HL—1M中的聚变中子产额

本文概算了在欧姆加热、波加热和中性束注入条件下，ＨＬ－１Ｍ托卡马克等离子体的聚变中子变额中子通量，以及相关的电离率，电交换率及快离子的空间分布。计算结果为发展下一代聚变中子探测系统和进行中子辐射的环境评估提供了依据。     

HT-7上氘等离子体放电时中子注量的测量与分析

利用三氟化硼（BF₃） 和氦三（3He）正比计数管组成的快速时间分辨中子注量探测系统,对HT-7超导托卡马克上氘等离子体放电时光中子和聚变中子的产生机理进行研究.结合γ射线、硬X射线等相关诊断的实验结果,分析了纯欧姆放电和低杂波辅助加热放电时,中子注量信号随时间演化的典型特征.结果表明：HT-7在投入大功率低杂波辅助加热等离子体放电时,能够产生数量可观的氘-氘（D-D）聚变中子. 关键词： 中子注量 聚变中子 光中子 托卡马克     

中子学积分实验

从６０年代开始，我所就开展了聚变中子积分实验，完成了造氚率、裂变率、穿透率及泄漏中子能谱测量等研究课题。１９８７年以来承担了“８６３”计划的聚变裂变混合堆包层中子学积分实验，开展了Ｂｅ、Ｐｂ的１４ＭｅＶ中子倍增率实验，其中Ｂｅ实验为中、美、日国际合作，实验误差为２．８％，实验结果为理论计算提供积分检验。     

聚变中子学的蒙特卡罗PVM并行模拟在ITER中子诊断设计中的应用

聚变能源很可能是人类文明得以维持发展的新型能源。未来的氘氚聚变堆的结构和工程设计很大程度上依赖于以聚变中子学为基础的计算。在过去的十余年中，很多的核数据库如FENDL和JENDL的检验工作围绕ITER设计而展开。聚变中子学计算包括中子和光子的输运计算。其计算目标是提供反应率和能谱等重要的信息。一维或二维的聚变中子学解析计算能提供一定精度的结果和高效率的优化设计，但对于一个三维的聚变托卡马克反应堆来说，只有蒙特卡罗方法能提供较精确的数值模拟结果。MCNP程序是由LANL实验室发展的用于中子和光子的蒙特卡罗计算的大型程序。PVM的并行计算环境能提高为MCNP程序的运行执行效率。     

HL-1M托卡马克中的中子通量和辐射剂量当量测量

用5台带有慢化剂(聚乙烯)的BF3₃正比计数管中子探测器测量中子通量和剂量当 量.4台 置于HL_1M装置的四周,分别测量了在氘等离子体条件下,因欧姆加热和波加热产生的热核聚 变中子产额、中子通量和剂量,以及氢等离子体条件下因高能x射线引起的光致核反应而产生 的光致中子. 另一台流动于其他6个观察点,主要监测中子剂量当量. 在D_D聚变条件下,实测 中子产额与计算值作比较,两者在数量级上大体一致. 中子辐射剂量当量远低于国家和部颁 标准,更低于国际防护委员会推荐的中子辐射允许剂量当量 关键词： 3正比计数管')" href="#">BF3₃正比计数管 光致中子 氘_氘聚变中子 剂量当量     

球形托卡马克堆嬗变中子学计算的比较研究

基于对球形托卡马克（ST）聚变堆的研究，提出了ST聚变－嬗变堆的设计概念。运用一维输运燃耗计算程序BISON3.0进行了优化设计，确定了适合于嬗变少额锕系MA核素的堆芯等离子体参数、包层结构及合适的换料周期。在一维计算的基础上，运用二维中子学程序TWODANT进行了二维中子输运计算；结合TWODANT给出的中子通量，运用一维放射性计算程序FDKR进行了燃耗计算，并给出了有关的计算结果。     

SILEX-I装置上激光-团簇聚变实验中子产额测量

 超短超强脉冲激光与CD4团簇相互作用可以产生高能量的氘离子,从而产生DD聚变中子,这种团簇聚变中子源有着非常广阔的应用前景。在SILEX-I 100 TW飞秒激光装置上,超短超强脉冲激光与CD₄团簇相互作用实现了DD核聚变。团簇聚变的中子产额是实验中最为重要的物理量,在实验中采用高灵敏的中子探测器对团簇聚变产生的中子进行了测量,在现有实验条件下测得中子产额为10³。     

聚变堆中子对第一壁辐照损伤的计算机模拟研究

用蒙特卡罗方法建立了适用于静态复成分非晶态靶的中子和带电粒子辐照损伤连接模拟程序，在模拟带电粒子级联碰撞时，特别考虑了替位碰撞，修正后的ＤＰＡ值比未考虑时减少了１０％－２０％；同时统计了ＤＰＡ中反常替位所占的比例。用此程序模拟研究了聚变堆中子对两种第一壁候选材料的辐照损伤，计算了中子辐照在材料中引起的ＰＫＡ。气体产生率，ＤＰＡ以及它们的深度分布，计算结果表明，中子引起的辐照损伤基本上为均匀的体损伤     

利用超高能中子诊断惯性约束聚变的燃烧

惯性约束聚变靶丸中,高能中子相互之间发生碰撞将导致超高能中子的产生.本文讨论超高能中子产生与聚变燃烧速率的关系.数值模拟理想模型,分析超高能中子产生量与平均烧氚体积的关系,讨论利用出壳超高能中子流与烧氚量诊断二维效应和混合效应.进一步分析出壳超高能中子流与平均烧氚率的关系,探讨利用超高能中子诊断平均烧氚温度并判断是否发生非平衡效应问题.     

中子学积分实验

从６０年代开始,我所就开展了聚变中子积分实验,完成了造氚率、裂变率、穿透率及泄漏中子能谱测量等研究课题．１９８７年以来承担了“８６３”计划的聚变裂变混合堆包层中子学积分实验,开展了Ｂｅ、Ｐｂ的１４ＭｅＶ中子倍增率实验,其中Ｂｅ实验为中、美、日国际合作,实验误差为２．８％,实验结果为理论计算提供积分检验．新的一轮中、美、俄的更大厚度的Ｂｅ中子倍增率实验国际合作正在进行之中．现在,中美关于核聚变合作已经确定了１７个项目,我所承担了其中的“关于ＩＴＥＲ和建议的聚变堆包层及屏蔽系统的中子学积分实验”这一项目． Since 1960s, the fusion neutronics integral experiments have been carried outin our institute. Several research subjects, including the measurements of the tritium production rate,the fission rate,the leakage rate and the neutron energy spectra, have been finished. Since 1987,neutronics integral experiments of the blanket in the fusion-fission hybridreactor in the "863" project have been taken on. The experiments of 14MeV neutron multiplication in Be and Pb have been performed and the experimental error is ...     

Diagnostic technique for measuring fusion reaction rate for inertial confinement fusion experiments at Shen Guang-Ⅲ prototype laser facility

A study is conducted using a two-dimensional simulation program （Lared-s） with the goal of developing a technique to evaluate the effect of Rayleigh-Taylor growth in a neutron fusion reaction region. Two peaks of fusion reaction rate are simulated by using a two-dimensional simulation program （Lared-s） and confirmed by the experimental results. A neutron temporal diagnostic （NTD） system is developed with a high temporal resolution of - 30 ps at the Shen Guang-Ⅲ （SG-Ⅲ） prototype laser facility in China, to measure the fusion reaction rate history. With the shape of neutron reaction rate curve and the spherical harmonic function in this paper, the degree of Rayleigh-Taylor growth and the main source of the neutron yield in our experiment can be estimated qualitatively. This technique, including the diagnostic system and the simulation program, may provide important information for obtaining a higher neutron yield in implosion experiments of inertial confinement fusion.     

Diagnostic technique for measuring fusion reaction rate for inertial confinement fusion experiments at Shen Guang-III prototype laser facility

A study is conducted using a two-dimensional simulation program(Lared-s)with the goal of developing a technique to evaluate the effect of Rayleigh–Taylor growth in a neutron fusion reaction region.Two peaks of fusion reaction rate are simulated by using a two-dimensional simulation program(Lared-s)and confirmed by the experimental results.A neutron temporal diagnostic(NTD)system is developed with a high temporal resolution of~30 ps at the Shen Guang-III(SG-III)prototype laser facility in China,to measure the fusion reaction rate history.With the shape of neutron reaction rate curve and the spherical harmonic function in this paper,the degree of Rayleigh–Taylor growth and the main source of the neutron yield in our experiment can be estimated qualitatively.This technique,including the diagnostic system and the simulation program,may provide important information for obtaining a higher neutron yield in implosion experiments of inertial confinement fusion.     

超快中子探测器闪烁体性能计算

超快中子探测器是ICF聚变反应速率测量系统的核心部件。利用蒙特卡罗粒子输运工具包Geant4模拟了一种超快中子探测器——BC-422型闪烁探测器的中子探测过程,计算出了几种厚度的BC-422型闪烁体的探测效率、输出光信号强度和时间分辨力;对比了闪烁体的2种不同反射表面对输出光信号强度和时间分辨力的影响。计算的结果显示:设计适当的BC-422型闪烁探测器能够测量的最低中子产额在108量级,对DT中子的信号时间分辨力好于20 ps,对DD中子的信号时间分辨力达到30 ps,能够用于大型激光装置及其原型的聚变反应速率测量。     

核聚变而不带强放射性的新途径

由晶格内束缚态离子引起的共振隧穿现象将完全不同于低能下束－靶相互作用引发的核反应现象。由于库仑位垒的作用，只有那些长寿命的核内能级才能与晶格内的离子能级发生共振。其结果是，带来中子辐射的快速核反应过程都不可能由此共振隧穿引发，也就是取得核聚变能而不引发强烈的中子辐射是可能的。     

Recent Result of Muon Catalyzed t–t Fusion at RIKEN-RAL

We have measured X-rays and neutrons associated with the muon catalyzed t–t fusion process at the RIKEN-RAL Muon facility. In the X-ray measurement, we observed K_α and K_β X-rays originating from the muon sticking process in muon catalyzed t–t fusion, and obtained the K_α X-ray yield and the K_β/K_α intensity ratio. An average recoil energy of the (μ⁻α) atoms in a solid T₂ medium was determined from the observed Doppler broadening width of the K_α X-ray line. The obtained t–t fusion neutron has shown an exponential time spectrum with a single component and a continuous energy spectrum with a maximum energy of 9 MeV. We have determined the t–t fusion neutron yield, the t–t fusion cycling rate and the muon sticking probability from the neutron data. The obtained maximum neutron energy is a very peculiar value from the view point of the reaction Q value (11.33 MeV) with the three-particle decay mode at the exit channel: t + t → α + n + n + Q. The obtained neutron energy distribution was analyzed by a simple model with two neutron energy components; reasonable agreement has been obtained, suggesting a strong (n–α) correlation in the exit channel of the t–t muon catalyzed fusion reaction. This revised version was published online in August 2006 with corrections to the Cover Date.     

近垒重离子熔合反应中的中子转移效应(英文)

近势垒及其以下能区重离子熔合反应中的中子转移耦合道效应是一个复杂且有争议的问题。简要介绍了近年来在中国原子能科学研究院的HI-13串列加速器上,基于静电偏转板装置完成的32S+90,94,96Zr,18O+74Ge和18O+58Ni等几个典型体系的熔合反应研究情况,并结合耦合道理论对实验数据进行了分析。选取反应体系时同时关注了正Q值的中子拾取和削裂道。另外,基于完全耦合道理论计算,提出了一种能够定量提取熔合反应中中子转移效应的自洽方法。这些研究进一步证实了垒下重离子熔合反应中的中子转移效应,同时指出了其复杂性。需要进一步的实验和理论研究来澄清相关核反应机制。The effect of neutron transfers on near-and sub-Coulomb-barrier fusion of heavy-ions is still a complicated and controversial problem. This paper reviews the recent experimental results of the fusion excitation functions of several typical systems, which have been measured by using an electrostatic deflector setup at the HI-13 tandem accelerator of CIAE. Both the neutron pickup and stripping effects were studied. Moreover, a self-consistent method to reliably isolate the transfer effect quantitatively based on the coupledchannels calculation is proposed. These studies give a further support for the neutron transfer effect on sub-barrier fusion of heavy-ions and its complexity. Further experimental and theoretical studies are needed for clarifying the relevant reaction mechanisms.     

聚变中子能谱测量系统脉冲中子灵敏度的实验研究

为多种复杂环境下的稳态和脉冲DT聚变中子能谱测量建立了一种灵敏度优化反冲质子磁谱仪. 使用成像板和同位素α源测量了谱仪的反冲质子能量-位置投影关系. 利用稳态加速器中子源平台、通过单粒子计数方法结合三维带电粒子输运程序模拟,研究了谱仪脉冲中子灵敏度能量响应. 通过高探测效率参数设置使谱仪对DT中子的探测效率达到2×10^-5 cm²水平,从而在较弱中子源上获得了较高统计精度实验数据. 程序模拟结果与谱仪α粒子刻度和DT中子标定实验结果取得了良好的一致性,可由此发展精细解谱技术,以提高脉冲中子能谱测量的灵敏度和能量分辨. 关键词： 聚变中子能谱 磁反冲质子 脉冲中子灵敏度 粒子输运     

Radiation effect of neutrons produced by D–D side reactions on a D–3He fusion reactor

One of the most important characteristics in D–³He fusion reactors is neutron production via D–D side reactions. The neutrons can activate structural material, degrading them and ultimately converting them into high-level radioactive waste, while it is really costly and difficult to remove them. The neutrons from a fusion reactor could also be used to make weapons-grade nuclear material, rendering such types of fusion reactors a serious proliferation hazard. A related problem is the presence of radioactive elements such as tritium in D–³He plasma, either as fuel for or as products of the nuclear reactions; substantial quantities of radioactive elements would not only pose a general health risk, but tritium in particular would also be another proliferation hazard. The problems of neutron radiation and radioactive element production are especially interconnected because both would result from the D–D side reaction. Therefore, the presentation approach for reducing neutrons via D–D nuclear side reactions in a D–³He fusion reactor is very important. For doing this research, energy losses and neutron power fraction in D–³He fusion reactors are investigated. Calculations show neutrons produced by the D–D nuclear side reaction could be reduced by changing to a more ³He-rich fuel mixture, but then the bremsstrahlung power loss fraction would increase in the D–³He fusion reactor.     

氘氚聚变中子发生器旋转氚靶传热特性研究

强流氘氚中子发生器可用于模拟聚变堆中子环境, 对于开展聚变堆包层材料相关实验研究具有重要意义. 本文提出了一种用于10¹² n·^-1量级氘氚中子发生器HINEG (high intensity neutron generator)的旋转氚靶系统设计方案, 并对其技术难点和强化传热方法进行了介绍. 为考查该氚靶系统的传热特性, 利用Computational Fluid Dynamics方法对冷却水层厚度、冷却水流速和氚靶系统旋转速度对靶面冷却的影响进行了分析, 并对不同热功率密度下靶面的传热过程进行了研究. 结果显示, 大的水层厚度、大的冷却水流速和高的靶系统旋转速度有利于靶面的冷却, 但水层厚度和水流速的变化对靶面传热影响较小. 一定条件下靶面所承受的热功率密度不能超过某个限值.