活化法测量散裂靶中子能谱的实验验证

散裂靶中子的能谱对加速器驱动次临界系统的倍增因数和嬗变率等影响很大,计算表明散裂靶中子谱在MeV能区与裂变中子谱相近。本文利用活化法测量临界装置的泄漏中子谱和中子注量率,提出了用In、Al、Mg、Ti、Au、Zn、Ni、Rh、Fe和Co等活化箔测量散裂靶中子能谱和中子注量率的方案。结果表明,将活化箔在散裂靶中子场中辐照5h,中子注量最高达5×1014 cm-2量级,辐照后1h内取出活化箔,根据半衰期的长短安排测量顺序,可测量散裂靶的中子能谱和中子注量率。     

中国散裂中子源强流质子加速器设计、研制及调试运行

中国散裂中子源(CSNS)是基于强流质子加速器的大科学装置,通过高功率质子束流轰击重金属靶产生高通量中子用于开展中子散射研究,CSNS是世界上第四台、发展中国家第一台脉冲型散裂中子源。CSNS包括高功率强流质子加速器、中子靶站和中子谱仪以及相应的配套设施等。加速器由80 MeV负氢直线加速器、1.6 GeV快循环同步加速器及相应的束流输运线组成。CSNS加速器是我国第一台中高能强流高功率质子加速器,本文将介绍CSNS加速器的设计、关键技术、设备研制以及束流调试过程和其中关键问题。     

中国散裂中子源强流质子加速器设计、研制及调试运行

中国散裂中子源（CSNS）是基于强流质子加速器的大科学装置,通过高功率质子束流轰击重金属靶产生高通量中子用于开展中子散射研究,CSNS是世界上第四台、发展中国家第一台脉冲型散裂中子源。CSNS包括高功率强流质子加速器、中子靶站和中子谱仪以及相应的配套设施等。加速器由80 MeV负氢直线加速器、1.6 GeV快循环同步加速器及相应的束流输运线组成。CSNS加速器是我国第一台中高能强流高功率质子加速器,本文将介绍CSNS加速器的设计、关键技术、设备研制以及束流调试过程和其中关键问题。     

中国散裂中子源直线加速器高功率自动老炼平台研制

本文研制了中国散裂中子源(CSNS)直线加速器高功率自动老炼平台,该平台集成了驻波比保护、真空检测、弧光打火探测器、腔体谐振频率计算和变频等功能,可根据腔体的打火情况自适应调节功率进行腔体老炼,通过软件界面对相关参数进行修改即可适应不同腔体的需求。该平台具有高安全性、高智能化、灵活性强的特点,其已在CSNS直线加速器8套功率源系统上使用,在保证腔体和功率源安全的前提下,大幅提高了老炼效率和降低值班人员的劳动量。     

中国散裂中子源RFQ的研制

中国散裂中子源研发了一台射频四极RFQ(Radio Frequency Quadrupole)强流质子加速器。为保证RFQ顺利出束,对加工焊接阶段、RF调谐调场、高功率RF(Radio Frequency)老练过程中出现的问题进行了分析,给出了解决办法,并进行了调束实验。三坐标测量测得RFQ精加工后的加工公差约在20μm,RFQ腔体无载品质因子Q0大于7 679,约为理论无载Q0值的80%。RFQ腔内RF电场分布的平整度好于2.5%,RFQ高功率RF老练入腔功率达到450 k W,是理论腔耗390 k W的1.15倍,且保持连续12 h不打火。在RFQ调束实验中,RFQ出口得到3 Me V、28 m A的负氢束流,满足中国散裂中子源的要求。     

中国散裂中子源快循环同步加速器束团长度研究

束团长度是中国散裂中子源（CSNS）快循环同步加速器（RCS）束流动力学的关键参数,通过对束团长度的研究,可了解RCS的机器性能并进一步指导机器优化研究。本文对RCS 100 kW时的束团长度进行精确测量,100 kW引出时的束团长度为105 ns。RCS 500 kW时束团长度可能超过无损引出允许值,需压缩束团长度。理论上提高腔压可压缩束团长度,本文模拟研究500 kW时束团长度随腔压曲线的变化规律,模拟结果表明提高加速后半阶段的腔压可压缩束团长度,给出了500 kW时无束流损失引出的腔压曲线。基于100 kW束流条件实验验证了通过提高加速后半阶段腔压来压缩束团长度的有效性和可行性,实验测量结果与模拟结果一致。因此,提高加速后半阶段腔压是500 kW时无损引出束流的有效方法。     

中国散裂中子源快循环同步加速器束团长度研究

束团长度是中国散裂中子源(CSNS)快循环同步加速器(RCS)束流动力学的关键参数,通过对束团长度的研究,可了解RCS的机器性能并进一步指导机器优化研究。本文对RCS 100 kW时的束团长度进行精确测量,100 kW引出时的束团长度为105 ns。RCS 500 kW时束团长度可能超过无损引出允许值,需压缩束团长度。理论上提高腔压可压缩束团长度,本文模拟研究500 kW时束团长度随腔压曲线的变化规律,模拟结果表明提高加速后半阶段的腔压可压缩束团长度,给出了500 kW时无束流损失引出的腔压曲线。基于100 kW束流条件实验验证了通过提高加速后半阶段腔压来压缩束团长度的有效性和可行性,实验测量结果与模拟结果一致。因此,提高加速后半阶段腔压是500 kW时无损引出束流的有效方法。     

中国散裂中子源快循环同步加速器射频系统的设计与研制进展

研制了大功率宽带快速扫频射频系统,其用于中国散裂中子源（CSNS）快循环同步加速器（RCS）中,主要包括铁氧体加载谐振腔、射频功率源、偏流源和低电平控制系统。射频系统工作重复频率为25 Hz,扫频范围为1.022～2.444 MHz,单个腔体（双加速间隙）可提供最大30 kV加速电压。两级的调谐控制能解决快速扫频过程中的系统失谐问题,采用束流前馈、直接反馈等多种技术手段可对束流负载效应进行补偿。     

中国散裂中子源靶体研制

中国散裂中子源(CSNS)靶体选用钨为靶材、钽为包覆层,采用包套法结合热等静压扩散焊工艺制备了钽包覆钨靶片。经检测,钨钽界面结合良好,钽层与钨基体平均结合强度大于64.07 MPa。靶体将钨靶片分成厚度不等的11片,散热采用一进一出的并行流结构,利用CFD软件进行了模拟计算,钨靶片间冷却流道间隙为1.2 mm,100 kW满功率运行情况下靶体最高温度为182.3 ℃,冷却水温升为7.1 ℃。经过半年多的试运行,CSNS靶体各参数满足CSNS的要求。     

Design of a prompt-gamma neutron activation analysis system on China Advanced Research Reactor

In this paper,computational methods are used to optimize the design of a prompt-gamma neutron activation analysis(PGNAA) system on China Advanced Research Reactor(CARR).Approaches are adopted for obtaining accurate neutron beam parameter and saving the computing time.For the radiation shielding design,the optimizing factors include the cost,weight,volume,machining convenience and background radiation at the detector position.Low background spectrum and high sensitivity are expected.The simulation results...     

Multi-scale modeling of irradiation effects in spallation neutron source materials

Changes in mechanical property of Ni under irradiation by 3 GeV protons were estimated by multi-scale modeling. The code consisted of four parts. The first part was based on the Particle and Heavy-Ion Transport code System (PHITS) code for nuclear reactions, and modeled the interactions between high energy protons and nuclei in the target. The second part covered atomic collisions by particles without nuclear reactions. Because the energy of the particles was high, subcascade analysis was employed. The direct formation of clusters and the number of mobile defects were estimated using molecular dynamics (MD) and kinetic Monte-Carlo (kMC) methods in each subcascade. The third part considered damage structural evolutions estimated by reaction kinetic analysis. The fourth part involved the estimation of mechanical property change using three-dimensional discrete dislocation dynamics (DDD). Using the above four part code, stress-strain curves for high energy proton irradiated Ni were obtained.     

Transmutation characteristics of problematic radionuclides in spallation and fusion neutron source

Transmutation of radiowaste is often referred to as a crucial step toward environmentally harmonized nuclear energy system. This area concerns with elimination of two classes of radionuclides: minor actinides and fission products. In a great majority of transmutation studies the stress has been given to some particular transmuters, mainly fast and accelerator driven reactors, and potential advantage of their use in waste management. The logic of the present paper goes in an opposite direction. Having finished general discussion on the final goal of transmutation, it turns to identify the radionuclides being the most severe obstacle on this way and, only after that, advocates the appropriate transmutation environments. Among the problematic nuclides cesium isotopes and ²⁴⁴Cm are accentuated with advocated correspondingly fusion and accelerator-driven transmutation.     

散裂中子源靶站和中子散射谱仪的概念设计

本文介绍了可应用于多学科应用的散裂中子源(CSNS)靶站和中子散射谱仪概念设计的进展。CSNS靶站将由重水冷却多片钨靶,铍/铁反射体和铁/重混凝土生物屏蔽体组成。采用三个WING型慢化器:水(室温),液体甲烷(100K)和液体氢(20K),设有18个水平中子孔道。MonteCarlo模拟显示优化的靶截面高宽比为1:2.5左右。额定的100kW核功率的质子束轰击后,慢化器处钨靶溢出的脉冲中子通量约为2.4×1016cm?2·s?1。有限元方法计算表明,钨靶体内的总发热量是47kJ/s。即使使用截面较小的钨靶,在通常的水冷速率下,靶体温度也仅略高于90°C。靶体的热应力形变最大不超过0.2mm。根据经济实用原则选择建造粉末衍射仪、小角散射仪、反射仪及直接几何非弹性散射仪等四类有代表性的中子散射谱仪,就能覆盖>80%的中子散射研究领域。     

~(252)Cf中子活化元素分析技术在工业过程控制中的应用前景

本文综述了利用~(252)Cf中子活化元素分析技术在工业过程控制中的应用现状、特点、前景和我国面临的任务。     

中国散裂中子源快周期同步加速器磁铁电源系统的研究

目前正在进行可行性研究的中国散裂中子源的主体结构是1台强流质子同步加速器。该加速器的一期目标为注入能量70MeV、引出能量1.6GeV、束流功率100kW、循环工作频率25Hz。文章阐述系统总体结构的设计原则以及二极磁铁（B）和四极磁铁（Q）磁场的跟踪误差要求。     

Development of self-powered neutron detectors for neutron flux monitoring in HCLL and HCPB ITER-TBM

Self powered neutron detectors (SPND) have a number of interesting properties (e.g. small dimensions, capability to operate in harsh environments, absence of external bias), so they are attractive neutron monitors for TBM in ITER. However, commercially available SPNDs are optimized for operation in a thermal nuclear reactor where the neutron spectrum is much softer than that expected in a TBM. This fact can limit the use of SPND in a TBM since the effective cross sections for the production of beta emitters are much lower in a fast neutron spectrum.This work represents the first attempt to study SPNDs as neutron flux monitors for TBM. Three state-of-the-art SPND available on the market were bought and tested using fast neutrons at TAPIRO fast neutron source of ENEA Casaccia and with 14 MeV neutrons at the Frascati neutron generator (FNG).The results clearly indicate that in fast neutron spectra, the response of SPNDs is much lower than in thermal neutron flux. Activation calculations were performed using the FISPACT code to find out possible material candidates for SPND suitable for operation in TBM neutron spectra.     

Experimental study on heat transfer and pressure drop in mercury flow system for spallation neutron source

In the design of MW-class spallation target system, using mercury to produce practical neutron applications, keeping the highest level of safety is vitally important. To establish the safety of spallation target system, it is essential to understand the thermal hydraulic properties of mercury. Through thermal hydraulic experiments using a mercury experimental loop, which flows at the rate of 1.2 m³/hr maximum, the following facts were experimentally confirmed. The wall friction factor was relatively larger than the Blasius correlation due to the effects of wall roughness. The heat transfer coefficients agreed well with the Subbotin correlation. Furthermore, for validation of the design analysis code, thermal hydraulic analyses were conducted by using the STAR-CD code under the same conditions as the experiments. Analytical results showed good agreement with the experimental results, using optimized turbulent Prandtl number and mesh size.     

A high-flux accelerator-based neutron source for fusion technology and materials testing

Advances in high-current linear-accelerator technology since the design of the Fusion Materials Irradiation Test (FMIT) Facility have increased the attractiveness of a deuteriumlithium neutron source for fusion materials and technology testing. This paper discusses the conceptual design of such a source that is aimed at meeting the near-term requirements of a high-flux high-energy International Fusion Materials Irradiation Facility (IFMIF). The concept employs multiple accelerator modules providing deuteron beams to two liquid-lithium jet targets oriented at right angles. This beam/target geometry provides much larger test volumes than can be attained with a single beam and target and produces significant regions of low neutron-flux gradient. A preliminary beam-dynamics design has been obtained for a 250-mA reference accelerator module. Neutron-flux levels and irradiation volumes were calculated for a neutron source incorporating two such modules, and interaction of the beam with the lithium jet was studied using a thermal-hydraulic computer simulation. Approximate cost estimates are provided for a range of beam currents and a possible facility staging sequence is suggested.This work was supported by Los Alamos National Laboratory Program Development Funds under the auspices of the U.S. Department of Energy.Supported in part by an appointment to the U.S. DOE Fusion Energy Postdoctoral Research Program administered by Oak Ridge Associated Universities.     

循环中子活化分析茶叶中的氟含量

应用堆循环中子活化分析(Cyclic neutron activation analysis,CNAA)和三种传统氟测量方法分析了含氟标准参考物质茶叶(GBW10016)中氟含量。结果表明,CNAA具有准确性好、灵敏度高、省时、用量少、溯源性强、抗干扰性好等优势。CNAA分析四类16种商品茶中氟含量的结果显示,茶叶中氟含量依次为黑茶、红茶、乌龙茶、绿茶,其原因与茶叶的选料及加工工艺密切相关。个别黑茶氟含量高达276 mg/kg,超出国家限量标准(≤200 mg/kg),存在饮用安全风险。