高纯锗探测器全能峰效率的MC模拟

采用MC模拟高纯锗探头对轴向和边侧的点源全能峰效率,与实验测得的全能峰效率相比较发现二者存在较大的偏差。本工作通过不断调节晶体的半径、厚度和锗晶体外层铜支架厚度,获得了模拟计算的准确尺寸。结果表明:使用调整后的尺寸模拟计算的全能峰效率与实验效率在轴向方向的偏差在±5%以内,边侧方向在±6%以内,获得了较为准确的高纯锗探头物理模型。     

溴化镧探测器的晶体表征与全能峰效率计算

无源效率刻度技术已在辐射探测器的效率刻度中得到了广泛的应用。本文基于点源效率实验及蒙特卡罗模拟计算方法,对溴化镧探测器的晶体尺寸进行了调整;在此基础上,计算得到不同位置处全能峰效率的计算值。点源效率实验的验证结果表明,在121～1 332 keV能量范围内,γ光子全能峰效率的计算值与实验值的相对偏差小于±5%。     

溴化镧探测器效率刻度与晶体表征

利用三种不同的放射性标准点源对溴化镧探测器的能量与道址关系曲线、能量与半高宽、全能峰探测效率曲线进行了实验研究;然后利用蒙特卡罗方法和实验探测效率曲线对溴化镧探测器的尺寸进行了表征,建立计算模型。根据计算模型,模拟计算在不同位置、能量区间在100~1 500 keV范围内的γ射线的全能峰探测效率。模拟结果与实验结果的相对偏差绝大部分处于±5%以内,说明计算模型是准确可靠的。     

γ谱仪测量土壤样品探测效率模拟刻度研究

针对Ф75mm×25mm的土壤样品,利用HPGeγ谱仪,分别用241Am、137Cs、~(60)Co混合点源测量5种高度的样品剖面上不同位置的全能峰效率,确定点源全能峰效率随半径变化的函数关系,对该函数进行数值积分计算可以得到59.54keV、661.66keV、1173.2keV和1332.5keVγ射线的面源全能峰效率,进一步拟合确定面源全能峰效率随样品高度变化的函数参数,对样品高度进行数值积分计算得到Ф75mm×25mm样品的体源全能峰效率。结果表明,点源模拟计算的体源全能峰效率和标准体源全能峰效率进行比较,两者在10%以内符合。因此,在没有标准体源的情况下,用已知活度的标准点源模拟体源进行全能峰效率刻度的方法替代标准体源进行效率刻度方法是可行的。     

应用蒙特卡罗方法表征HPGe探测器

采用蒙特卡罗方法计算HPGe探测器对光子的探测效率,需对计算模型参数进行确定。使用蒙特卡罗模拟计算和实验测量相结合的方法,对晶体死层厚度及冷指尺寸进行了表征。结果表明,使用此方法确定晶体参数模拟光子的探测效率,在59.54～1408.1keV光子能量范围内,计算效率与实测效率相对偏差在5%以内,并进行了实验验证。     

应用蒙特卡罗方法模拟HPGeγ谱仪的体源探测效率

采用蒙特卡罗方法模拟计算了HPGeγ谱仪对标准样品体源的全能峰探测效率;然后通过实验测量获得标准样品体源各特征能量γ光子的全能峰净计数,并结合模拟得到的全能峰探测效率计算出标准样品体源中天然放射性核素的比活度,计算结果与标称值的相对偏差在±3%以内,符合较好。     

高纯锗探测器无源效率刻度的锗晶体尺寸自动调整方法

本发明涉及辐射测量技术领域,具体涉及一种用于高纯锗探测器无源效率刻度的锗晶体尺寸自动调整方法。该方法在一个测量位置处获得多个不同E能量的γ射线全能峰探测效率测量值,然后依据探测产品说明书中晶体的原始尺寸,进行蒙特卡罗模拟计算,获得相应的各E能量γ射线全能峰探测效率计算值;对效率计算值与测量值进行误差分析,通过蒙特卡罗计算获得当前晶体尺寸下,晶体尺寸T、R和L对E能量γ射线的效率影响公式;设定计算效率期望改变百分比,建立方程组,求解获得新晶体尺寸,如此循环得到最终结果。本发明可以自动、快速、准确地确定高纯锗晶体及其灵敏区尺寸,从而为高纯锗探测器实现快速蒙特卡罗无源效率刻度提供了有效保证。     

蒙特卡罗方法计算用于低能光子测量的高纯锗探测器的效率

在内照射活体测量中,为了用蒙特卡罗方法计算探测器对光子尤其是低能光子的探测效率,需要对探测器准确建模。通过使用蒙特卡罗模拟计算和实验测量相结合的方法来准确确定低能光子高纯锗探测器晶体的死层厚度、半径和长度;结果表明使用此方法确定的晶体尺寸来模拟计算探测器效率,在17．5～662keV光子能量范围内,低能光子高纯锗探测器探测效率的模拟计算结果与实验结果比较,相对偏差平均小于1．0％,最大为3．2％。     

高纯锗探测器的效率刻度

探测效率是高纯锗谱仪的重要性能指标,探测器的效率刻度具有重要的意义。针对新购置的高纯锗谱议,采用多线法和距离变换相结合的实验方法,刻度了高纯锗探测器在不同源距下的全能峰效率曲线,并利用厂家提供的探头结构尺寸,采用MCNP5程序模拟计算了该探测器对不同能量γ射线的全能峰效率。将模拟计算效率和实验效率进行对比,模拟计算的全能峰效率和实验测定的全能峰效率具有一定偏差,经分析偏差主要原因是探测器内部结构尺寸不够精确,通过调节死层厚度和冷指尺寸,使得模拟计算效率和实验效率很好符合。     

海洋γ谱连续监测方法模拟

通过蒙特卡罗程序MCNP(Monte Carlo N Particle Transport Code)建立了海洋γ谱连续监测的测量模型,模拟计算不同能量γ射线在海水中的衰减情况和有效探测距离。根据我国近岸海域海水中天然放射性核素活性浓度,模拟得到不同晶体尺寸NaI探测器连续监测的本底谱,分析能量分辨率对全能峰本底计数率的影响并探讨了影响NaI探测器能量分辨率的因素。最后针对我国核电厂周围海域中重点关注的人工放射性核素,并假设不同尺寸NaI晶体在能量662 keV处分辨率保持7.0%不变的条件下,分别计算了不同尺寸NaI晶体探测器在海洋γ谱连续监测中的探测效率、本底计数率和最小可探测活性浓度等技术参数。模拟结果为海洋或其它水体中γ谱连续监测方法的应用提供技术参考。     

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.