高产额脉冲堆爆发脉冲过程力学特性数值模拟

脉冲堆的性能主要受机械冲击引起的物理损伤的限制。高产额脉冲堆比CFBR-Ⅱ等金属铀脉冲堆追求更窄的脉冲宽度和更高的裂变产额,脉冲过程应力变化更加剧烈。为了获得高产额脉冲堆爆发脉冲过程中应力应变的分布,为新型脉冲堆设计和安全分析提供技术支持,基于圆柱型的铀钼合金快中子脉冲堆Godiva Ⅳ,以点堆方程以及MC(蒙特卡罗)方法对其中子产额以及功率分布进行了计算。并建立了快中子脉冲堆Godiva Ⅳ的三维模型,基于已知功率分布条件,利用有限元计算软件ANSYS Mechanical对其脉冲动态过程进行了瞬态的有限元计算,得到了Godiva Ⅳ圆柱型金属燃料在超临界脉冲爆发条件下的应力响应特性。     

脉冲γ射线对光纤的辐射效应

介绍了光纤的损耗机制和γ射线对光纤的辐射效应,设计了针对脉冲γ射线作用于光纤而产生辐射感生损耗的实验测量系统。利用平均光子能量为0.3 MeV、脉冲宽度25 ns、剂量率2.03×107Gy.s-1,和平均光子能量为1.0 MeV、脉冲宽度25 ns、剂量率5.32×109Gy.s-1的2种脉冲γ射线分别作用于多模和单模光纤,分别采用波长为405,660,850,1 310和1 550 nm的激光光纤传输系统对辐射感生损耗进行了测量。获得了光纤辐射感生损耗和辐射剂量的关系,并对实验结果进行分析。从实验结果可以看出:在近红外到可见光范围内,脉冲γ射线对光纤作用产生的辐射感生损耗随探测波长减小而增大;在0.1~3.5 Gy剂量范围内,多模光纤辐射感生损耗和辐射剂量呈线性关系。分析辐射对光纤的作用机制和实验结果后得出:光纤基质原子的电子能级对传输光子的共振吸收而造成吸收损耗增加;光纤折射率分布的改变从而导致波导损耗增加。     

射线引起DNA双链断裂的统计分布

辐射过程引起的生物细胞的DNA双链断裂是一种很重要的细胞损伤过程.射线在细胞中能量沉积比较大时,DNA双链断裂的碎片分布会偏离随机断裂模型给出的结果,为此发展了新的模型分析方法-统计碎裂模型.根据统计物理学的原理和方法，放射性射线照射细胞后，将射线的能量传递给细胞中的DNA分子，当沉积的能量比较大时，体系会经过一个弛豫过程，DNA碎片大小l按照统计规律分布.体系熵值取极大的分布是最可几的分布，从而得到了辐射导致DNA双链断裂后碎裂片段随其大小l的分布函数exp(αl+βl²)，它对应于 两种成分，一种成分随碎裂片段的大小l的增大而迅速减小，这对应于分布函数中的exp(βl ²)项，对于质量比较小的碎裂片段，这种成分是主要贡献；另外一种成分随碎 裂片段的大小l的增大而缓慢减小，这对应于分布函数中的exp(αl)项，对于质量比较大的 碎裂片段，这种成分是主要贡献.根据实验所测的碎裂片段分布，通过数值解法解积分方程 ，将热力学参数α，β解出，与实验结果进行比较，实验的结果支持了DNA双链断裂后碎裂 片段分布的统计碎裂模型. 关键词： 熵 统计碎裂模型 DNA双链断裂     

不同LET辐射致DNA集簇性损伤的研究

利用辐照质粒DNA构象变化的分子模型,以DNA糖苷酶Fpg和AP核酸内切酶EndoIII识别并切割辐射所致DNA碱基损伤,将其转换为DNA断裂损伤,通过电泳分析DNA分子构象变化,研究比较γ射线、质子和7Li离子诱发DNA集簇性损伤。50Gy以上高剂量γ辐射对质粒DNA的损伤主要表现为单链断裂(SSB)和很少比例的双链断裂(DSB),并能产生一定水平的集簇性损伤。相比之下,高能质子束和高LET的7Li离子直接所致DNA的断裂损伤以及所产生的集簇性碱基损伤比γ射线的要严重,质子10Gy照射就可诱发明显的集簇损伤。     

γ射线诱导DNA损伤中DNA浓度和剂量率的影响

在进行辐射致DNA损伤中, DNA浓度和剂量率是两个重要的因素。 利用γ射线在不同的剂量率下对不同浓度的质粒DNA pUC19水溶液进行了辐照， 利用凝胶电泳对辐照后的样品进行分析。 结果表明， 在同一剂量下被辐照的DNA样品， 随浓度的降低DNA损伤越来越严重； 通过分析软件和理论公式得到的每个DNA上的双链断裂数随着DNA浓度的变化呈现为非线性趋势。 As two factors， the changes of concentration of DNA and dose rate are of significance in the study of DNA damage induced by irradiation. The influence of DNA damage induced by γ ray at different concentration of DNA under different dose rate was investigated. The result of gel electrophoresis indicate that DNA molecules were damaged severely as the concentration of DNA decreasing. The number of double strand breakages per DNA were obtained by the software of Alpha Innotech and theoretical analysis. It shows that the numbers of double strand breakages per DNA presented nonlinear feature as the concentration of DNA decreasing, and the dose rate had little influence on DNA damage.     

面向个人剂量计校准的小尺度伽玛参考辐射模拟研究

针对伽玛射线个人剂量计基于标准伽玛参考辐射进行校准时检定效率低、校准工作复杂和需要远程送检的关键技术问题,建构了1 Ci 137Cs放射源小尺度参考辐射场物理模型,采用蒙特卡罗方法,研究了小尺度参考辐射场内的剂量分布、装置结构和待检剂量计变化导致散射射线对剂量场的影响,获得了待检剂量计形状、数量、类型和装置结构产生的散射伽玛射线对小尺度参考辐射量值定度的影响结果。研究结果表明,1 Ci 137Cs可以为小尺度参考辐射辐射场检验点提供1.5 mSv/h的伽玛遂行剂量率,辐照个人剂量计载台直径30 cm束斑上的剂量率相对标准偏差约为0.48%。当载台厚度为20 mm时,散射射线对小尺度参考辐射检验点处剂量率值的影响率为3.27%,高于剂量计尺寸（1.62%）和剂量计数量（0.56%）的影响。     

基于光谱学分析的生物磷参与暹罗芽孢杆菌对铀的去除行为及机制研究

以暹罗芽孢杆菌为研究对象,它具有较高的表面积/体积比,吸附性能良好。前人关于暹罗芽孢杆菌的研究多集中在它降解纤维素淀粉或抗菌方面,关于暹罗芽孢杆菌与放射性核素的作用及机制基本未涉及。利用等离子发射光谱和等离子发射光谱-质谱研究溶液初始pH值、铀初始浓度、菌体用量等因素对暹罗芽孢杆菌去除铀的影响及作用过程中菌体释放的生物磷与铀去除的关系;利用红外光谱和扫描电镜对与铀作用前后的暹罗芽孢杆菌形貌及基团变化进行表征;利用X射线光电子能谱和扫描电镜能谱分析菌体表面元素分布情况和元素价态,进而探讨暹罗芽孢杆菌对铀的去除机制。结果表明,由于不同pH条件下暹罗芽孢杆菌生长活性、铀存在形态和磷元素释放量的不同,其对铀的去除差异很大。在pH 5.0时,暹罗芽孢杆菌对铀的去除效果最好。菌体用量增加有利于暹罗芽孢杆菌对铀的去除。对实验结果进行Langmuir和Freundlich等温吸附拟合后发现:暹罗芽孢杆菌对铀的去除行为符合Langmuir等温吸附模型;铀浓度实验获得的最大吸附量高于理论计算的最大吸附量,说明暹罗芽孢杆菌对铀的去除可能是物理和化学行为的共同作用。暹罗芽孢杆菌能够有效去除水体中的铀,实验获得的最大去除率为96.5%,最高吸附量为450.3 mg·g~(-1),高于大部分已报道的用于吸附铀的芽孢杆菌。对反应前后菌体的扫描电镜测试发现,与铀作用后暹罗芽孢杆菌表面出现鳞片状沉淀, X射线光电子能谱和扫描电镜能谱分析表明该沉淀为含磷铀物质。结合红外光谱分析,推测暹罗芽孢杆菌去除铀的机制为:首先,通过静电作用铀被快速吸引到暹罗芽孢杆菌表面,随后以配位的形式被菌体上的磷酸基团、氨基、羟基、羧基等活性基团吸附,同时与菌体释放的含磷酸盐类物质相互作用,形成含磷铀沉淀而被固定至细菌表面。在此过程中,少部分六价铀被菌体释放的胞内物质还原成四价铀而发生沉降。推测菌体表面沉淀可能为铀的磷酸盐沉淀和含磷化合物与铀的络合物形成的混合物。     

L波段微波脉冲对微型计算机的辐照效应实验

 在L波段使用1.3 GHz载波频率的微波脉冲辐照微型计算机主板,通过改变脉冲宽度、重复频率和脉冲串长度等参数,实验研究了微波脉冲辐照导致微型计算机失去响应的功率阈值的变化规律,讨论了L波段微波脉冲辐射的积累效应。实验结果表明：当微波脉冲宽度增加时,微波功率阈值下降;当微波脉冲重复频率升高时,微波功率阈值呈下降趋势;在固定重复频率的条件下,微波脉冲数目的增加也会导致微波功率阈值的下降;微波脉冲功率阈值始终小于连续波微波的功率阈值。当微波脉冲间隔时间较长或者脉冲宽度较宽时,微波功率阈值由单个微波脉冲的参数确定,与脉冲重复频率没有明显关系。利用假设的微波脉冲辐射积累效应,可以定性解释和分析微波脉冲辐照微型计算机实验中功率阈值变化的趋势。     

CCD与CMOS像素传感器γ射线电离辐射响应特性对比研究

为了研究CCD与CMOS像素传感器对γ射线电离辐射的响应差异,对比研究了4类像素传感器的结构特点和辐射响应特性。通过辐射实验,对各传感器在不同辐射水平条件下的光子响应事件分布、平均灰度值以及典型光子响应事件进行研究。研究结果表明：光子响应程度均与辐射剂量率相关;CCD像素传感器的沟道传输方式使每列像元间的辐射响应更容易相互干扰;平均灰度值随剂量率的增大存在明显的梯度,各积分周期内输出信号灰度值围绕均值上下波动,CCD像素传感器输出信号灰度浮动范围较小;CMOS像素传感器各像元对光子的响应更加明显,CCD像素传感器各像元的响应信号易与相邻像元发生串扰;各类像素传感器典型辐射响应事件区域中发生光子响应的像元数量随剂量率的增大而增多,响应事件并非单个光子的行为,而是反映了多个光子在区域内同时沉积能量的过程。本研究为开发像素传感器的γ射线辐射探测技术和应用提供了重要的理论分析和实验数据支撑。     

放射源辐射场Monte Carlo模拟计算

选取Pu-238为放射源，采用简化的级联衰变链对其进行源项分析，得到放射源各衰变子体原子数及放射性活度的变化曲线，在此基础上，采用MCNP程序，对放射源进行了精确建模，对放射源辐射场及其有效屏蔽问题进行了模拟计算，得到放射源周围中子、能谱及辐射场分布，辐射场计算值与参考实验剂量吻合较好，屏蔽体的采用可有效降低放射源的辐射剂量，其中，剂量降低为裸源的0.1%左右，中子剂量降低为裸源的13%～17%。     

Measurement of high energy neutrons by fission reactions

In most high energy radiation fields, such as those encountered around accelerators or cosmic rays in the atmosphere, neutrons produce the largest percentage of the hadron dose. In these radiation fields, the neutron spectrum is typically formed by low energy neutrons (evaporation spectrum) and high energy neutrons (knock-on spectrum).

Neutron spectrometry and dosimetry are better understood for low energy neutrons (i.e. neutrons with energy below 20 MeV) than for those of higher energies. This paper reports the study of different detectors based on the registration of fission fragments of different heavy elements (namely bismuth, gold and tantalum), which have their principal response to high energy neutrons.     

Measurement of peak fluence of neutron beams using Bi-fission detectors

Fission fragments and other charged particles leave tracks of permanent damage in most of the insulating solids. Damage track detectors are useful for personal dosimeters and for flux/dose determination of high-energy particles from accelerators or cosmic rays. A detector that has its principal response at nucleon energy above 50 MeV is provided by the fission of Bi-209. Neutrons produce the largest percentage of hadron dose in most high-energy radiation fields. In these fields, the neutron spectrum is typically formed by low-energy neutrons (evaporation spectrum) and high-energy neutrons (knock-on spectrum). We used Bi-fission detectors to measure neutron peak fluence and compared the result with the calculated value of neutron peak fluence. For the exposure to 100 MeV we have used the iThemba Facility in South Africa.     

241Am-Be中子参考辐射的蒙特卡罗模拟研究

研究用于校准场所中子剂量监测仪表的241Am-Be中子参考辐射场计量特性。采用蒙特卡罗方法模拟了空气自由中子参考辐射(FRNR),GB/T 14055规定的最小尺寸中子参考辐射(SRNR)和实际中子参考辐射(ARNR)中不同检验点处中子周围剂量当量率、散射中子占比和能谱分布特征。研究结果表明,空气对FRNR中的剂量率和能谱分布影响小,近似为理想中子参考辐射;采用5%含硼聚乙烯作屏蔽的最小尺寸SRNR可减少热中子,降低散射中子占比,影锥法不适用于小尺寸中子参考辐射中对散射中子的修正;ARNR中的散射中子更少、占比更低,影锥法所得散射中子占比与理论值基本一致。     

Atomic force microscopy of Bacillus spore surface morphology

Bacillus spore surface morphology was imaged with atomic force microscopy (AFM) to determine if characteristic surface features could be used to distinguish between four closely related species; Bacillus anthracis Sterne strain, Bacillus thuringiensis var. kurstaki, Bacillus cereus strain 569, and Bacillus globigii var. niger. AFM surface height images showed an irregular topography across the curved upper surface of the spores. Phase images showed a superficial grain structure with different levels of phase contrast and significant differences in average surface morphologies among the four species. Although spores of the same species showed similarities, there was significant variability within each species. Overall, AFM revealed that spore surface morphology is rich with information, which can be used to distinguish a sample of about 20 spores from a similar number of spores of closely related species. Statistical analysis of spore morphology from a combination of amplitude and phase images for a small sample allows differentiation between, B. anthracis and its close relatives.     

Analysis of the relationship between neutron dose and Cerenkov photons under neutron irradiation through Monte Carlo method

To theoretically explore the feasibility of neutron dose characterized by Cerenkov photons, the relationship between Cerenkov photons and neutron dose in a water phantom was quantified using the Monte Carlo toolkit Geant4. Results showed that the ratio of the neutron dose deposited by secondary electrons above Cerenkov threshold energy to the total neutron dose is approximately a constant for monoenergetic neutrons from 0.01 eV to 100 eV. With the initial neutron beam energy from 0.01 eV to 100 eV, the number of Cerenkov photons has a good correlation with the total neutron dose along the central axis of the water phantom. The changes of neutron energy spectrum and mechanism analysis also explored at different depths. And the ratio of total neutron dose to the intensity of Cerenkov photons is independent of neutron energy for neutrons from 0.01 eV to 100 eV. These findings indicate that Cerenkov radiation also has potential in the application of neutron dose measurement in some specific fields.     

重离子加速器示范装置被动式束流配送系统次级中子特征的蒙特卡罗研究

在碳离子放射治疗中,碳离子束在剂量配送过程中会与束流输运线相互作用,形成以中子辐射为主的外辐射场.由于中子是高LET射线,具有较高的相对生物学效应,减少碳离子放疗中产生的次级中子有助于降低放疗后正常组织并发症几率及二次肿瘤风险.利用蒙特卡罗方法对保守情况(能量为400 MeV/u,多叶光栅完全闭合)下碳离子治疗被动式束...     

Prompt gamma radiation from fission fragments due to the Strutinsky-Denisov polarisation

The hard electric dipole radiation from fission fragments of ²³⁵U by thermal neutrons is predicted. The radiation arises due to the Strutinsky-Denisov-induced polarisation mechanism. The probability of the radiation is at the level of 0.0025 per fission, which is in agreement with experiment. The angular distribution exhibits left-right asymmetry with respect to the plane perpendicular to the neutron polarisation axis. That means that the emission of gamma quanta at the given angle depends on the neutron polarisation. The asymmetry is at the level of 10^-3. This effect is similar to that observed earlier for gamma quanta in binary and alphas in ternary fission. The study of this effect will give information about dissipation of the collective energy of the surface vibration in fragments with large amplitude, and gives a picture of the process of snapping back the nuclear surface.     

Iterative unfolding for Bonner sphere spectrometers using the MSANDB code – Sensitivity analysis and dose calculation

Since many decades, Bonner sphere spectrometers (BSSs) are routinely used for assessment of neutron spectra over a wide energy range from some meV to GeV. Typically, a spectrometer consists of a neutron detector sensitive to thermal neutrons located inside moderating polyethylene (PE) spheres of various sizes. Based on the response functions of the detector/sphere systems that must be calculated by Monte Carlo codes, an unfolding procedure is applied to deduce the present neutron spectrum from the count rates of the detectors. To start the unfolding procedure, a guess spectrum is required that includes some prior information on the physics of the investigated neutron spectrum, and that is iteratively modified to match the measured count rates. For the present investigation, a BSS-system consisting of an ³He proportional counter and seventeen spheres containing PE or a combination of PE and lead is used. The system is used for example to measure secondary neutrons from cosmic radiation at mountain altitudes, or from high-energy accelerators outside the radiation shielding. A systematic study was performed to quantify the influence of the chosen guess spectrum and the number of iteration steps on the unfolded neutron spectrum, and on integral quantities deduced such as total neutron fluence or ambient dose equivalent. It turned out that none of these changes resulted in dose quantities that were more than a few percent different to those deduced when the optimised start spectrum was used. Similarly, use of the two different response matrices available for our BSS system provided similar values for the ambient dose equivalent.