电子和β射线两用外推电离室的研制

本文研制了一台测量电子束和β射线吸收剂量的外推电离室,其空腔室壁材料可拆换并分别与空气、组织和硅等效,收集电极名义直径为1.5、3、10和30mm,空气空腔可变范围为0.2～15mm。该外推电离室具有在空腔内部测温,自动改变窗口上方材料厚度及采用微型计算机控制等特点。适用于测10 MeV能量以下,剂量率为10~5～10~(-3)Gy/h的电子或β射线吸收剂量。整个外推电离室自动测剂量系统在测~(204)TLβ放射源表面剂量率的不确定度为2.3％。测1.5 MeV电子束在硅和哈密瓜深部剂量率时,不确定度分别为4.0％和2.8％。     

β吸收剂量绝对测量装置

β吸收剂量绝对测量装置由PTW 23392型湿度计和外推电离室、FJ—356型振动电容静电计、数字电压表、温度计、气压计等组成。实验测定了所用静电计的内部反馈电容、外推电离室不同极间距离时的电容,从而确定了外推电离室的有效收集面积为7.106×10~(-4)m~2。实验测量了外推电离室窗对于天然铀、~(147)Pm和(~(90)Sr ~(90)Y)β辐射的散射和阻止的修正。实验测出或计算出其他修正,实验测出直径为90mm、厚为10mm的天然铀块表面组织吸收剂量率为2.289mGy/h,总不确定度为1.7％。实验测出~(147)Pm和(~(90)Sr ~(90)Y)β参考辐射的组织吸收剂量率,总不确定度分别为3.0％和1.7％。     

X射线空气比释动能(治疗水平)标准装置的建立

为开展X射线在治疗水平剂量率下的量值溯源与传递工作,依据IEC 60731—1997标准的要求,建立了管电压为10~250 kV、剂量率范围为1.0×10^-3~10 Gy/h的X射线空气比释动能(治疗水平)标准装置。其中10~60 kV X射线空气比释动能(治疗水平)标准装置在1.0 m处非均匀性小于1%的辐射野为ø60 mm,散射对辐射场贡献小于1.2 %,在距离放射源1~5 m范围内反平方律在2.5 %内符合,使用标准电离室测得装置的稳定性为1.8％、重复性为0.1％。60~250 kV X射线空气比释动能(治疗水平)标准装置在1.0 m处非均匀性小于1%的辐射野为ø80 mm,散射对辐射场贡献小于1.2 %,在距离放射源1~5 m范围内反平方律在1.5 %内符合,使用标准电离室测得装置的稳定性为1.7％、重复性为0.03％。标准装置辐射场空气比释动能率的相对扩展不确定度为3.0％ (k=2),经测量,装置的各项性能指标均满足治疗水平剂量检测仪器的检定/校准要求。     

大口径薄窗密封型穿透电离室(英文)

穿透电离室用于在线监测探伤加速器输出剂量率、累计剂量,并为剂量保护提供监测和控制信号。电离室的存在不影响加速器的输出特性。该电离室的线性、工作的长期稳定性是加速器调试和运行的关键之一。电离室采用大口径双重密封结构,制作工艺难度大,要求高。电离室透射性能好,薄窗直径Φ80mm,厚0.05mm,薄窗及电极总厚度对1～4MeV Ⅹ射线强度吸收小于1％。电离室的灵敏度高,当加速器中心轴线上距靶一米处的剂量率为1Gy/min时,电离室电离电流大于0.55μA。电离室线性好、饱和特性好,当加速器中心轴线上距靶一米处的剂量率小于4.15Gy/min时,其非线性小于1％;当电离室工作电压-700V,且承受的脉冲剂量率高达2×10~5Gy/min时,其复合校正小于1.5％。电离室的重复性也好,相隔一年零七个月,前后两次测得电离室的重复性均为0.5％左右。当电离室工作电压-700V时,电离室漏电流小于5×10~(-13)A。在恶劣环境下、强干扰场中和运动及冲击条件下,电离室能长期稳定可靠地工作。     

基于~(90)Sr源β射线的外推电离室入射窗修正因子

为实现外推电离室对β辐射吸收剂量的准确测量,对影响外推电离室入射窗修正因子k_(wi)的主要量进行了研究。实验测量了外推电离室不同极间距和不同源-探距(源到外推电离室入射窗表面的距离)下的k_(wi)。研究结果表明,在源-探距不变的条件下,k_(wi)随电离室极间距的增大而减小;在电离室极间距为3 mm的条件下,k_(wi)随源-探距的增大而减小。利用蒙特卡罗模拟计算出不带展平过滤器、源-探距为30 cm、电离室极间距为3 mm时,k_(wi)为1.084 5,与实验测量结果比较,其相对偏差为0.11%。因此,在给出k_(wi)的同时,应提供相应的源-探距和电离室极间距。     

基于90Sr源β射线的外推电离室入射窗修正因子

为实现外推电离室对β辐射吸收剂量的准确测量,对影响外推电离室入射窗修正因子k_wi的主要量进行了研究。实验测量了外推电离室不同极间距和不同源 探距（源到外推电离室入射窗表面的距离）下的k_wi。研究结果表明,在源 探距不变的条件下,k_wi随电离室极间距的增大而减小;在电离室极间距为3 mm的条件下,k_wi随源-探距的增大而减小。利用蒙特卡罗模拟计算出不带展平过滤器、源 探距为30 cm、电离室极间距为3 mm时,k_wi为1.0845,与实验测量结果比较,其相对偏差为0.11%。因此,在给出k_wi的同时,应提供相应的源-探距和电离室极间距。     

4MeV电子直线探伤加速器主要参数测量

在加速器中心轴线上距靶1m处,放置标准剂量计空腔电离室,此电离室放在160 mm×150 mm×150 mm的标准有机玻璃模体的最大剂量深度处,用标准次级剂量计进行测量。经激光对中后,在不同重复频率下,重复三次,测得最大吸收剂量率为4.11 Gy/min。     

高剂量率近距离治疗源井型电离室校准

对高剂量率⁶⁰Co近距离治疗放射源参考空气比释动能率进行测量并校准井型电离室。根据国际原子能机构推荐方法利用指型电离室测定参考空气比释动能率标准值,进而对井型电离室校准。参考空气比释动能率标准值为1.061 3×10^-2 Gy·m²·h^-1,井型电离室的校准因子为9.391×10⁵Gy·m²·h^-1·A^-1;⁶⁰Co放射源的参考空气比释动能率标准值的不确定度为2.11%(k=2),井型电离室校准因子的不确定度为2.6%(k=2)。实现了⁶⁰Co近距离治疗放射源参考空气比释动能率的测量及其井型电离室的校准,为高剂量率⁶⁰Co近距离治疗源的临床质控提供了量值保障。     

可作为校准检定用标准剂量计的能量补偿型高气压电离室改进

在电离辐射计量检定工作中,标准剂量计的测量结果通过检定逐级传递到工作计量器具,以实现单位统一和量值准确可靠。由于环境水平γ射线剂量率较低,国际上常用的PTW-UNIDOS系列标准剂量计无法满足需要。针对这一特点,结合蒙特卡罗方法对高气压电离室的X射线、γ射线和宇宙射线响应特性进行模拟计算,进行了能量补偿型高气压电离室改进。测试结果表明:剂量率约30 μGy/h时,能量补偿型高气压电离室在87 keV～1.25 MeV能量范围内相对于¹³⁷Cs γ射线的响应偏差不大于6%,宇宙射线和¹³⁷Cs γ射线的响应偏差不大于10%,在0.5 μGy/h～1 mGy/h范围内相对固有误差为-3%,0.5 μGy/h时的重复性为0.7%,校准因子的不确定度为4%(k=2),可作为环境水平标准剂量计在校准检定工作中使用。     

X射线空气比释动能(诊断水平)标准装置的建立

为了实现诊断水平X射线剂量率值的准确测量,并开展量值的溯源与传递工作,本文根据IEC 61267—2005标准的要求,建立了管电压40~150 kV、剂量率1.0×10^-3~10 Gy/h的X射线空气比释动能(诊断水平)标准装置,实验测量给出了不同辐射质下的辐射场特性,并评定给出了辐射场空气比释动能率的相对扩展不确定度。实验测量结果表明,RQR5辐射质在距离X射线光斑焦点1.0 m处,均匀性＞99.0%的辐射野为ø8.0 cm,均匀性＞95.0%的辐射野为ø10.0 cm;散射对辐射场的贡献＜0.9%;在1.0~5.0 m范围内的距离平方反比律偏差＜2.0%;标准电离室测得辐射场剂量率重复性为0.1%。对RQR2~RQR10系列与RQT8~RQT10系列辐射质的半值层和同质系数进行测量,其半值层偏差不超过±0.09 mm,同质系数偏差不超过±0.02。辐射场空气比释动能率的相对扩展不确定度评定结果为U_rel=3.8%(k=2)。辐射质特性实验测量结果表明,X射线空气比释动能(诊断水平)标准装置的各项性能指标均满足IEC 61267—2005等标准要求。     

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.     

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.