低能离子注入植物种子深度的研究

为了研究种子内部空洞大小对注入离子穿行深度的影响,基于注入离子穿行过程的随机性及与植物种子内靶原子碰撞的微观过程,建立注入离子在植物种子内穿行过程的非平衡统计理论模型,求解与广义朗之万方程等价的Fokker-Planck方程,得到穿行深度概率密度分布函数。在此基础上,计算出注入离子与不同靶原子碰撞所走的平均穿行深度并进行比较,分析种子内部涨落的存在、引起的注入离子平均穿行深度的变化及植物种子内部空洞占不同体积比时对注入离子穿行深度概率密度的影响等。以入射能量为30 ke V的N~+注入到植物种子糙米中为例,计算了平均穿行深度,比较了空洞大小对N~+穿行深度的影响。结果表明:糙米种子内部空洞体积越大,N~+的穿行深度越大。     

Au离子注入花生种胚深度的研究

使用金属蒸汽真空孤离子源（MEVVA源）离子注入机对花生种胚进行Au离子的注入，采用卢瑟福背散射（RBS）和X射线能谱分析（EDAX）法测量Au元素在花生种子中的深度分布，并观察注入前后的样品形貌。结果表明，由于样品表面粗糙，RBS不适于测量Au元素在花生种子中的浓度分布，而EDAX的测量则显示Au元素在花生种子的最大穿透深度可达15μm。另外本文还讨论了离子注入的诱变机理。     

HL-1M弹丸注入实验中等离子体的约束改善特征和中心磁流体动力学特性研究

在HL-1M实验中,多发弹丸注入到欧姆加热放电中,明显改善了等离子体约束特性。与相同条件下的欧姆加热放电相比,能量约束时间提高了约30％。等离子体约束的改善是因为弹丸注入后在等离子体中心区域形成了高度峰化的密度和压强分布。实验发现弹丸穿透的深度决定了密度和压强分布的峰化程度,而等离子体中心的磁流体力学活性义随着     

SGTR事故下气泡穿透深度模拟实验

蒸汽发生器传热管破裂(SGTR)后,气泡在冷却剂中的穿透深度影响铅基冷却反应堆的安全运行。针对中国铅基反应堆SGTR事故,实验营造不同气体泄漏量,利用高速摄影技术对气泡在水介质中的穿透深度特性进行了模拟实验研究。观察了气泡流动流型演化全过程,得到了气泡流型及穿透深度的初步实验数据,并推导出气泡无量纲穿透深度与弗劳德数间的准则关系式,在弗劳德相似准则基础上该关系式可应用于密度比小的气泡在液态金属冷却剂中的注入过程。实验结果表明,在破口面积一定的条件下,气泡穿透深度与气体初始速度呈正比。由量纲分析得到气泡穿透深度关系式与文献的实验结果吻合较好。     

特征X射线能谱法测定Fe^＋注入小麦种子的深度

用１１０ｋｅＶ Ｆｅ＾＋离子束垂直注入小麦种胚后，在扫描电子显微镜上沿种子纵沟剖面，在不同深度上测量Ｆｅ元素被激发出的特征Ｘ射线强度分布，结果表明分布呈指数衰减，与晶体中的热扩散分布相类似，并对此进行了讨论。     

HL-1M弹丸注入实验中等离子体的约束改善特征和中心磁流体动力学特性研究(英文)

在HL-1M实验中,多发弹丸注入到欧姆加热放电中,明显改善了等离子体约束特性。与相同条件下的欧姆加热放电相比,能量约束时间提高了约30％。等离子体约束的改善是因为弹丸注入后在等离子体中心区域形成了高度峰化的密度和压强分布。实验发现弹丸穿透的深度决定了密度和压强分布的峰化程度,而等离子体中心的磁流体力学活性又随着密度和压强分布的峰化程度的增大而改变。另一方面,等离子体中心磁流体动力学(MHD)活性在限制可达到的中心等离子体压强和决定中心输运特性上起着重要作用,标志着弹丸注入约束改善的峰化的密度、压强分布在出现第一个大锯齿后平化。随着弹丸穿透的加深,芯部区域的压强(密度)梯度变陡,中心MHD活性受到弹丸注入的强烈影响,锯齿崩溃特征有在更高密度、更高压强下时才出现的类理想模的特性,并在崩溃过程中m=1模的发展与一个非常定域的压强扰动耦合。     

弹丸注入对HL-1M装置等离子体MHD行为及电流密度分布的影响

弹丸注入所引起的等离子体响应与注入前等离子体本身的条件和状态、扰动参数以及弹丸穿透深度有关。我们曾对弹丸注入后的等离子体MHD行为及约束性能进行了研究。本文主要根据PIN光二极管阵列探测器所探测到的1～10keV能量的软X辐射扰动,定性分析多发弹丸注入对HL-1M     

掠入射质子荧光分析技术研究

首次提出采用掠入射质子荧光分析(PIXE)方法对表面存在污染的铝片、注入铁离子的单晶硅片以及注入氧隔离SOI半导体材料进行了分析.实验结果表明,现有PIXE分析技术不需要对设备做任何重大的升级改造,只是简单的采用掠入射方法,就能有效提高其表面分析的灵敏度.通过研究不同角度时峰面积与探测限之比与穿透深度之间的关系,得出质子柬在样品中的穿透深度越浅,峰面积与探测限的比值就越大,可检测的表面污染的灵敏度就越高.     

HL-1M装置弹丸穿透特性的分析

在HL-1M装置氢弹丸注入实验中,通过观测注入截面中的氢原子的H_α线发光强度对时间和空间的变化,在对几十发不同直径的弹丸注入方法进行分析的基础上,重点研究了氢弹丸的穿透特性、注入深度与弹丸速度之间的关系。 Spitzer于1954年就提出了采用弹丸注入方法对等离子体进行加料的设想,但时隔20年后,这种设想才引起人们的关注。由于弹丸注入加料效率高,且为控制等离子体密度提供了灵活性,而用中性气     

花岗岩体单裂隙中核素迁移数学模型Ⅱ.脉冲注入实验解析模型

研究了在饱和水流条件下,花岗岩单裂隙中脉冲注入核素迁移的数学模型,给出了脉冲注入情况下裂隙和岩块中核素浓度分布的解析解;结合裂隙中流出液样浓度的穿透曲线,给出了核素迁移的有关参数,并对影响这些迁移参数的主要因素进行了分析。     

Preparation of Zn/TiO2 powder and its photocatalytic performance for oxidation of P-nitrophenol

Zn-doped TiO2 catalysts were prepared using a sol-gel method and characterized by XPS,UV-Vis, BET, XRD in this study. Under the irradiation of simulant sunlight, the photocatalytic activity for the degradation of p-nitrophenol was studied too. After irradiation for 2.5 h, the degradation percentage of p-nitrophenol could rise to more than 80 %. The results showed that the spectrum absorption band edge of Zn/TiO2 powder does not broaden obviously comparing with pure TiO2 powder. Zinc exists as Zn （11）. When calcined at 973 K, there is a new phase as ZnTiO3 in Zn/TiO2 catalyst. The order of photocatalytic activity of Zn/TiO2 catalysts calcined at different temperatures for p-nitrophenol is 773 K 〉 673 K 〉 873 K 〉 573 K 〉 973 K and the photocatalytic activity of Zn/TiO2 catalyst calcined at 773 K is better than TiO2 catalysts heated at the same temperature, and outclasses that of commercial TiO2 catalyst. It also showed that the photocatalytic degradation of p-nitrophenol follows first-order kinetics under the irradiation of simulant sunlight.     

Current status of radiation therapy for prostate cancer

Radiotherapy for the treatment of prostate cancer has been extensively explored in the past. Along with the comprehensive understanding of the biology of prostate cancer and rapid advances in terms of technology, the out- come of treatment for the patients with prostate cancer has improved. The authors review radiotherapy as the primary treatment for the disease, with particular emphasis on the technological advances from both the radiobiological and radiophysics aspects. Nonconventional fractionated irradiation like hyper- or hypo-fractionation has been imple- mented in the clinic, the final results still need to be confirmed in the future. Technological advances like IMRT, IGRT, in the last two decades have significantly improved the delivery of external radiotherapy to the prostate. This has re- sulted in an overall increase in the total dose that can be safely delivered to the prostate, which has led to modest im- provements in the biochemical outcome. However, establishing the standard therapy for prostate cancer remains con- troversial. It is hoped that the next decades will bring continued advances in the development of biologicals that will further improve current clinical outcomes.     

The control system for SSRF injection and extraction

This paper introduces the injection and extraction control system design for SSRF,which is a distributed control system aimed at stability and reliability of the pulse power supplies,PPS(Personnel Protection System)and MPS(Machine Protection System).The hardware environment is mainly based on PLC(Programmable Logic Con- troller),and ARM(Advanced RISC Machine)is also applied for studying stability of the power supplies.WinCC and EPICS(Experimental Physics and Industrial Control System)have been selected as the platforms of SCADA(Super- visory Control and Data Acquisition).For unifying the interfacing to the control computer,all front-end equipments are connected via Industrial Ethemet.     

水平管内含空气蒸汽强制对流冷凝换热模型研究

为研究含空气蒸汽在水平管内强制对流冷凝换热特性,基于对传热传质过程的分析,建立了管内为环状流与波状流条件下的流动冷凝换热模型。从潜热、显热和液膜3个环节对整个换热过程进行建模,最终得到计算局部冷凝换热系数的理论关系式。模型预测结果与实验数据的对比表明,二者相对偏差在±20%以内,验证了该换热模型的准确性与适用性。通过进一步的研究发现：从换热管入口至出口,随着冷凝的进行,管内换热主要热阻由液膜热阻向气液界面的凝结热阻转变;主流气体对流换热过程基本可忽略。     

Investigations on landmine detection by BF3 detector

Experiments were carried out to investigate the possible use of neutron backscattering for the detection of polyethylene (PE) sample buried in the soil. In detection of landmine by neutrons, the neutron detector and its shield play an important role. In this paper, the effects of graphite, heavy water, polyethylene and boric acid moderators on the flux of back scattered neutrons were investigated. We have also experimentally verified the effect of BF3 detector shield and obtained good agreement with theory.     

Web Services interface of SSRF archive data analysis system

Accelerator database stores various static parameters and real-time data of accelerator. SSRF (Shanghai Synchrotron Radiation Facility) adopts relational database to save the data. We developed a data retrieval system based on XML Web Services for accessing the archive data. It includes a bottom layer interface and an interface applicable for accelerator physics. Client samples exemplifying how to consume the interface are given. The users can browse, retrieve and plot data by the client samples. Also, we give a method to test its stability. The test result and performance are described.     

Assessment of radioactivity levels in some oil samples from the western desert, Egypt

Distributions of natural gamma-emitting radionuclides were determined in 93 oil samples collected from some petroleum fields in the western desert of Egypt. The radioisotope activities in the area under investigation lay in the range of (21 ± 4) to (38 ± 13) Bq?L-1 for 226Ra, (9 ± 2) to (15 ± 5) Bq?L-1 for 232Th, and (154 ± 28) to (303 ± 54) Bq?L-1 for 40K. The mean values were 27, 12, and 201 Bq?L-1, respectively. Among oils, variations in radionuclide ac- tivities could be on account of differences in TDS, HCO3, and Ba, with high or low pH. In this environment, oil prop- erties differently affected the mobilization of natural radionuclides. The range of 226Ra variation had been compared with available data from other countries. The calculated absorbed dose rate ranged from 22.33 to 32.66 nGy?h-1 in lo- cation (B) and (E) respectively, which was less than the accepted value.     

Preparation and properties of 117m Sn(IV)-TTHMP in in-vitro and in small animals

In this work,TTHMP was synthesized and labelled with 117m Sn.The preparation conditions,stability and lipophilicity of 117m Sn(IV)-TTHMP were investigated.Biodistribution of the complex in rabbits and mice was studied.It was found that the quantity of TTHMP and pH value of the prepararion solution had vital effects on the labeling yield of 117m Sn(IV)-TTHMP.It was also found that 117m Sn(IV)-TTHMP was hydrophilic and stable at room temperature and 37℃ in open air 117m Sn(IV)-TTHMP showed unexpectedly high bone uptake and bone-to-blood ratio in the animals.This made it potentially useful as an reagent for skeletal scintigraphy and radiotherapy of bone tumors.     

The role of AGFA high-energy CR in the calibration and quality control of multileaf collimators （MLC）

Linear accelerators equipped with multileaf collimators （MLC） are becoming more common and are widely used in the intensity-modulated radiotherapy （IMRT）. There is an imperative need to ensure the commissioning specification of the linear accelerators for the sake of quality assurance （QA） and quality control （QC）. This paper is aimed to investigate the role of AGFA high-energy CR （Computed Radiography） in calibrating dynamic multileaf collimators and evaluating the accuracy of the leaf position. The result shows that AGFA high-energy CR can easily and conveniently be used to calibrate MLC and verify its position. Hence, the application of AGFA high-energy CR is proved to be an accurate and time-saving method for routine MLC QC, especially when MLC calibration adjustments are required.     

Gamma radiation levels in the ambient environment of the QNPP Base

Monitoring results of gamma dose rate level in 1992～2004 in the ambient environment of the Qinshan Nuclear Power Plants(QNPP)Base,the northeast of Zhejiang Province,are reported in this paper.It is shown that the gamma dose rate of five monitoring sites of 2.5 km to QNPP Base is 84～113 nGy/h,with an average of 96 nGy/h in the 13 years.The average value is close to the background level of 93 nGy/h prior to operation of the QNPP Base,and is lower than the monitoring result of 101 nGy/h at the reference site in Hangzhou City.Within 50 km from the QNPP Base,the cumulative dose rate of the thermoluminescent dosimeter(TLD)is 90 nGy/h,which is lower than the back- ground level of 111 nGy/h.