Zr-2/Cr扩散反应层物相分析

研究Zr-2/Cr扩散反应层物相，可为判断Zr-2和Cr是否相容提供依据。用热压法（50MPa)获得在1073K时Zr-2/Cr扩散反应层。分别用透射电镜（TEM）和场发射扫描电镜配备的薄窗能谱仪（EDS）对反应层进行结构的成分分析。结果表明，Zr-2/Cr扩散反应生成六方结构（C14型的）Zr(Fe,Cr)2Laves相。     

Al-Si共晶合金与1Cr18Ni9Ti不锈钢的相容性研究

用粉末冶金法制备了Al-Si共晶合金与1Cr18Ni9Ti不锈钢反应堆扩散偶。采用电子显微镜（SEM）、能谱分析仪（EDS）、X射线衍射仪（XRD）D究了扩散偶在560℃和650℃时的相容性及扩散层形成机理。结果表明,扩散温度对两种材料之间的相容性有显著影响;650℃时,Al-Si共晶合金与1Cr18Ni9Ti之间通过浸润和扩散反应形成了比较明显的扩散层。XRD谱也表明,扩散层中存在Fe2Al5化合物;560℃时Al-Si共晶合金与1Cr18Ni9Ti之间仅发生固相反应,形成的扩散层很薄,二者相容性较好。     

U-Mo-Zr／Al-Si的互扩散行为

通过弥散体和扩散偶堆外退火试验，研究了Zr添加到U-Mo合金对U-Mo-Zr和Al-si反应的影响。Zr含量为1wt．％、2wt．％和4wt．％的U-7wt．％Mo合金锭由真空感应熔炼而成，采用离心雾化法制成粉末。对经γ相热处理过的U-7Mo-Zr合金进行高温退火试验，研究其γ相稳定性。X射线衍射分析结果表明：U-7Mo-Zr合金的γ相分解与U-7Mo合金类似。为研究互扩散行为，使用U-Mo-Zr粉末和Al-（0、0．4、2、5）wt．％Si合金粉末制备了弥散型样品。采用和弥散型样品化学成份相同的材料制备了扩散偶样品并进行了退火试验，以比较弥散型样品和扩散偶样品的互扩散行为。高Zr含量的弥散型样品在600℃时互扩散速度小幅增大，而扩散偶样品表明Zr添加到U-7Mo中降低了反应增长速度。Si能够减缓反应增长速度。U-Mo合金中添加的Zr没有在反应层中富集，而添加到～中的Si在反应层富集。U-Mo-Zr／Al-Si扩散偶中形成的反应产物为富Si的U（Si、Al）2。     

热处理对锆-4合金中第二相结构和成分的影响(英文)

用电化学方法分离出锆-4合金中第二相,研究了不同热处理制度对第二相结构和成分的影响。锆-4合金经1050℃β相加热空冷后,析出的第二相为立方结构的Zr(Fe,Cr)_2,Fe/Cr比值在2.1～2.5之间。试样重新在600～800℃下加热3h,晶体结构不发生改变,只是Fe/Cr比值逐渐降至1.9;但在700～800℃下加热后,有少量的六方结构Zr(Fe,Cr)_2第二相析出。生产厂提供的锆-4板中第二相是六方结构的Zr(Fe,Cr)_2,重新在700～800℃加热3h,晶体结构不发生变化,Fe/Cr比值由1.9降至1.5左右。这说明在重新加热时,第二相中的Fe和Cr与周围基体中的Fe和Cr会相互扩散置换。试样从β相冷却析出第二相时,Fe原子的扩散比Cr原子快;Cr原子在六方晶格Zr(Fe,Cr)_2中的固溶度比在立方晶格Zr(Fe,Cr)_2中的大。由于这些原因造成了第二相成分随热处理制度不同而变化的现象。     

Nb-1Zr与316L不锈钢爆炸焊高温退火扩散层的显微组织分析

研究了Nb-1Zr合金与316L不锈钢爆炸焊在1 300 ℃退火后形成的互扩散层.该互扩散层宽度约为80 μm.用透射电子显微镜(TEM)分析观测到该扩散层中有大量针状析出相产生.经选区电子衍射(SADP)技术测定,析出相为亚稳定的ζ-(Nb, Ni)相,基体相为(Ni,Cr,Nb,C)Fe-α合金.     

Nb-1Zr与1Cr18Ni9电子束自钎焊形成的互扩散层的微观组织分析

利用扫描电子显微镜(SEM)、透射电子显微镜(TEM)和电子衍射能谱仪(EDS)分析了Nb-1Zr合金与1Cr18Ni9不锈钢在电子束自钎焊过程中形成的互扩散层的微观组织形貌、析出相成分和结构。结果表明：在电子束自钎焊过程中，两种合金的合金元素在界面处产生强烈的相互扩散，形成互扩散过渡层，互扩散以Nb向不锈钢一侧扩散为主；扩散层金相组织主要由基体组织和条状析出物组成．条状析出物呈全片层状结构。通过对析出相选区衍射花样(SADP)分析，初步确定互扩散层的析出物为μ-Fe(Ni)2Nb0和α-FeCr金属间化合物,而基体组织则为四方结构的α-Fe(Ni，Cr，Nb，C)相。     

Zr-4合金α-Zr固溶体中的Fe、Cr含量分析

将电化学分离Zr-4合金中Zr(Fe,Cr)2第二相粒子的技术和原子吸收光谱分析技术相结合，建立了一种分析Zr-4合金α-Zr固溶体中Fe,Cr含量的新方法，并用这种新方法分析了不同热处理状态下Zr-4合金α-Zr固溶体中的Fe,Cr含量。分析结果表明，随着淬火温度的增加。α-Zr固溶体中的Fe,Cr含量和Fe/Cr比值均增加，而Zr(Fe,Cr)2第二相粒子中的Fe/Cr比值则相应降低。结合以前的工作，可得结论：过饱和固溶在α-Zr固溶体中的Fe,Cr含量对Zr-4合金的耐水侧腐蚀性能有重要影响。     

Zr(Fe,Cr)_2金属间化合物在500℃过热蒸汽中的腐蚀(英文)

用非自耗电弧炉熔炼了Fe/Cr比值为1.75和4.50的Zr(Fe,Cr)_2金属间化合物,它们的粉末经500℃、10.3MPa过热蒸汽腐蚀不同时间后,用X射线衍射、电子探针和透射电子显微镜分析了腐蚀后生成物的结构及其形貌,以及成分的重新分布。Fe/Cr比值不同的Zr(Fe,Cr)_2腐蚀后的生成物都相同,但是含Cr高的更不易被腐蚀。腐蚀初期的生成物是立方ZrO_2,并析出α-Fe(Cr),在继续腐蚀时,立方ZrO_2逐渐转变为单斜ZrO_2,α-Fe(Cr)也逐渐被氧化成(Fe,Cr)_3O_4。Fe和Cr在偏聚时,Fe原子的扩散速率比Cr原子快。根据实验结果,讨论了第二相影响Zr-4合金腐蚀性能的原因。     

U-Mo合金与Zr合金的相容性研究

采用扩散偶方法研究U-Mo合金与Zr的相容性。扩散偶采用包覆热轧法制备,热处理温度为750℃和800℃,热处理时间为10 h和50 h。结果表明:U-Mo合金与Zr合金间的扩散层有分层现象,在U-Mo/Zr界面扩散反应成分复杂界面处存在类似Mo2Zr的析出物。经X射线衍射(XRD)检测表明U-Mo/Zr扩散层由M2Zr、UZr2和U等组成。U-Mo/Zr的扩散过程是U和Mo原子向Zr扩散,Mo优先与Zr反应生成Mo2Zr、U通过Mo2Zr扩散形成γ-(U,Zr)固溶体的过程。U-Mo合金与Zr具有良好的相容性。     

Zr（Fe,Cr）2金属间化合物的氧化

用非自耗电弧炉熔炼了比值(重量比值)不同的Zr(Fe,Cr)_2,并在773K和973K的空气中氧化。经X射线衍射和电子衍射分析表明:当Fe/Cr≤4.5时,Zr(Fe,Cr)_2,是MgZn_2型(六方)的Laves相,它的晶格常数随Fe/Cr比增加而收缩。Zr(Fe,Cr)_2氧化后生成的稳定氧化物是单斜ZrO_2和六方(Fe,Cr)_2O_3。在形成稳定氧化物之前,还会出现亚稳定的立方ZrO_2。根据本实验结果讨论了Zr-4合金中Zr(Fe,Cr)_2第二相对腐蚀性能的影响。     

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.