求。在格架材料生产和使用过程中需要对其中子吸收性能(硼含量)进行无损检测和监测,针对这两个方面的需求,我们研制了核电厂乏燃料水池格架B₄C_Al中子吸收材料检测设备。该检测设备主要由中子源(3枚252Cf放射源)、中子探测器(10个锂玻璃组成的探测阵列)、中子屏蔽准直和慢化系统等组成,通过测量中子透射率来推算待测样板上各个测量点的10B面密度,从而达到对于乏燃料水池贮存格架材料B₄C_Al合金硼含量的无损检测。使用该套设备进行了两种B₄C_Al合金20 cm×30 cm悬挂样片的检测,结果可靠。该B₄C_Al材料中子吸收性能检测设备为国内首创,推动了我国含硼中子吸收材料的无损检测研究,能为核电厂乏燃料水池的临界安全监测提供有力保障。     

国际评价中子核数据库

介绍了当今世界上五大评价中子数据库 ,即美国的 ENDF/B- 6、日本的 JENDL- 3.2、欧洲的 JEF- 2 .2、中国的 CENDL- 2 .1及俄罗斯的 BROND- 2 ,的现况 ,以及国际评价中子数据库的发展趋势和用户如何获得与使用这些数据.The present status of the five major evaluated neutron nuclear data libraries in the world, i.e. ENDF/B 6(America), JENDL 3.2(Japan), JEF 2.2(Europe), CENDL 2.1(China), BROND2(Russia) are introduced. The developing trend of the international neutron evaluated nuclear data library is discussed. How to get and use these data for the domestic users is alro presented.     

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. 