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.     

SiO2水玻璃微球辐射增强扩散研究

激光惯性约束聚变使用的玻璃微球经中子辐照后,产生辐射增强扩散效应,Ar在玻璃微球中的扩散性能显著改善,获得了常规加热加压扩散方式无法得到的扩散效果。而带电离子辐照玻璃微球后Ar的扩散性能却没有明显改善。研究了中子和其它带电粒子辐射增强扩散效应的差异。After being radiated by neutron, the glass microspheres, which used in ICF research, have greatly increased the ability of Ar diffusion in it because of the radiation-enhanced diffusion. Such results cannot be achieved by means of thermal diffusion. But after being radiated by charged particles, the ability of Ar diffusion in glass has not increased very much. The differences of the radiation-enhanced diffusion caused by neutron and ions are presented.     

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.     

塑料闪烁体中子探测效率及相对发光产额的标定

利用加速器中子源研究了用于标定塑料闪烁体中子探测效率及相对发光产额的实验技术 ,在四川大学原子核科学技术研究所 2 .5MeV静电加速器上 ,利用T(p,n)和D(d ,n)核反应作为中子源 ,在 0 .6—5MeV中子能区对直径为 40mm ,厚度为 5mm的 1 42 1塑料闪烁体的中子探测效率及相对发光产额进行了测定.A method used for the calibration of neutron efficiency and the relative photo yield of plastic scintillator is studied. T(p,n) and D(d,n) reactions are used as neutron resources. The neutron efficiencies and the relative photo yields of plastic scintillators 1421 (40 mm in diameter and 5 mm in thickness) are determined in the neutron energy range of 0.655—5 MeV.     

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.     

中子物质中超流性的自能色散效应

利用扩展的 Brueckner- Hartree- Fock理论与推广的 BCS方法研究了自能的色散效应和基态关联对中子物质中超流性和能隙的影响 .研究结果表明 ,自能的色散效应使中子物质中能隙减小;考虑基态关联后 ,超流性将进一步减弱. The effects of the dispersion and ground state correlation of the single particle self-energy on neutron matter superfluidity have been investigated in the framework of the Extended Brueckner-Hartree-Fock and the generalized BCS approaches. A sizable reduction of the energy gap is found due to the energy dependence of the self-energy. And the inclusion of the ground state correlations in the self-energy suppresses further the neutron matter superfluidity.     

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.     

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.     

Z-pinch中PF腔中子发射的产生机制

采用束 靶机制和热核机制,利用Maxwell分布,推导了等离子体焦点装置的中子产生机制、热核反应速率、中子平均能量及中子反映速率.Using the machanism of beam target and heat nuclics, the scaling relationship between the neutron yields of denser plasma focus and the PF plasma current is induced.The results of DPF .The principle is brief discussed with denser plasma focus(DPF) as the neutron generator.We have stated that some factors that influnce the DPF discharging to produce neutron yield and some methodsthat improve stability of neutron yields on the denser plasma focus(DPF).     

用中子晕弹核探寻同位旋非对称核物质状态方程

总结和评述了用中子晕弹核探寻同位旋非对称核物质状态方程。 在具有同位旋和动量依赖的同位旋相关量子分子动力学框架内, 采用对比中子晕弹核和相等质量稳定弹核在完全相同入射道条件下物理观测量的差别, 来突出中子晕核明显的同位旋效应和加强物理观测量对于同位旋的灵敏性, 从而提取核物质状态方程。 例如, 与稳定弹核碰撞系统相比, 中子晕弹核明显提高了发射核子的中子\|质子比和增加了它对于对称势的灵敏性, 这两点特征非常有利于提取对称势。 同样, 由于中子晕弹核碰撞系统在低能区（E<60 MeV）由于内部松散结构减弱了核子碰撞力度和动量耗散, 与稳定核碰撞系统相比, 明显提高了原子核阻止; 而在高能区由于两体碰撞同位旋效应的增加, 从而明显提高了原子核阻止。 利用这些特征可以提取核子\|核子碰撞截面的介质效应和同位旋依赖性。 Based on the isospin and momentum dependent quantum molecular dynamics, we use the comparison for the differences between observables in the reactions induced by the halo\|neutron projectile and stable projectile with the same mass under complete same incident channel condition to protrude the isospin effect of halo\|neutron projectile and strengthen the sensitivity of observable on the isospin for extracting the information for the equation of state. For example, the halo\|neutron projectile increases the emitted neutron\|proton ratio and then enhances its sensitivity on the symmetrical potential. Two points above are more favorable than the normal neutron\|rich and neutron\|poor projectiles for extracting the symmetry potential. We also found that the neutron\|halo projectile induces the decrease of nuclear stopping in lower beam energy region and the increase in higher beam energy region, compared to corresponding same mass stable projectile under the same incident channel condition, so that we can use these properties to extract the information for the medium effect and isospin effect of in\|medium nucleon\|nucleon cross section.     

强光一号装置单氘丝中子发射实验研究

 介绍了利用飞行时间技术测量Z箍缩装置单氘丝中子发射。实验发现,Z箍缩中子发射过程中,伴随产生很强的硬X射线,利用铝丝阵产生硬X射线的实验,建立较好的硬X射线屏蔽,大大减弱了它的辐射强度。所采用的双闪烁探测器中子探测系统,进行了3个发次的单氘丝负载实验,确认产生了聚变氘氘中子。4172发次实验测量结果表明,中子产额1.5×10⁹,中子能量为(2.45±0.26) MeV。实验结合分幅照相数据分析认为,峰电流和负载未能很好匹配,等离子体存在不稳定现象。     

STM detection of imprints left on graphite by nuclear reaction products

We present STM imaging of HOPG surfaces which have been in contact with an aluminum foil and have been irradiated with thermal neutrons. We have detected imprints of aluminum nuclei recoil following neutron capture. These include local amorphous structures, piles of few tens of atoms and craters.     

The influence of irradiation temperature (4.2 and 77 K) on the resistivity recovery of pure and Ge alloyed aluminum

An examination of the resistivity increment of pure and Ge alloyed aluminum neutron irradiated at 77 K and 4.6 K followed by an anneal at 77 K was carried out. In the first treatment, the resistivity increment, for pure and germanium alloyed aluminum, was found smaller than that corresponding to the second treatment.     

Shock temperature measurement using neutron resonance spectroscopy

We report a direct measurement of temperature in a shocked metal using Doppler broadening of neutron resonances. The 21.1-eV resonance in 182W was used to measure the temperature in molybdenum shocked to approximately 63 GPa. An explosively launched aluminum flyer produced a planar shock in a molybdenum target that contained a 1-mm thick layer doped with 1.7 at. %(182)W. A single neutron pulse, containing resonant neutrons of less than 1 mus duration, probed the shocked material. Fits to the neutron time-of-flight data were used to determine the temperature of the shocked molybdenum.     

铝基碳化硼材料中子屏蔽性能的蒙特卡罗模拟

采用蒙特卡罗方法, 运用MCNP4C程序研究了碳化硼含量20%–40%、中子能量200 eV–15 keV、材料厚度0.3–2 cm对B₄C/Al复合材料中子屏蔽性能的影响. 结果表明: 碳化硼含量与中子透射系数呈一次线性下降关系; 同含量的碳化硼, B₄C/Al材料的中子屏蔽效果要大大优于聚乙烯碳化硼材料; 在等厚度条件下, 模拟试样B20等的中子屏蔽效果要优于水、铜、混凝土等常规屏蔽材料; 材料厚度与中子透射系数呈指数下降关系, 且单位厚度的增加对中子透射系数改变很大; 含硼量对热中子透射系数影响很大; 在热中子能区, 中子每单位能量的变化对中子透射系数改变较大; 在慢中子能区, 中子每单位能量的变化对中子透射系数改变很小. 关键词： 中子透射系数 蒙特卡罗 铝基复合材料 碳化硼     

激光聚变实验装置屏蔽性能模拟计算

主要采用了蒙特卡罗方法对激光聚变实验装置外表面的中子和光子能谱及剂量进行模拟与分析,引入了MCAM软件绘制激光聚变实验装置的三维模型图,并自动转化为MCNP的输入文件,进行了靶室屏蔽性能的蒙卡模拟,从辐射防护的角度为屏蔽系统的建立、人员的辐射防护以及靶室材料的选择提供理论依据。通过模拟结果得出,CLAM钢作为靶室材料时,其屏蔽中子产生的瞬发光子剂量,在非孔道处是铝合金的1/2左右,40 cm厚的混凝土屏蔽层对中子和光子起到了很好的屏蔽作用,均降低了一个数量级,另外在孔道处的中子和光子剂量,加了混凝土的情况反而比裸靶室时高10% 左右,建议对靶室孔道外部考虑额外的防护。     

激光聚变实验装置屏蔽性能模拟计算北大核心CSCD

主要采用了蒙特卡罗方法对激光聚变实验装置外表面的中子和光子能谱及剂量进行模拟与分析,引入了MCAM软件绘制激光聚变实验装置的三维模型图,并自动转化为MCNP的输入文件,进行了靶室屏蔽性能的蒙卡模拟,从辐射防护的角度为屏蔽系统的建立、人员的辐射防护以及靶室材料的选择提供理论依据。通过模拟结果得出,CLAM钢作为靶室材料时,其屏蔽中子产生的瞬发光子剂量,在非孔道处是铝合金的1/2左右,40cm厚的混凝土屏蔽层对中子和光子起到了很好的屏蔽作用,均降低了一个数量级,另外在孔道处的中子和光子剂量,加了混凝土的情况反而比裸靶室时高10%左右,建议对靶室孔道外部考虑额外的防护。     

Two-dimensional spatially ordered Al2O3 systems: Small-angle neutron scattering investigation

The structure of anodized aluminum oxide films has been investigated by the small-angle neutron scattering method. A theoretical solution is obtained for describing neutron scattering from the Al₂O₃ ordered porous structure. Analysis of the neutron-experiment data shows the possibility of obtaining porous membranes with ideally periodic hexagonal packed pores on a large area (～0.5 cm²).     

Neutron production in collisions between carbon nuclei of energy 2 GeV per nucleon and carbon,aluminum, copper,cadmium, and lead nuclei

Double-differential cross sections for neutron production were measured by the time-of-flight method for the interactions between carbon nuclei of energy 2 GeV per nucleon and carbon, aluminum, copper, cadmium, and lead nuclei. These measurements were performed for angles of 30°, 53°, and 90° in the neutron-energy range fromseveral hundred keVunits to 300MeV. The phenomenologicalmodel of four moving sources was used as a basis in analyzing experimental results and in estimating the contribution to neutron emission from various reaction stages. The temperature parameters determined from the slope of the neutron energy spectra proved to be 22 ± 2 MeV for a hot source (fireball) and 4.5 ± 0.3 MeV for the stage of thermal fragmentation of highly excited heavy nuclear residues. The relative contribution of these two sources to the total neutron yield is independent of the type of the target nucleus and is about 42%, on average.     

Investigation of multiple ultrasmall-angle neutron scattering with the aid of a double-crystal diffractometer

A method of multiple small-angle neutron scattering (MSANS), used to obtain information about inhomogeneities of substances, is considered. Experimental schemes and theory of a double-crystal diffractometer intended for measuring multiple small-angle neutron scattering are described. Methods used to approximate MSANS angular distributions at a low concentration of inhomogeneities and based on Moliére’s theory are reviewed. Their applicability is demonstrated for the examples ofMSANS spectra of samples from ferromagnetic iron-nickel alloys, aluminum powders, and high-T _c superconductor ceramic materials. Theoretical and experimental investigations of interference effects that manifest themselves in multiple small-angle neutron scattering on systems containing high concentrations of scatterers are reported.