中国散裂中子源二期靶站关键部件辐照损伤模拟计算

中国散裂中子源一期工程于2018年通过国家验收,当前束流功率已经达到140 kW.为进一步提高靶站慢化器输出中子强度,已经提出中国散裂中子源二期500 kW功率升级计划.靶站关键部件长期受到高通量、高能量的粒子辐照,会产生较强的辐照损伤,影响着这些部件的使用寿命.本文首先使用PHITS3.33程序计算了钨、SS316不锈钢、6061铝合金3种材料的质子和中子原子离位截面以及氢、氦的产生截面,并分析了NRT (Norgett-Robinson-Torrens)模型和热平衡前原子复位修正(athermal recombination corrected,ARC)模型对材料离位损伤的影响.在此基础上结合中国散裂中子源二期靶站基线模型计算了靶站关键部件在500 kW的束流功率下运行5000 h产生的原子离位次数(displacement per atom,DPA)以及氢、氦的产额.计算结果表明,钨靶受辐照后产生的NRT-dpa,ARC-dpa,H和He产额最大值分别为8.01 dpa/y (1 y=2500 MW·h),2.39 dpa/y,5110 appm/y (atom parts pe...     

散裂中子源靶站谱仪的物理设计

中子散射广泛地应用于凝聚态物质研究和应用的众多学科领域,是研究物质微观结构和动态的理想工具之一.散裂中子源能是新一代的加速器基脉冲中子源,能为中子散射提供高通量的脉冲中子.文章重点介绍了散裂中子源项目CSNS中靶站和谱仪的建设内容和设计工作的进展.     

散裂中子源与中子散射

文章介绍了散裂中子源的物理基础、中子散射用散裂中子源对加速器的要求和靶系统的特点，阐述了利用散裂源，尤其是脉冲散裂源进行了散射实验的主要优点，并对我国建造散裂中子源的发展战略提出了建议。     

中国散裂中子源的多学科应用

中国散裂中子源(China Spallation Neutron Source,CSNS)是我国首台、世界第4台脉冲型中子大科学设施。CSNS基于加速器产生的高能质子轰击钨靶产生中子,然后利用中子进行实验。CSNS面向全世界的用户开放,为科学研究和工业研发服务,在物理、化学、生物、能源、材料等领域都有广泛的应用。文章将介绍CSNS的基本构成、发展历程和中子散射的多学科应用。     

中国散裂中子源简介

一、中子散射1932年,查德威克发现了中子,人们认识到原子核由带正电的质子和不带电的中子构成。中子的发现及应用是20世纪最重要的科技成就之一。当一束中子入射到所研究的对象上时,与研究材料中的原子核或磁矩发生相互作用,被散射出来,通过测量散射出来的中子能量和动量的变化     

散裂中子源靶站谱仪的物理设计

中子散射广泛地应用于凝聚态物质研究和应用的众多学科领域,是研究物质微观结构和动态的理想工具之一.散裂中子源能是新一代的加速器基脉冲中子源,能为中子散射提供高通量的脉冲中子.文章重点介绍了散裂中子源项目CSNS中靶站和谱仪的建设内容和设计工作的进展.     

基于中国散裂中子源反角白光中子束线的天然锂中子全截面测量

锂是熔盐堆燃料载体盐的主要材料之一,其中子核反应截面数据是熔盐堆芯中子物理设计及堆芯长期安全运行中的重要基础数据.本工作基于中国散裂中子源反角白光中子束线(CSNS Back-n)飞行时间谱仪,利用中子全截面测量谱仪(NTOX),采用透射法测量了天然锂中子全截面.实验中,中子飞行距离约为76.0 m,采用15.0 mm和8.00 mm两种厚度的天然锂金属样品,在0.4 e V—20 Me V中子能量范围内测得了统计计数较好的中子全截面.特别是在ke V及以下能区增补了实验数据,为锂的核数据评价工作提供了更加丰富和可靠的实验数据.在此基础上,采用1/v律和R矩阵理论对Me V以下能区的新测量数据进行了理论分析,获得了7Li和6Li在260 ke V能量附近的中子共振参数.     

中国散裂中子源多功能反射谱仪屏蔽设计

本文介绍了利用蒙特卡罗粒子输运程序MCNPX2.5.0进行中国散裂中子源多功能反射谱仪屏蔽设计的屏蔽需求、辐射源项、计算方法和设计结果等内容.在计算中考虑慢化器泄漏源项、中子导管损失源项等不同辐射源项,使用分步计算和源项角度偏移、源项能量偏移、几何分裂等多种减方差方法,在保证计算结果精度的同时提高计算速度.在谱仪束线传输段、第二中子开关、散射室等的屏蔽计算中,通过比较了不同条件下的所需屏蔽确定最终屏蔽设计,确保谱仪屏蔽外人员可到达区域的剂量低于安全限值2.5μSv/h.     

中国散裂中子源快循环同步加速器主剥离膜设计

设计了中国散裂中子源(CSNS)快循环同步加速器(RCS)注入区的主剥离膜装置。为降低研制难度和成本,提高运行可靠性,选择了回转体式的结构。根据在线可调性、高稳定性、高定位精度和超高真空等技术难点,给出了CSNS/RCS主剥离膜的具体结构方案和控制方案。利用ANSYS有限元分析软件和材料力学原理,对设备的核心部件不锈钢同步带进行了模拟计算和理论分析。     

Preliminary shielding analysis for the CSNS target station monolith

The construction of the China Spallation Neutron Source (CSNS) has been initiated at Dongguan,Guangdong,China.In spallation neutron sources the target station monolith is contaminated by a large number of fast neutrons whose energies can be as large as those of the protons of the proton beam directed towards the tungsten target.A detailed radiation transport analysis of the target station monolith is important for the construction of the CSNS.The analysis is performed using the coupled Monte Carlo and multi-dimensional discrete ordinates method.Successful elimination of the primary ray effects via the two-dimensional uncollided flux and first collision source methodology is also illustrated.The dose at the edge of the monolith is calculated.The results demonstrate that the doses received by the hall staff members are below the required standard limit.     

Preliminary shielding analysis for the CSNS target station monolith

The construction of the China Spallation Neutron Source （CSNS） has been initiated at Dongguan,Guangdong,China.In spallation neutron sources the target station monolith is contaminated by a large number of fast neutrons whose energies can be as large as those of the protons of the proton beam directed towards the tungsten target.A detailed radiation transport analysis of the target station monolith is important for the construction of the CSNS.The analysis is performed using the coupled Monte Carlo and multi-dimensional discrete ordinates method.Successful elimination of the primary ray effects via the two-dimensional uncollided flux and first collision source methodology is also illustrated.The dose at the edge of the monolith is calculated.The results demonstrate that the doses received by the hall staff members are below the required standard limit.     

Calculations of radioactivity and afterheat in the components of the CSNS target station

This paper shows the calculations of radioactivity and afterheat in the components of the China Spallation Neutron Source (CSNS) target station, with the Monte Carlo codes LAHET, MCNP4C and the multigroup code CINDER'90. These calculations provide essential data for the detailed design and maintenance of the CSNS target station.     

单元素靶粒子位移损伤计算方法及有效模式分析

通过SRIM程序的快速损伤计算与全级联计算两种常用模式,对单元素靶材料进行粒子辐照模拟计算,分别利用基于损伤能量间接计算移位数的NRT位移模型方法和直接通过输出文件读取的方法获得移位数,并对数据进行相应的处理及分析对比,结果表明：对于单元素靶来说,在SRIM快速损伤和全级联两种计算模式下,利用NRT位移模型数值计算得到的移位数基本一致,都可以用于进一步计算得到可靠的位移损伤剂量（dpa）;而通过SRIM两种模式下的输出文件数据直接获得的移位数则有两倍左右的差异,要想得到相对可靠的dpa相关参数,需要根据不同辐照情况选取合适的计算模式。     

中国散裂中子源直线加速器丝靶扫描器的设计与模拟

In this paper, we report the design and simulation of a wire scanner for the linac of the CSNS （China Spallation Neutron Source）. The wire scanner is used to measure the transverse beam profile and the emittance. The effect of beam energy change upon the mechanical design of the wire scanner must be considered. The simulation results of heat on the two specified wires, tungsten and carbon, by using the finite element method software, ANSYS, are presented. In addition, the effect of wire deformation on the beam profile measurement is qualitatively analyzed, and the signal level of the wire scanner is discussed.     

Design and simulation of a wire scanner for the CSNS linac

In this paper,we report the design and simulation of a wire scanner for the linac of the CSNS(China Spallation Neutron Source).The wire scanner is used to measure the transverse beam profile andthe emittance.The effect of beam energy change upon the mechanical design of the wire scanner must beconsidered.The simulation results of heat on the two specified wires,tungsten and carbon,by using the finite element method software,ANSYS,are presented.In addition,the effect of wire deformation on the beam profile measurement is qualitatively analyzed,and the signal level of the wire scanner is discussed.     

Neutron capture cross section of 169Tm measured at the CSNS Back-n facility in the energy region from 30 to 300 keV

The capture cross sections of the ¹⁶⁹Tmbegin{document}$ (n, gamma) $end{document} reaction were measured at the back streaming white neutron beam line (Back-n) of the China Spallation Neutron Source (CSNS) using four C₆D₆ liquid scintillation detectors. The background subtraction, normalization, and correction were carefully considered in the data analysis to obtain accurate cross sections. For the resonance at 3.9 eV, the R-matrix code SAMMY was used to determine the resonance parameters with the internal normalization method. The average capture cross sections of ¹⁶⁹Tm for energy between 30 and 300 keV were extracted relative to the ¹⁹⁷Aubegin{document}$ (n, gamma) $end{document} reaction. The measured cross sections of the ¹⁶⁹Tmbegin{document}$ (n, gamma) $end{document} reaction were reported in logarithmically equidistant energy bins with 20 bins per energy decade with a total uncertainty of 5.4% – 7.0% in this study and described in terms of average resonance parameters using a Hauser-Feshbach calculation with fluctuations. The point-wise cross sections and the average resonance parameters showed fair agreement with the evaluated values of the ENDF/B-VIII.0 library in the energy region studied.     

Transient electromagnetic simulation and thermal analysis of the DC-biased AC quadrupole magnet for CSNS/RCS

Due to the large eddy currents at the ends of the quadrupole magnets for CSNS/RCS, the magnetic field properties and the heat generation are of great concern. In this paper, we take transient electromagnetic simulation and make use of the eddy current loss from the transient electromagnetic results to perform thermal analysis. Through analysis of the simulated results, the magnetic field dynamic properties of these magnets and a temperature rise are achieved. Finally, the accuracy of the thermal analysis is confirmed by a test of the prototype quadrupole magnet of the RCS.     

Design and analysis of the tunnel connecting the beamcorridor and the spectrum hall of the CSNS

There is a tunnel connecting the beamcorridor and the target station in the spectrum hall in the CSNS project.The length of the tunnel is about 20 m.The shielding design of the tunnel is very significant for the persons working in the spectrum hall because the tunnel is not covered ed soil for shielding.In order to reduce the dose rate at the exit of the cable ducts,we use the ISIS construction,which is designed with four turnings,as a reference for the tunnel design.The thickness of the shielding is obtained by a simulationwith the Monte Carlo Code FLUKA.The result is compared with the data obtained with Moyer Mode and the reliability of the simulation is proved.This paper provides the basis for the design of the tunnel.     

Design and analysis of the tunnel connecting the beamcorridor and the spectrum hall of the CSNS

There is a tunnel connecting the beamcorridor and the target station in the spectrum hall in the CSNS project. The length of the tunnel is about 20 m. The shielding design of the tunnel is very significant for the persons working in the spectrum hall because the tunnel is not covered by soil for shielding. In order to reduce the dose rate at the exit of the cable ducts, we use the ISIS construction, which is designed with four turnings, as a reference for the tunnel design. The thickness of the shielding is obtained by a simulation with the Monte Carlo Code FLUKA. The result is compared with the data obtained with Moyer Mode and the reliability of the simulation is proved. This paper provides the basis for the design of the tunnel.