双极运算放大器LM158电离总剂量与重离子协同辐射效应研究

为研究双极运算放大器电离总剂量与单粒子瞬态的协同效应,选取双极运算放大器LM158分别在高剂量率0.1 Gy·s?1(Si)和低剂量率1×10?4 Gy·s?1(Si)条件下进行60Coγ射线辐照试验,累积电离总剂量至1000 Gy(Si)后,再进行重离子类型为钽(Ta)离子的协同辐照试验.试验结果表明:电离总剂量会导...     

线性稳压器不同偏置下电离总剂量及剂量率效应

为对工作在空间电离环境中稳压器的电离总剂量及剂量率效应进行研究,选择一种常用的低压差线性稳压器进行了不同偏置的高低剂量率的电离辐照和退火实验。结合电路特征和电离辐射效应,对线性稳压器产生蜕变的原因进行分析。结果显示,器件输出电压、线性调整率、负载调整率等关键参数在电离辐射环境下发生不同程度变化。在零偏条件下,低剂量率（LDR）下损伤明显大于高剂量率（HDR）条件,表现出低剂量率损伤增强效应;而在工作偏置条件下,高剂量率辐照损伤大于低剂量率的,退火实验中,发生损伤恢复现象,表现为时间相关效应。在整个辐照和退火过程中,零偏置损伤比工作偏置损伤大。     

不同偏置条件的10位CMOS模数转换器的辐射效应

对10位CMOSADC7910在不同偏置条件下的电离辐射效应及退火特性进行了研究。结果表明:模数混合电路在不同偏置条件下的电离辐照响应有很大的差异。与加电偏置相比,零偏下0.25Gy/s(Si)剂量率辐照时的辐射损伤更严重。并对其损伤机理进行了初步探讨。     

模拟数字转换器AD574总剂量和单粒子翻转的协合效应

以美国亚德诺半导体技术有限公司bipolar/I2L工艺的12位模拟数字转换器AD574为研究对象,在60Coγ辐照条件下累积400 Gy(Si)的电离剂量(Total ionizing dose,TID),对累积总剂量前后的样品进行激光单粒子翻转(Single-event upset,SEU)试验,获得了0 V、1 ...     

反应堆脉冲中子和γ射线辐照SiGe HBT器件的退火因子及典型直流参数测量分析

本工作测量了反应堆脉冲中子、γ辐照SiGe HBT典型直流电参数和退火因子.在反应堆1×1013 cm2的脉冲中子注量和257 Gy(Si)γ总剂量辐照后,SiGe HBT静态共射极直流增益减小了20%.辐照后基极电流、结漏电流增大,集电极电流、击穿电压减小.初步分析了SiGe HBT瞬态中子、γ辐射损伤机理.     

不同偏置下10位双极模数转换器高低剂量率的辐射效应

研究了10位双极模数转换器(ADC)在60Coγ射线不同剂量率、不同偏置条件辐照下的电离辐射效应及退火特性。研究结果发现,此类模数混合信号电路在不同偏置和不同剂量率辐照下的电离辐照响应有较大差异。同一电参数既表现出低剂量率损伤增强效应(ELDRS)又表现出时间相关效应(TDE)。研究结果进一步表明,低剂量率辐照0 V偏置是最劣偏置;与之相反,高剂量率辐照5 V偏置是最劣偏置,而加电阻偏置对辐照损伤有一定的抑制作用。最后,结合空间电荷模型和边缘电场效应对其辐照损伤差异及退火机理进行了初步探讨。     

质子辐射环境下PNP输入双极运算放大器辐照效应与退火特性

对不同偏置下的PNP输入双极运算放大器在3、10 MeV两种质子能量下的辐照效应进行了研究,并将质子辐射损伤效应与0.5Gy(Si)/s剂量率60 Coγ射线辐射损伤效应进行了比较,以探究质子和γ射线产生的辐射损伤之间的对应关系。结果表明,运放LM837对γ射线的敏感程度较10 MeV质子和3 MeV质子的小,然而其室温退火后的后损伤效应却更严重;相同等效总剂量条件下,10 MeV质子造成的损伤较3 MeV质子的高;质子辐射中器件的偏置条件对损伤影响不大。     

双极型运算放大器ELDRS效应试验研究

针对空间辐射环境下应用的双极型器件抗辐射能力与地面高剂量率辐照模拟试验所获得器件的抗辐照水平存在差异,在地面利用60Co辐射源开展了双极型运算放大器的总剂量辐照试验研究,分析了辐照剂量率、辐照偏置和室温退火3种试验组合条件下样品的总剂量响应.结果表明,在300 Gy的辐照水平下,低剂量率辐照条件下器件参数的退化损伤是高...     

180 nm CMOS微处理器辐照损伤剂量的实验研究

以180 nm互补金属氧化物半导体(Complementary Metal Oxide Semiconductor, CMOS)工艺制造的STM32微处理器为实验对象,设计了由被测最小系统电路、剂量计、通讯电路和上位机组成的总剂量效应实验条件。利用60Co源分别在63.3 Gy(Si)·h~(-1)和101.2 Gy(Si)·h~(-1)剂量率下,对14个实验样品进行了在线辐照,通过数据校验实时判断受照样品的功能运行状态;在227.2～855.0 Gy(Si)累积剂量范围内,对75个实验样品进行了离线辐照,对比样品受照前后的功能运行状态。实验结果表明:片内FLASH存储器是STM32微处理器中最先损伤的硬件单元;受照前后,STM32微处理器各引脚的对地阻抗以及片内模拟数字转换器输出值基本无变化,功耗电流略有增加。63.3 Gy(Si)·h~(-1)和101.2 Gy(Si)·h~(-1)在线照射条件下辐照损伤剂量分别为(235.4±16.4)Gy(Si)和(197.4±13.0)Gy(Si);离线照射条件下的辐照损伤剂量介于391.5～497.6 Gy(Si)之间。     

典型光电器件~(60)Co γ射线辐照试验研究

用60Coγ射线对GaAlAs异质结红外发光二极管OP224和NPN型Si光电三极管OP604进行了电离辐照试验,分析了试验器件在60Coγ射线辐照下氧化物陷阱电荷和界面态陷阱电荷的积累效应。结果表明,随着辐照累积剂量的增加,OP224正向电流的最大值逐渐下降,红外光强度逐渐衰减;OP604的暗电流逐渐增大,光电流逐渐下降。     

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。     

有效探测面积大于1000 cm2的正比计数器测量系统性能测试

为对自制的活性面积高达1 000 cm²的大面积源进行表面发射率定值,同时作为现有2πα、2πβ表面发射率标准装置能力的扩充,研制了一套内置式大面积2π多丝正比计数器测量系统,并利用活性区直径为8 mm的²⁴¹Am点源及活性区面积为10 cm×15 cm的大面积²⁴¹Am和⁹⁰Sr-⁹⁰Y源对其进行计量学性能测试。结果表明：计数器内计数响应均匀性优于±0.4%,有效探测面积达1 400 cm²;所得²⁴¹Am源高压坪曲线的坪长为1 400 V,坪斜为0.27%/100 V,坪区内计数变化为0.87%;⁹⁰Sr-⁹⁰Y源高压坪曲线的坪长为300 V,坪斜为0.75%/100 V,坪区内计数变化为0.80%;10次测量重复性好于0.4%,8 h内短期稳定性好于0.3%,1 a内长期稳定性好于0.8%。     

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.     

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.