Physics Analysis and Optimization Studies for a Fusion Neutron Source Based on a Gas Dynamic Trap

To further investigate the fusion neutron source based on a gas dynamic trap （GDT）, characteristics of the GDT were analyzed and physics analyses were made for a fusion neutron source based on the GDT concept. The prior design of a GDT-based fusion neutron source was optimized based on a refreshed understanding of GDT operation. A two-step progressive development route of a GDT-based fusion neutron source was suggested. Potential applications of GDT are discussed. Preliminary analyses show that a fusion neutron source based on the GDT concept is suitable for plasma-material interaction research, fusion material and subcomponent testing, and capable of driving a proof-of-principle fusion fission hybrid experimental facility.     

Design of Neutron Source Based on HI-13 Tandem Accelerator

<正>Neutron source of keV energy range will be built via ~7Li(p,n)~7Be reaction based on pulsed proton beam of HI-13tandem accelerator at China Institute of Atomic Energy.HI-13tandem accelerator can provide frequency of 6 MHz,pulse width of 2ns,average beam intensity of about 1μA,and the lowest end voltage of 3 MV     

组件燃耗对堆芯裂变中子源参数的影响

在中子输运计算中，准确的裂变中子源是保证计算结果可靠性的前提和基础：随着组件燃耗的加深．^235U等核素不断消耗，^239Pu、^240Pu、^241Pu等核素不断积累，导致每次裂变产生的平均中子数v和裂变释放的平均能量E也随之变化，裂变中子源的归一化因子随燃耗增加而增加。因此，在中子输运计算中，必须考虑组件燃耗对堆芯的裂变中子源参数的影响。     

用于核素在线瞬发伽马数据测量的热中子源设计

基于MCNP程序建立了西安脉冲堆热中子源设计的蒙特卡罗深穿透耦合屏蔽计算方法;采用MCNP临界源模型计算了热柱方腔前表面的中子、伽马平面源的参数,并与实验值进行了对比,给出了平面源的修正系数;基于中子、伽马等效平面源,采用新型硼铝复合材料以及铅、铋等材料,优化设计了热中子束流滤束装置,给出了热中子束流滤束装置的升级改造方案,得到热中子通量密度较原设计方案提高3倍、中子伽马通量密度比值大于10的平行热中子束,且束流外侧区域的中子、伽马本底剂量率接近0.025 mSv/h的辐射防护标准。     

Optimization of Grooved Thermal Moderator for Pulsed Neutron Source,and Its Characteristics

A grooved moderator having grooves on the neutron emanating surface of the moderator has been proposed for the purpose of increasing the neutron intensity of the pulsed neutron source. Experimental studies on polyethylene grooved moderators are performed, and the effects of the groove, the optimum dimensions and the influence of the reflector on the optimum condition are examined with a view to enhancing the emanating thermal neutron intensity. The pulse shapes of emanating neutrons are also measured and the figures of merit of the grooved moderator are discussed.

The experimental results reveal that the optimum condition is determined by the balance of increase of intensity from the grooves and the decrease from the fins. The optimum dimensions for the moderator with a graphite reflector are as follows. The fin width is less than 1 cm, the fin length 8~10 cm and the fin area about 60% of the emanating surface. These values does not depend strongly on whether the moderator is covered by the reflector or not. This size of grooved moderator increases the emanating neutron intensity by about twice at the neutron energy of 25 meV, as compared with the rectangular shaped moderator of 5 cm thick, although it broadens the pulse width considerably. Analysis of the figures of merit suggests that although the grooved moderator is not useful for the usual neutron scattering experiments, it may be of value in experiments having a resolution which is not. very sensitive to the pulse width.     

Some Studies on the Time Resolved Energy Spectrum Reconstruction for Pulsed Neutron Source

The purpose of this article is to present some new numerical results concerning the time resolved energy spectrum reconstruction of a short pulsed neutron source, like one created in plasma focus devices. An MCNP code is used to simulate a time dependent neutron source, plastic scintillator detectors, and their recorded signals. A Monte Carlo program reconstructs spectrum using the signals produced by MCNP code. By the numerical computations we determined the optimum number of four detectors which are needed to be placed at 0, 10, 18 and 30 m from the source, respectively. A time resolution about 12 ns and an energy resolution of 40 keV are obtained. Neutron scattering in the air is considered, and it is found that the intensity of spectrum is increased by 6%.     

Energy Confinement Scaling Predictions for the Stabilized Tandem Mirror

The absence of toroidal curvature and the relatively weak internal parallel currents in a tandem mirror gives the system favorable stability and transport properties. GAMMA-10 experiments demonstrate that sheared plasma rotation suppresses turbulent radial losses through control of the radial potential profiles. Recent achievements of the GAMMA-10 include 3 keV ion confinement potentials and T _e ≥ 800 eV. Total energy confinement times for the GAMMA-10 experiment exceed by an order of magnitude the corresponding empirical confinement times in toroidal devices. At the temperatures achieved in the GAMMA-10, the end loss rate τ_p ≃ 100 ms so that radial losses determine τ_E, as intended in tandem mirror reactor designs. Drift-wave results on radial confinement times developed using Bohm, gyro-Bohm, and electron temperature gradient (ETG) scalings imply that the tandem mirror has a qualitatively different form of drift-wave radial transport from that in toroidal devices. Drift-wave eigenmodes for the GAMMA-10 are analyzed for the fluctuating electrostatic potential and magnetic perturbations.     

基于白光中子源的169Tm辐射俘获截面测量和共振参数分析

中子辐射俘获截面及共振参数在核工程设计、核天体物理等研究领域中有重要的应用价值。在中国散裂中子源（CSNS）反角白光中子束线（Back n）上,使用C6D6测量系统开展了169Tm辐射俘获反应测量。通过脉冲高度权重技术、共振吸收法和饱和归一法得到169Tm辐射俘获反应的产额。利用SAMMY程序拟合169Tm的产额数据,得到169Tm在1~100 eV能量区间的共振能量、中子宽度、辐射俘获宽度等共振参数。使用实验测得的共振参数和Reich Moore近似计算了169Tm在1~100 eV能量区间的辐射俘获截面。实验测量结果与ENDF/B Ⅷ.0数据库的推荐值总体符合较好,部分共振参数和截面存在一定的差异。产生这些差异的原因与Back n的源中子能谱结构、能量分辨率、实验本底的精度有关。     

中国散裂中子源靶站中子通道初步屏蔽计算分析

基于中国散裂中子源靶站中子通道设计,采用二维离散纵标程序DORT对中子导出通道各种设计方案的屏蔽效果进行计算分析。计算得出二维剂量场分布及通道中心处剂量当量率轴向分布,并得到较优化的屏蔽方案及模型,确保谱仪大厅内工作人员接受的剂量低于规定的标准。结果表明,未安装谱仪的中子通道屏蔽模型中心含有SS316合金钢时的屏蔽效果较好,剂量在辐射防护标准以下,符合设计要求。中子孔道开闭装置屏蔽模型中前端加入钨板屏蔽效果较好,并随钨板长度的增加,屏蔽效果提高。     

铜镜的快中子活化分析

利用中子发生器产生的快中子对50面古代青铜镜进行了快中子活化分析。铜镜标本取自不同朝代,采用比较分析法测定了铜镜中的铜、锡、铅三个组分的含量。文中介绍了测量过程中的具体方法和设备。     

Reactor Neutron Fluctuation Simulator Using Pulsed Neutron Source

The fission phenomena in a multiplying medium are simulated by neutron bursts in a non-multiplying medium produced by a pulsed neutron source. To simulate the chain reaction, the pulsed neutron source is triggered by neutronic signals from a detector installed in that medium. The kinetic parameters can be changed at will by regulating the detector sensitivity, the system medium and the burst yield of the pulsed neutron source.

This simulator has been tested on experiments with Rossi-a, Feynman-a and pulse die away methods and is also applied to the experiments with waiting time method and observation of neutron families to verify the recently developed theory in this domain.

The results prove that, in principle, the number of neutrons in this simulator can represent the probabilistic nature of the neutrons in a multiplying medium described by one point model. Furthermore, the newly developed theory for reactor parameter measurement has been substantiated with use of the simulator.

The simulator in its present form is restricted in applicable range to keff=0–0.66 by limitations in the performance of the pulsed neutron source used.     

241Am-Be中子源快中子成像研究

中子成像是一种与X射线成像互补的无伤探测技术。快中子比热中子等低能中子具有更强的穿透力而适合更厚材料的检测。但是快中子难于探测使得快中子成像研究直到最近几年才受到人们的重视。同位素和加速器中子源适合发展可移动中子成像无伤检测系统，而且同位素中子源还有发展便携式无伤探测系统的潜能。本文介绍作者利用同位素中子源241Am-Be开展快中子成像研究的初步结果。     

中国先进研究堆冷中子源中子性能和自稳特性优化研究

针对中国先进研究堆(CARR)冷中子源的技术难点，研究采用国际上尚无先例的带助冷冷包结构及带助冷两相热虹吸自然循环冷却方式的可行性。在此基础上，开展了新冷却方式下冷包内液氢形状的优化，对不同冷包结构下的中子性能进行分析，优化出较好的冷包结构。针对该冷却方式，开展了对冷中子源运行稳定性至关重要的自稳特性的研究，推导出具有一阶惯性环节的自稳特性方程。通过对方程解的分析，证明了CARR新冷却方式具有较好的自稳特性并可据此开展优化分析。     

Small Resonance Accelerator with a Laser Ion Source for Neutron Production

An operating model of a neutron source based on a small linear resonance accelerator of deuterons with a laser ion source is described. The results of theoretical and experimental investigations and optimization of the physical characteristics of the model are presented. An assessment is made of the possibility of increasing the neutron yield of the apparatus.     

Neutron Yield Increase by Simulated Pyroelectric Crystal Neutron Source

In this work, we initially simulated a pyroelectric crystal neutron source and calculated its neutron yield. Then in order to carry out its validation, we compared our results with experimental results. Afterwards with changes in the pyroelectric crystal shape, we could reduce the ion beam radius and followed by its convergence; the neutron gain increased. In the following, we compounded the convergence model and two crystal systems that caused more neutron gains. Finally, by using various materials as the target, we tried to offer materials with high neutron producing ability.     

A Pulsed Neutron Source for Thermal Reactor Physics

A compact 200 kV Cockcraft type pulsed neutron source was designed and constructed as a versatile tool for various pulsed neutron experiments in thermal reactor physics. Special care was taken to obtain the maximum peak intensity of pulsed neutrons against the average background neutrons induced from accelerator operation. To this end, two particular design features have been adopted. One is pulsing of the R-F ion source probe voltage combined with pulsing of the deflector voltage of the post accelerated D⁺ ion beam. The other feature is the use of a beam analyzing magnet to the accelerated beam. With these devices, a peak to background ratio of 10⁵ was obtained.

Pulsed neutrons of 14 MeV can be generated at pulse widths from 0.13 μs 500 ms, with a neutron yield of 3.7×10⁴–2×10⁹ n/pulse. The repetition rate of the pulses can be changed independently of the pulse width. An arrangement for long focusing beam adjustment provides for selection of the target position in a wide range.