单粒子效应辐射模拟实验研究进展

应用质子直线加速器进行了静态随机存取存储器(SRAM)的单粒子效应模拟实验研究.采用金箔散射法降低质子束流,研制了弱流质子束测量系统,测量散射后的质子束流,实验测得SRAM质子单粒子翻转截面为10-14 cm2/bit量级.利用重离子加速器和锎源进行了SRAM的单粒子效应实验.研究其单粒子翻转截面与重离子线性能量传输(LET)值的关系,得到了单粒子翻转阈值和饱和截面.实验表明252Cf源单粒子翻转截面与串列加速器的重离子单粒子翻转截面一致,说明对于SRAM,可以用252Cf源替代重离子加速器测量单粒子翻转饱和截面.与中国原子能研究院、东北微电子研究所合作开展了国内首次重离子微束单粒子效应实验.建立了大规模集成电路重离子微束单粒子效应实验方法,找到了国产SRAM的单粒子翻转敏感区.应用14MeV强流中子发生器进行了SRAM单粒子效应实验,测得了64K位至4M位SRAM器件14MeV中子单粒子翻转截面.用α源进行SRAM单粒子效应辐照实验,模拟封装材料中的232Th和238U杂质发射出的α粒子导致的单粒子翻转.测量α粒子射入SRAM导致的单粒子翻转错误数,计算单粒子翻转截面和失效率,比较三种器件的抗单粒子翻转能力,为器件的选型提供依据.并开展了路由器的α粒子辐照实验,复演了路由器在自然环境中的出错情况,为路由器的设计改进提供了依据.     

SRAM单元中子单粒子翻转效应的Geant4模拟

应用Geant4工具,构造了不同特征尺寸的SRAM单元几何模型及单粒子翻转截面计算模型,分析了敏感体积和临界电荷对低能中子单粒子翻转效应的影响趋势,计算了反应堆裂变中子谱辐射环境下,不同特征尺寸SRAM的中子单粒子翻转截面,认为小尺寸SRAM器件的低能中子单粒子翻转效应更为严重。     

微处理器中子单粒子效应测试系统设计与试验研究

为开展微处理器的空间大气中子单粒子效应研究,以一款TI公司65 nm CMOS工艺的微处理器为研究对象,研制了一套微处理器中子单粒子效应测试系统。该测试系统可实现对被测微处理器的单粒子翻转、单粒子功能中断和单粒子闩锁效应的实时监测。利用加速器中子源,对该微处理器开展14 MeV中子辐照试验。试验结果表明,中子注量累积达3?5×1011 cm-2时,该器件未发生单粒子锁定效应。但总线通信、模数转换等功能模块发生了多次单粒子功能中断,其中集成总线通信接口模块为最敏感单位,试验获得的器件中子单粒子效应截面为6?6×10-11 cm2。     

高能电子单粒子效应模拟实验研究

本文基于2 MeV自屏蔽电子加速器和10 MeV电子直线加速器,开展了电子单粒子效应实验研究,并分析了其机理。在保持入射电子能量不变的情况下,在±20%范围内改变器件的工作电压进行了单粒子翻转实验。实验结果表明：45 nm SRAM（额定工作电压1.5 V）芯片在电子直线加速器产生的高能电子照射下能产生明显的单粒子翻转,单粒子翻转截面随入射电子能量的变化趋势与文献数据相符合;电子引起的单粒子翻转截面随器件工作电压的变化趋势与理论预期一致,即工作电压越小,单粒子翻转临界电荷越小,翻转截面也越高。     

用于单粒子效应辐照实验的CYCIAE-100白光中子源研究

中子诱发单粒子效应会影响航空飞行器和地面核设施用电子器件的可靠性。基于质子加速器打靶产生的白光中子束是研究电子器件中子单粒子效应的重要中子源。通过开展辐照实验获取器件中子单粒子效应截面或阈值等信息,能够预测器件在中子辐射环境中的失效率,并为有针对性抗辐射加固提供数据支撑。中国原子能科学研究院100 MeV质子回旋加速器(CYCIAE-100)通过质子轰击W靶发生散裂反应可以产生具有连续能量的白光中子。本文基于核反应理论,采用蒙特卡罗方法模拟了100 MeV质子与W靶相互作用产生的中子的产额、能谱和角分布,模拟结果表明,平均1个100 MeV质子可以产生0.33个中子;中子能量范围为0～100 MeV,且随着能量的增加中子注量先增加后减小,峰值在1 MeV附近;沿质子束方向中子角分布具有轴对称性,且随着出射角的增加,中子注量先减小后增加,在90°时,中子注量最小。选取0°出射方向的中子束开展单粒子效应实验,采用基于双液闪探测器的中子飞行时间法测量白光中子能谱,获得了能量范围为3～100 MeV的中子能谱,且当质子束为100 MeV/1μA时,在距离W靶15 m处的中子注量率为3.3×10...     

不同特征尺寸SRAM质子单粒子效应实验研究

利用中国原子能科学研究院100 MeV质子回旋加速器开展了一系列不同特征尺寸双数据速率（DDR）静态随机存储器（SRAM）单粒子效应实验研究。获得了不同能量、不同入射角度下3款SRAM的单粒子翻转（SEU）截面曲线。分析了入射质子能量及角度对不同特征尺寸SRAM的SEU饱和截面的影响和效应规律,并利用蒙特卡罗方法对65 nm SRAM SEU特性进行了模拟。研究结果表明：随特征尺寸的减小,SEU饱和截面会出现不同程度的降低,但降低程度会由于多单元翻转（MCU）的增多而变缓;随入射角度的增加,MCU规模及数量的增加导致器件截面增大;3款SRAM所采用的位交错技术并不能有效抑制多位翻转（MBU）的发生。     

不同特征尺寸SRAM质子单粒子效应实验研究

利用中国原子能科学研究院100 MeV质子回旋加速器开展了一系列不同特征尺寸双数据速率(DDR)静态随机存储器(SRAM)单粒子效应实验研究。获得了不同能量、不同入射角度下3款SRAM的单粒子翻转(SEU)截面曲线。分析了入射质子能量及角度对不同特征尺寸SRAM的SEU饱和截面的影响和效应规律,并利用蒙特卡罗方法对65 nm SRAM SEU特性进行了模拟。研究结果表明:随特征尺寸的减小,SEU饱和截面会出现不同程度的降低,但降低程度会由于多单元翻转(MCU)的增多而变缓;随入射角度的增加,MCU规模及数量的增加导致器件截面增大;3款SRAM所采用的位交错技术并不能有效抑制多位翻转(MBU)的发生。     

FLASH ROM 28F256和29C256的14 MeV中子辐照实验研究

给出了国内首次FLASH ROM器件的中子辐照效应实验研究结果。发现28F256和29C256器件的14 MeV中子辐照效应不同于以往所认为的单粒子效应,它只有“0”→“1 ”错误。错误发生有个中子注量阈值,当中子注量小于某一个值时,无错误; 当中子注量达到一定值时,开始出现错误。随着中子注量的增加,错误数增加,直到所有“0”变为“1”。 动态监测和静态加电的器件都出现硬错误,不能用编程器重新写入数据。错误随读取次数的增加而增加。在相同的中子注量下,不加电的器件无错误,而加电的器件都出现错误,并且出现不确定性错误。     

利用Geant4模拟研究中子在半导体中引发的单粒子翻转效应

静态随机存储器在反应堆中子辐射环境中会发生单粒子翻转(Single event upset,SEU)。钨和铜等重金属作为局部互联,在半导体中已得到广泛应用,这些重金属对中子在半导体中的单粒子翻转截面会产生影响。不同条件下单粒子翻转截面与临界能量的关系可作为器件设计和使用时的参考,利用Geant4对特定中子能谱在CMOS(Complementary metal oxide semiconductor)器件中的能量沉积进行模拟,给出特定能谱下翻转截面σ与临界能量Ec的关系:σ=exp[-18.7×Ec-32.3],其中能量单位为Me V,截面单位为cm2。并且模拟了1-14 Me V的单能中子在含有互联金属钨及不含钨的CMOS中的沉积能量及单粒子翻转截面,得出在1-14 Me V内单粒子翻转截面随中子能量而增大,且钨的存在会增加α粒子的产额,从而增大了1-3 Me V中子的单粒子翻转截面,而对4-14 Me V中子基本不会产生影响。     

65nm三阱CMOS静态随机存储器多位翻转实验研究

利用4种不同线性能量转换值的重离子对一款65nm三阱CMOS静态随机存储器(SRAM)进行重离子垂直辐照实验,将多位翻转图形、位置和事件数与器件结构布局结合对器件单粒子翻转截面、单粒子事件截面及多位翻转机理进行深入分析。结果表明,单粒子事件截面大于单个存储单元内敏感结点面积,单粒子翻转截面远大于单个存储单元面积。多位翻转事件数和规模的显著增长导致单粒子翻转截面远大于单粒子事件截面,多位翻转成为SRAM单粒子翻转的主要来源。结合器件垂直阱隔离布局及横向寄生双极晶体管位置,分析得到多位翻转主要由PMOS和NMOS晶体管的双极效应引起,且NMOS晶体管的双极效应是器件发生多位翻转的主要原因。     

~(115)In中子非弹性散射截面的实验测量及蒙特卡罗修正

~(115)In是一种重要的活化材料,准确测量它的中子非弹性散射截面数据对中子注量监测具有重要意义。在四川大学原子核科学技术研究所2.5 MV静电质子加速器上,利用核反应D(d,n)~3He产生的单能中子,以~(197)Au作为标准,采用活化法测量了2.95 Me V、3.94 Me V、5.24 Me V能点的~(115)In中子非弹性散射截面。用Monte Carlo程序MCNPX(Monte Carlo N-Particle eXtended)对靶头材料、冷却水层和样品的包层材料等引起的多次散射效应及注量率衰减效应等进行了修正计算,得到最终结果与Loevestam的计算值符合较好,并且实验中可通过减小靶管、靶底衬、水层及样品的包层材料等厚度来减小多次散射效应和自屏蔽效应的影响。     

Measurement of Leakage Neutron Spectra from a Spherical Pile of Zirconium Irradiated with 14MeV Neutrons and Validation of Its Nuclear Data

In order to make a benchmark validation of the nuclear data for Zr, the leakage neutron spectrum from a Zr sphere of a 61-cm diameter was measured between 0.1 and 16MeV using a time-of-flight technique with a 14MeV neutron source facility, OKTAVIAN. The result was compared with the calculation using the Monte Carlo code MCNP-4A. To investigate the spectrum dependence on the individual neutron reactions, test calculations were carried out with the MCNP-4A code using the JENDL-3.2-based libraries, in which partial cross section values were reduced from the original values. From the comparison between the measured and the calculated spectra, it was found that each of the results could predict well the experiment in general. However, in detail, both ENDF/B-VI and EFF-2.4 gave considerable overestimation above 1 MeV. The JENDL-3.2 predicts the spectrum almost satisfactorily except below 0.8 MeV and around 10 MeV. The discrepancy found in JENDL-3.2 calculation is considered due to the cross section values of the (n, 2n) reaction and its secondary energy distributions (SED). The modified JENDL-3.2 library with the reduced (n, 2n) reaction values and the lower SED below 1 MeV reproduced the experiment with better agreement over the whole energy range.     

活化法测量197Au等核素的14MeV中子反应截面

采用活化法测量了197Au等核素的14MeV中子反应截面.当入射中子能量为14.75MeV时,197Au(n,2n)196Au反应截面测量结果为(2175±76)×10-31m2,并与其他测量结果和ENDF/B-6评价数据库数据进行了比较.对于结果的一些不确定度因素,采用MCNP程序进行了分析.     

Theoretical estimates of cross sections for neutron–nucleus collisions

We construct an analytical model derived from nuclear reaction theory and having a simple functional form to demonstrate the quantitative agreement with the measured cross sections for neutron induced reactions. The neutron–nucleus total, reaction and scattering cross sections, for energies ranging from 5 to 700 MeV and for several nuclei spanning a wide mass range are estimated. Systematics of neutron scattering cross sections on various materials for neutron energies up to several hundred MeV are important for ADSS applications. The reaction cross sections of neutrons are useful for determining the neutron induced fission yields in actinides and pre-actinides. The present model based on nuclear reaction theory provides good estimates of the total cross section for neutron induced reaction.     

Measurement and Analysis of Neutron Spectra in Lithium Fluoride and Polytetrafluoroethylene Piles

For the assessment of neutron cross section data for fluorine, angular neutron spectra in the lithium fluoride (LiF) and polytetrafluoroethylene ((CF₂)n) piles were measured in the energy range from a few keV to a few MeV by the time-of-flight method with an electron linac, and the results were compared with those calculated by using nuclear data from JENDL-2 and ENDF/B-IV. Spatial distributions of neutron and X-ray fluxes were also measured in the test piles by the activation method, and the influence of photoneutrons generated in the sample material on the neutron spectrum in each pile was estimated. As a result, it was found that their influence on the neutron spectrum shape below 1 MeV was not so large as was necessary to be taken into account for the present assessment.

The calculated spectra using the JENDL-2 data and the ENDF/B-IV data show generally good agreement with those measured in both piles. However, both calculations underestimate the neutron fluxes around several 100 keV, and overestimate those below 100 keV, when they are normalized in the energy range of 10 keV～1 MeV. Large discrepancies are found between the shapes of the measured and calculated spectra around the resonances of fluorine cross section below 100 keV. The present measurements and analyses suggest that the reevaluations of the inelastic and elastic scattering cross sections below 1MeV and the resonance cross sections below 100 keV are necessary to reduce the observed discrepancies.     

Analysis of (n, 2n) multiplication in lead

Lead is being considered as a possible amplifier of neutrons for fusion blankets. A simple one-group model of neutron multiplications in Pb is presented. Given the 14 MeV neutron cross section on Pb, the model predicts the multiplication. Given measured multiplications, the model enables the determination of the (n, 2n) and transport cross sections. Required for the model are: P—the collision probability for source neutrons in the Pb body—and W—an average collision probability for non-virgin, non-degraded neutrons. In simple geometries, such as a source in the center of a spherical shell, P and an approximate W can be expressed analytically in terms of shell dimensions and the Pb transport cross section. The model was applied to Takahashi's measured multiplications in Pb shells in order to understand the apparent very high multiplicative power of Pb. The results of the analysis are not consistent with basic energy-balance and cross-section magnitude constraints in neutron interaction theory.     

~(176)Hf(n,2n)~(175)Hf反应截面测量

采用相对测量技术,以活化法对13.4～14.8MeV范围内的176Hf(n,2n)175Hf反应截面进行了测量。样品固定在距离D-T中子源20cm处的圆环的不同位置上进行中子辐照,采用93Nb(n,2n)92Nbm作为监测反应,活化产物采用高纯锗探测器进行了测量,所得14MeV附近的176Hf(n,2n)175Hf反应截面实验值为(2100±85)mb,对实验结果与公开文献值和ENDF/B6.8评价库数据进行了比对。     

Calculated neutron cross sections for Cu and Nb up to 32 MeV for neutron damage analysis

Cross sections for neutron interaction with Cu and Nb, with emphasis on spectra of light particles from binary reactions, are calculated for neutron energies from 4 to 32 MeV for estimating recoil probability densities for the analysis of damage experiments with a Be (d, n) neutron source. Nuclear model parameters were adjusted to reproduce the available cross-section data around 14 MeV. Helium production cross sections were also calculated for ⁶³Cu for neutrons below 20 MeV, as an illustration of the Hauser-Feshbach method for calculating tertiary reaction cross sections.