双通道人工放射性气溶胶监测系统设计

人工放射性气溶胶的监测环境较为复杂,有时甚至要在地下洞库、坑道或地下核设施测量,其环境中氡及其子体产物的浓度高达10~3-10~4 Bq·m~(-3)。在高氡钍环境下,氡钍能峰拖尾导致其放射性计数影响了人工气溶胶道址计数,进而影响人工放射性气溶胶的探测下限。本文研制了一种适合在高氡环境下工作的常压、真空双通道人工气溶胶监测仪。虽然常压测量通道测量准确度较差,但响应速度快,可以弥补真空测量通道测量准确但响应速度慢的缺点。本仪器对大气环境中钚、铀气溶胶检测的响应时间快,在有人工核素泄露的情况下最快30 min内可以得到测量结果,理论探测下限可达到10~(-4)-10~(-3) Bq·m~(-3),可验证探测下限为铀0.1 Bq·m-3、钚0.02 Bq·m~(-3),适用于各类需要对人工核素进行无人监测的高氡环境场所。     

特殊环境中气载放射性物质的监测

本文介绍一种可用于特殊环境下空气中 β放射性气体和 β放射性气溶胶浓度的连续测量方法 ,重点对探测下限、测量范围和测量误差进行了分析。试验和分析表明 ,该方法对 β放射性气体的探测下限为 1 .85Bq/L ,对 β放射性气溶胶的探测下限为 7.4× 1 0 - 3Bq/L ,测量范围跨 5个数量级     

高氡背景下人工核素气溶胶快速监测装置

在地下洞库、坑道或地下核设施,尤其是处在花岗岩地带的地下设施,其环境中的氡及其子体产物的浓度可高达10^3～10^4Bq／m^3,它们将严重干扰人工核素（例如U、Pu）气溶胶的监测,甚至会造成测量失效,这是多年来急待解决的问题。为此,研制了一种新型气溶胶监测装置。该装置适用于在花岗岩坑道内氡水平较高的环境中测量低水平的铀、钚气溶胶浓度,并具有灵敏高、探测速度快的优点。该监测装置也可用于核设施工作场所及气态排出流中气溶胶的快速连续监测。     

高灵敏度的放射性气溶胶连续监测仪

介绍了一种高灵敏度的放射性气溶胶连续监测仪（CAM-1型）。该监测仪利用人工放射性气溶胶和天然放射性气溶胶粒度分布特性的不同,采用气溶胶粒度分离采样的方法,在采样过程中首先去除了天然放射性本底的大部分;进而在样品测量中利用a能谱分析法和改进a/β比值法,进一步消除了天然放射性本底的影响。通过上述措施,不仅实现了a气溶胶和β气溶胶的同时监测,而且极大地提高了仪器的监测灵敏度。介绍了CAM-1型放射性气溶胶连续监测仪的工作原理、结构设计、运行实验和监测灵敏度的估算。实验表明,在普通天然本底条件下,仪器的监测灵敏度为0.015Bq/m^3(对a放射性气溶胶）和1.0Bq/m^3(对β放射性气溶胶）;在高氡本底（10^3～10^4Bq/m^3）情况下,仪器的监测灵敏度则分别为0.15Bq/m^3（对a放射性气溶胶）和10Bq/m^3(对β放射性气溶胶）。监测仪报告数据的时间间隔通常30min,了可按需要任意设置。仪器具有各项自动报警功能。     

在线进样ICP-MS用于239Pu气溶胶活度浓度连续监测技术研究

为了弥补传统场所α气溶胶实时连续监测技术在后处理等场所239Pu气溶胶活度浓度连续监测方面探测能力和响应速度方面的不足,本文开展了基于ICP MS的空气中239Pu气溶胶连续监测技术研究。通过对气溶胶直接进样方法、ICP MS连续测量定量方法、238U干扰等方面研究工作的开展,建立了基于ICP MS、气溶胶直接进样系统和膜去溶雾化器联用的场所239Pu气溶胶活度浓度连续监测技术。在单次测量时间为1 min的情况下,依据ISO 11929（2019）计算得到本系统对239Pu气溶胶判断限和探测限分别为124×10-5 Bq/m3和248×10-5 Bq/m3,优于传统的基于PIPS的α气溶胶实时连续监测系统,远低于239Pu的导出空气浓度限值,证明该技术可为相关工艺场所239Pu气溶胶活度浓度连续监测提供快速高效的技术支持。     

新型放射性气溶胶在线监测仪设计

采用传统工控机作为控制/处理器的放射性气溶胶在线监测仪体积大、集成度低,在恶劣环境下容易因计算机死机、系统故障等导致仪器运行中断,为此研制了一种新型放射性气溶胶在线连续监测仪。该仪器在以高性能ARM嵌入式系统为核心的硬件和软件环境下,较好地实现了α能谱平滑、寻峰、峰位校正,天然氡钍及其子体放射性气溶胶扣除等关键技术,有效地提高了仪器的运行可靠性和稳定性。对监测仪进行了超过72 h的普通实验室环境的运行实验,测试结果表明:该仪器对α和β气溶胶的探测限分别为0.046 Bq/cm~3和0.29 Bq/cm~3。此外,通过相关试验对监测仪的准确性和稳定性进行了验证。     

双拟合方法在快速放射性检测系统中的应用

本文构建了一种用于测量食品中低水平放射性的快速放射性检测系统,提出采用双拟合方法对测量的γ能谱特征峰进行分析。在预设的能窗内通过第1次曲线拟合得到特征峰的基本信息,然后在特征峰位的5σ区间内确定峰区边界。通过第2次曲线拟合自动得到特征峰的净面积,完成快速放射性检测系统的定量分析。利用双拟合方法对标样进行测量、计算、分析,得到检测系统对137Cs核素的判断限、探测限、定量下限与测量时长、测量相对标准误差之间的关系。当检测时间为20 min时,系统的探测限约为8 Bq/L。若相对标准误差为15%,定量下限约为16 Bq/L。结果表明,双拟合方法可应用于快速放射性检测系统的数据处理,可对低水平放射性核素进行定性与定量分析。     

大气放射性气溶胶连续监测最小可探测活度浓度研究

介绍了大流量空气采样器用于北京地区大气放射性气溶胶进行连续监测的情况,给出了大流量空气采样器用于大气放射性气溶胶进行连续监测最小可探测活度、最小可探测活度浓度的计算方法,并且分析了几种典型人工核素的最小可探测活度浓度以及影响最小可探测活度浓度的因素。     

轻型α/β放射性气溶胶实时采样与测量系统设计

设计了一款轻型的α/β放射性气溶胶实时采样与测量系统。该系统通过微型泵对气溶胶进行实时取样,放射性物质富集在滤膜表面;PIPS探测器对滤膜进行直接测量,通过反符合设计,有效降低γ射线的干扰。在室外进行空气采样测试,该系统对α和β的探测下限为191.16 Bq/m³和1 133.27 Bq/m³。该系统的质量不足5 kg,可搭载在无人机、机器人及其他装备上,方便在复杂环境及核应急环境下使用。     

利用薄板塑闪测量水中总β放射性

在一些特定的情况下,需要一种能快速监测水中放射性活度变化的方法和装置。当前水中总β放射性测量主要采用取样测量的方法,取样测量的结果精确却耗时,这就需要采用新的仪器和设备对水中的放射性进行就地测量。研制了一套基于塑料闪烁体的水中放射性在线监测装置,对该装置的性能进行了模拟计算和初步测试。模拟计算结果表明,装置对40K探测效率为4.9×10-5cps/[(Bq/L)cm2]。通过实际测量,本装置对40K探测效率为3.0×10-5cps/[(Bq/L)cm2],模拟结果与实测结果的差异可能是闪烁光在传输过程中的损失造成的。对该装置进行测试,装置对水中的40K的最小可探测活度浓度约为500 Bq/L。     

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.