碘化汞探测器的研制进展

使用片状法生长ＨｇＩ２单晶片制砀２０ｍｍ２×０．４ｍｍ探测器在常温下对５９．５ｋｅＶγ射线和５．９ｋｅＶＸ射线的能量分辨率分别为１．９ｋｅＶ和９００ｅＶ。已用于Ｃｕ、Ｐｂ、Ｚｎ等矿样分析，取得了新结果。     

大面积Si（Li）探测器

测量了不同温度条件下面积为４９ｍｍ×４９ｍｍ、厚３．５ｍｍ的Ｓｉ（Ｌｉ）探测器的Ｉ－Ｖ特性。Ｓｉ（Ｌｉ）－Ｅ－１和Ｅ－２探测器对＾２３８Ｐｕ５．４９９ＭｅＶ α粒子的能量分辨率例如为５４．４ｋｅＶ和５７．０９ｋｅＶ。     

元件破损实时监测与分析中裂变产物光子能量的选择

计算了不同裂变产物的主要γ光子对φ７６．２ｍｍ×７６．２ｍｍ ＮａＩ探测器光电峰的相对探测效率。结果表明，在燃料元件破损监测中，光电效应计数率最高的几种光子能量与核素是８１ｋｅＶ（＾１３３Ｘｅ）、１９６．３ｋｅＶ（＾８８Ｋｒ）、２２０．９ｋｅＶ（＾８９Ｋｒ）、２４９．８ｋｅＶ（＾１３５Ｘｅ）、４０２．６ｋｅＶ（＾８７Ｋｒ）和５２９．８ｋｅＶ（＾１３３Ｉ）。由于活化产物γ辐射的干扰，监测用γ光子的能     

电致冷高分辨率Si（Li）能谱仪

电致冷高分辨率Ｓｉ（Ｌｉ）Ｘ射线能谱分析仪采用电阻反馈前置放大器，灵敏面积为２８ｍｍ＾２Ｓｉ（Ｌｉ）探测器，对＾５５Ｆｅ５．９ｋｅＶＸ射线，能量分辨率（ＦＷＨＭ）为７００ｅＶ左右，对探测器在不同温度下随偏压的变化，致冷功率与温度关系，冷却温度与时间关系进行了研究。     

HPGe低本底反康普顿γ谱仪

本文报道了以ＨＰＧｅ为主探测器的低本底反康普顿γ谱仪，该谱仪以环形和圆柱形ＮａＩ（ＴＩ）组成阱型反符合屏蔽探测器，以钢，铅及不锈钢等材料组成复合结构屏蔽室。对＾４０Ｃｏ１３３２．５ｋｅＶγ射线，ＨＰＧｅ主探测器能量分辨率为１．８６ｋｅＶ，相对效率为３８％，在阱型反符合屏蔽条件下，谱仪对＾１３７Ｃｓ点状薄膜源测得康普顿抑制系数为４．４；峰康比为８７０：１；５０￣２０００ｋｅＶ能区内每ｍｉｎ积分本底为     

低温小立体角α谱仪的研制

研制了１套工作温度在室温至－２７．５℃、面源对探测器所张的相对立体角在５．２８７×１０－２—１．１１９×１０－４之间、分辨率达到１３．３ｋｅＶ的低温小立体角半导体α谱仪，研究了谱仪分辨率与探测器温度和相对立体角之间的关系。该谱仪已应用于α放射性比、α粒子能量、α粒子辐射几率和α放射性活度的测量。     

Ar离子辐照的非晶态合金表面发泡扫描电镜观测

１５０、１９５和３００ｋｅＶＡｒ离子在室温下辐照非晶态合金Ｃｏ７０．２Ｆｅ３． ９Ｎｄ３．９Ｓｉ１４Ｂ８和Ｃｏ６６Ｆｅ４．５Ｖ２．２５Ｎｉ２．２５Ｓｉ１０Ｂ１５，扫描电镜在一定的辐照剂量范围观测到了表面发泡形成，发泡形成的临界剂量和直径随离能量增加而增加。Ａｒ离子能量高于１９５ｋｅＶ时，发泡和发泡破裂是主要的表面损伤现象，而在１５０ｋｅＶＡｒ离子辐照下，未观测到发泡破裂。     

Si（Li）电子谱仪的研制

研制了“无窗”的Ｓｉ（Ｌｉ）电子谱仪，测量了＾２０７Ｂｉ的内转换电子能谱，对能量９７５．６２ｋｅＶ的电子取得了２．０７ｋｅＶ的能量分辨率。     

一台自行组建的低本底Ge（Li）－NaI（T1）反符合γ谱仪

本文报道自行组建的一台Ｇｅ（Ｌｉ）－ＮａＩ（Ｔｌ）反符合γ谱仪的结构和性能。主探测器是φ６１．５ｍｍ×５６．０ｍｍ的同轴Ｇｅ（Ｌｉ）探测器（灵敏体积为１５０ｃｍ￣３），由φ８８．９ｍｍ×７６．２ｍｍ的圆柱形ＮａＩ（Ｔｌ）晶体和外、内径×高为２５４ｍｍ、８８．９ｍｍ×３０５ｍｍ的环形ＮａＩ（Ｔｌ）晶体构成井型反符合探测器，主要的物质屏蔽层是１００ｍｍ铅＋１５ｍｍ钢＋５ｍｍ铜。Ｇｅ（Ｌｉ）探测器对￣（６０）Ｃｏ１３３３ｋｅＶ能量的分辨率为２．４ｋｅＶ，峰康比为４４，相对探测效率为２４％。在反符合屏蔽条件下，谱仪在康普顿坪（３５８—３８２ｋｅＶ）和康普顿端（４６０—４８４ｋｅＶ）的抑制因子分别为５．Ｏ和５．４；康普顿区积分（５０—５９５ｋｅＶ）抑制因子３．６，峰康比（￣（１３７）Ｃｓ点源）为４９４。在１００—２０００ｋｅＶ能区屏蔽室内、外的积分本底比为１：１３１。加反符合和不加反符合条件下的积分本底抑制因子为３．５，加反符合后的积分本底为１７．２ｃｐｍ。当测量时间１０００ｍｉｎ、置信度９５％时，￣（１３７）Ｃｓ的最低可探测活度（判断限）为５．８ｍＢｑ．２４小时内，￣（２４１）Ａｍ、￣（１３７）Ｃｓ和￣（６０）Ｃｏ     

外延硅dE／dX探测器的研制

本文介绍了厚度为５．２－６．０、１０－１３、１９μｍ，有效面积为２８－１５４ｍｍ＾２的外延硅ｄＥ／ｄＸ探测器的研制工艺，主要用途，测试结果（对９．８７ＭｅＶ α粒子的能损△Ｅ的分辨率为５６－１２８ｋｅＶ）和在核物理实验中的应用。     

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.