关于现有x、γ热释光个人剂量计测量深部个人剂量当量Hp(10)适用性的探讨

测量了X、γ热释光个人剂量计对深部个人剂量当量Hp(10)的能量响应和角响应,实验结果表明,这些剂量计对Hp(10)的能量响应和角响应满足ICRP 35号出版物的要求。     

IP板对中/高能X/γ射线响应特性研究

为了实验得到IP板对中/高能X/γ射线的响应,基于X射线装置和~(137)Cs、~(60)Co放射源研究了IP板对40keV~1.33 MeV范围内的X/γ射线的响应。利用IP板的物理模型和蒙特卡罗方法对IP板的响应进行了计算和模拟,两者的结果与实验结果符合较好。基于X/γ射线在IP板感光层中的沉积效率,研究了IP板对X/γ射线沉积的灵敏度响应,理论计算结果与实验结果亦符合较好。本文研究结果为将IP板应用于中/高能X/γ射线测量提供了数据支撑和技术基础。     

在辐射防护测量中使用的量

本文论述了在辐射防护测量中使用实用量的必要性。分别讨论了现存X、γ射线监测仪、热释光x、γ个人剂量计测量H~*(10)、Hφ(10)的适用性,说明采用实用量对未来仪器的设计不会带来严重问题。给出了校准X、γ辐射场所监测量和个人剂量计的方法。     

圆柱形电离室的能响补偿

电离室由于其具有结构简单、使用方便的特点,目前仍被广泛应用于辐射监测领域。用于X、γ射线测量时,必须研究电离室的能量响应,并通过能响补偿使其灵敏度在一定的误差范围内是与入射X、γ射线的能量无关的常数。利用蒙特卡罗方法,模拟计算了圆柱形电离室对X、γ射线的灵敏度和能量响应;并根据计算结果的规律,对圆柱形电离室的能量响应进行了补偿,给出了补偿参数的最优范围。     

~6LiH 过滤盒的性能研究及其在剂量测量中的应用

本文给出了~6LiH 过滤盒的中子、γ射线吸收性能的实验结果。壁厚约为1.5mm 的~6LiH 盒对反应堆热中子的吸收与0.5mm 厚的 Cd 相当;利用壁厚为2mm 的~6LiH 盒,测得~7LiF、~6LiF 和天然 LiF 热释光剂量计(TLD)的热中子响应系数分別为6.2×10~(-10)、1.06×10~(-7)和2.5×10~(-8)R·cm~2;通过与 Cd 盒比较,得到 Cd 的俘获γ系数为4.96×10~(-9)R·cm~2。介绍了用包~6LiH的 LiF-TLD 测量反应堆周围中子-γ混合场中的热中子和γ射线剂量。     

用于X射线探测的CVD金刚石薄膜探测器

研制了用于X射线测量的化学气相沉积(CVD)金刚石薄膜探测器.该探测器灵敏区直径为15 mm、厚度300 μm,其暗电流在800 V偏压下小于50 pA,且暗电流-电压曲线线性较好.就CVD金刚石探测器对不同能量X射线的响应及脉冲X射线时间响应进行了理论和实验研究.结果表明:该探测器对6～22 keV X射线具有10-4～10-2A·W-1的灵敏度,假设电荷收集效率为39%时,灵敏度的理论值与实验测量值符合较好,探测器的RC时间常数约为1.5 ns;对亚纳秒脉冲X射线的响应上升时间为2～3 ns.     

嫦娥一号X射线谱仪定标

介绍了嫦娥一号X射线谱仪实验室定标,主要包括能量响应(能量与能道关系、能量分辨率)和角度响应,这些定标结果对于环月运行获得的X射线数据的反演与分析是必不可少的.     

φ76mm×100mm BGO闪烁探测器在20 MeV以下能区的能量响应

用上海硅酸盐所提供的φ76mm×100mm BGO晶体制作γ闪烁探测器、用来探测???离子核反应中放出的10-100 MeV的γ射线,该探测器对~?Cs的0.661 MeV γ射线的?????14.2%。在加速器上用若干(p,γ)反应产生的单能光子测试探测器的能量响应,通过细致的数?拟合得到该探测器在20 MeV以下能区的能量响应和全能峰能量分辨率。对17.65 MeVγ射线。探测器的能量分辨率为4.1%。     

一种用于个人剂量当量Hp(0.07)监测的剂量计研制

鉴于目前国内生产的个人剂量当量H_p(0.07)剂量计对低能β辐射响应较差,以及对β、γ混合场中H_p(0.07)剂量测量误差较大的问题,基于LiF:Mg, Cu, P热释光探测器,结合模拟计算,研制了一种ZF-P7型H_p(0.07)剂量计。其性能指标测试结果表明：对于最大能量为225 keV～2.274 MeV的β射线,响应在0.67～0.95之间;对16 keV～1 250 keV的X、γ射线,响应在0.66～1.45之间;在剂量100μSv～1.2 Sv范围内,剂量线性在0.91～1.10范围内;在入射角为0～±60°,对65 keV X射线的角度响应在0.99～1.09范围之内,对⁸⁵Kr β射线角度响应在0.94～1.11范围之内。经实验验证,ZF-P7型H_p(0.07)剂量计的各项指标均满足行业标准EJ/T 1178—2005和检定规程JJG(军工)37—2014要求。由于该ZF-P7型剂量计性能优良,特别是对不同能量的X、γ、β辐射响应较好,可解决混合辐射场作业人员H...     

β-γ胶片剂量计

本文介绍了用上海牌4F型胶片对~(204)Tl,~(32)P,~(90)Sr ~(90)Y和天然铀等几种β源的β射线灵敏度实验以及对X和γ射线的能量响应实验,选择了测β射线的三个过滤窗和一个测γ射线用的锡过滤窗,组成了四窗的β-γ胶片剂量计。     

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.     

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%。     

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.