质子旋磁比精密测量系统

本文描述了用于质子旋磁比精密测量中的计算机控制测量系统,它采用CAMAC数据获取装置,并用HP-85和PDP-11/60计算机进行在线控制、分析,采用RSX11M操作系统,控制软件用FORTRAN语言编写。     

扩充SPECTRAN-F软件用于活化分析在线数据处理

一、引言中子活化分析在微量元素分析中得到了广泛的应用。它可以同时测定多种元素的含量,但在一次测量中产生大量的数据,尤其是单比较器K_0方法(见文献[1,2])涉及到很多核参数。因此,计算机在线数据处理非常必要。我们从美国Canbarra公司引进的PDP-11/34计算机及SPECTRAN-F程序只能满足一般谱分析的在线数据处理要求,而不能     

岩性密度测井仪的研制

此测井仪包括井下探测仪器及地面计算机数据获取与控制管理系统。此仪器的测量范围:光电因子最大为33巴/电子,体密度1.9—2.9g/cm~3。测量精度:光电因子的相对误差小于±6％,密度的绝对测量偏差<±0.03g/cm~3。井下仪器能在井深3500m下正常工作。     

铜版纸涂布量在线测量仪

铜版纸涂布量在线测定仪采用TP-801单板计算机处理数据,能直接数码显示和打印单位面积的涂布量(g/m~2),仪器测量时间10s,在线测量重复性为±1g/m~2,与称重法相对误差为±5％。     

放射免疫分析的离线自动分析系统

在核医学测量系统中,经常要对所测数据进行各种处理,这往往是很烦琐的,有的用手工计算甚至难于实现。如使用计算机,可以方便地进行各种处理,并能迅速给出处理结果。 在核医学测量领域内,与其它不少测量领域一样,常遇到的数据可分为模拟和数字两大类。这两类数据,计算机都无法直接接受,必须应用“接口”技术,将其转换成可以接受的数字信息,送入计算机才能进行处理。这就是计算机自动测量系统。     

华南花岗岩类岩石中稀土元素的仪器中子活化分析

将样品放入重水反应堆反射层内(通量4.8×10~(13)n/cm~2·s)照射8小时,用S-40多道计算机程控Ge(Li)γ谱仪进行测量,通过PDP11/34A计算机完成谱数据处理。 本工作测定了我国华南地区有代表性的9个花岗岩内10个稀土元素的含量,结果列于表,精度大约为15％。用本法同时分析了国际标样AGV-1,测定结果和文献值相比较符合良好。     

一个支持高能物理实验数据获取与数据分析的通用程序系统

本文通过对Fermilab MULTI系统的剖析,介绍一个支持高能物理实验数据获取与数据分析的通用程序系统的结构,功能及系统生成,对在PDP-11/23计算机上运行的0.5级系统的局部改造工作也作了简单介绍。     

符合装置-微计算机测量系统的建立及应用

建立了符合装置-微计算机测量系统,实现了测量数据的自动获取与处理,广泛地适用于不同衰变类型核素放射性活度的绝对测量。     

研究离子与固体相互作用的系列程序TCIS在PDP-11/70机上的应用

在表面物理领域中,经常用到Monte Carlo模拟计算程序。把TCIS程序移值到PDP-11/70计算机上将会遇到一些困难,例如,程序中的有些数组很大,超出了计算机可寻找的虚拟地址空间。本文运用虚数组和覆盖技术解决了这些问题,并给出PDP-11/70计算机上计算的一些成功算例。     

20MeV电子韧致辐射谱的阈探测法测定

对２ＯＭｅＶ能量的电子在Ａｕ靶中产生的韧致辐射谱用阈探测法进行了测量。测量数据经过计算机处理得到的结果与理论计算相一致。     

核能谱数据采集DMA接口电路

利用微机本身具有ＤＭＡ功能，研制了一种ＤＭＡ方法的核数据快速采集接口，在一个仅５片组件的硬件接口支持下，配置相应软件便可实现核能谱的快速采集。     

Benchmarking of JEFF-3.2, FENDL-3.0 and TENDL-2014 evaluated data for tungsten with 14.8 MeV neutrons

Integral experiments on tungsten slab samples were carried out on the D-T neutron source facility at China Institute of Atomic Energy.Leakage neutron spectra from the irradiated tungsten target were measured by the time-of-flight technique.Accuracy of the nuclear data for tungsten was examined by comparing the measured neutron spectra with the leakage neutron spectra simulated using the MCNP-4C code with evaluated nuclear data of the JEFF-3.2,FENDL-3.0 and TENDL-2014 libraries.The results show that the calculations with JEFF-3.2 agree well with the measurements in the whole energy range and all angles,whereas the spectra calculated with FENDL-3.0 and TENDL-2014 have some discrepancies with the experimental data.     

Benchmarking of JEFF-3.2, FENDL-3.0 and TENDL-2014 evaluated data for tungsten with 14.8 MeV neutrons

Integral experiments on tungsten slab samples were carried out on the D-T neutron source facility at China Institute of Atomic Energy.Leakage neutron spectra from the irradiated tungsten target were measured by the time-of-flight technique.Accuracy of the nuclear data for tungsten was examined by comparing the measured neutron spectra with the leakage neutron spectra simulated using the MCNP-4C code with evaluated nuclear data of the JEFF-3.2,FENDL-3.0 and TENDL-2014 libraries.The results show that the calculations with JEFF-3.2 agree well with the measurements in the whole energy range and all angles,whereas the spectra calculated with FENDL-3.0 and TENDL-2014 have some discrepancies with the experimental data.     

Measurements and Calculations of Angular Flux Spectra Emitted from Lithium and Graphite Slabs with D-T Neutron Source

Angular dependent flux spectra from slab assemblies (lithium and graphite) were measured to test nuclear data and calculational methods for D-T fusion reactor neutronics. The collimated 14 MeV neutron source could be applied by the use of an associated particle method and the neutron spectra from 14 to 2 MeV were observed with TOF technique. The measured spectral pattern was dependent on the anisotropy of secondary neutrons emitted from both the elastic and the non-elastic scattering for 14 MeV neutrons. As for the numerical calculations, one-dimensional discrete ordinates transport codes (ANISN and NITRAN) were used. The multigroup cross sections processed with SPTG4Z from ENDF/B-IV were used as common nuclear data base. The problems of calculational methods and nuclear data were discussed in comparison with the experimental data and it was clarified that sufficient nuclear data of angular dependent cross sections for the non-elastic scattering have not been available in ENDF/B-IV and that the anisotropy of the scattering could not be calculated with ANISN which utilized the scattering kernel generated by incorrect treatment of scattering kinematics in the processing code. However, good agreement between the measurements and calculations was obtained by the use of NITRAN system with the appropriate processing codes of inelastic scattering anisotropies. It was shown that the NITRAN system was useful for anisotropic neutron transport calculations.     

Use of new ENDF/B-VI proton and neutron cross sections for singleevent upset calculations

Single-event upsets (SEU) in microelectronics are calculated from newly-developed silicon nuclear reaction recoil data for incident protons and neutrons with energies up to 150 MeV. This paper focusses on the nuclear reaction physics that is important for calculating recoil spectra, and burst generation rate spectra. Comparisons are made with previous results, obtained from intranuclear cascade calculations as well as from previous ENDF data below 20 MeV, to demonstrate new features in the present calculations. Calculated SEU cross sections are compared with measured data     

镓样品泄漏中子谱的测量与分析

基于中国原子能科学研究院的中子学积分实验装置,利用BC501A液体闪烁体探测器,结合飞行时间法（TOF）测量了镓样品的泄漏中子谱。采用MCNP 4C程序进行了模拟并与实验泄漏中子谱进行了比较,对ENDF/B-Ⅶ.1、JEFF-3.2、TENDL-2015数据库中镓核中子评价数据进行了宏观基准检验分析,并与TALYS程序计算结果作对比。研究结果显示：在9 MeV以下能区,TENDL-2015库与实验结果符合很好;在弹性散射能区,JEFF-3.2和TENDL-2015库与实验结果符合较好;对于12 MeV左右的非弹性散射峰,JEFF-3.2库与实验结果符合较好,TALYS计算结果显示该部分主要来自镓核分离能级的贡献。     

Extension of a nuclear reaction calculation code CCONE toward higher incident energies — multiple preequilibrium emission,and spectrum in laboratory system

A nuclear reaction calculation code CCONE, which was developed for nuclear data evaluation for JENDL/AC-2008 and JENDL-4, has been upgraded to improve the prediction accuracy for calculated cross sections at nucleon incident energies higher than 20 MeV. Multiple particle emission, in which nucleons and complex particles up to α-particle are involved, from pre-equilibrium reaction process was implemented based on the sequential-decay calculations for all produced exciton states within the framework of the two-component exciton model. The effect of velocity-change of particle-emitting nuclei on the multiple emission in preequilibrium and compound processes, which was not included in the previous evaluations, was taken into account to obtain spectra in the laboratory system using an average velocity approximation for each composite/compound nucleus. Calculated nucleon emission spectra at nucleon incident energies from 20 to 200 MeV were compared with experimental and evaluated data for the proton- and neutron-induced reactions on ²⁷Al. The present results are in good agreement with experimental data. It was found that their predictions were better than those of JENDL/HE-2007 especially for low emission energies at high incident energies.     

Theoretical calculations and evaluations of n+23Na reaction

The data for neutron-induced reactions are indispensable in a lot of applications of nuclear science and technologies. All reaction cross sections, angular distributions, energy spectra, and double-differential cross sections of neutron, proton, deuteron, triton, and alpha-particle emissions are consistently calculated and analyzed for n+~(23)Na reactions at incident neutron energies below200 Me V, based on nuclear theoretical models. The calculated results are compared with the experimental data and the evaluated data in the ENDF/B-VII, JENDL-4.0,and JEFF-3.2 libraries. In most cases, the calculated results describe the corresponding experimental data well. At the resonance energy region, evaluated experimental data are adopted to fit to the resonance structures.     

中能中子与60Ni反应的理论计算和分析

在中子与⁶⁰Ni反应的总截面、去弹性散射截面和弹性散射角分布的实验数据基础上,获得了入射中子能量0.456~150MeV范围内的一组普适的中子与⁶⁰Ni反应的光学模型势参数。利用光学模型、宽度涨落修正的Hauser-Feshbach理论、预平衡反应的激子模型和核内级联模型的中能核反应计算程序UNF和MEND,计算了中子与⁶⁰Ni反应的所有截面、角分布和能谱,并将理论计算结果与实验数据和评价数据进行了分析比较。     

Earthquake response analysis for a BWR nuclear power plant using recorded data

In the dynamic analysis of complicated structures such as nuclear power plants, it is necessary to consider different damping characteristics for each structural element.

The authors have developed a computer program for the dynamic analysis based on the internal viscous damping theory and have recently performed a vibration test and earthquake observations of an actual nuclear power plant. The data resulting from the test and observation were applied to the program and the dynamic response of each part of the plant was computed.

A close agreement was noted between the computed and recorded acceleration-time histories as well as acceleration-response spectra. The authors conclude that their analyzing system might be one of the most reliable methods for the design of the nuclear power plants.