锆合金薄壁细管的单调拉伸与低周疲劳试验研究

利用自行研制的高温夹具完成了Zr-1Nb合金和Zr-4合金薄壁短管试样不同温度下的单调拉伸和375℃下的等幅低周疲劳试验,获得了两种锆合金的单调和循环本构关系及Manson-Coffin寿命估算模型。研究结果表明：Zr-1Nb合金和Zr-4合金的弹性模量、屈服强度、抗拉强度以及应变硬化程度明显下降。随着温度的升高,温度对Zr-4合金的应变硬化程度的影响逐渐减弱;应变速率对Zr-4合金的拉伸性能的影响微弱。在等幅应变循环过程中,Zr-4合金表现为循环硬化,应变幅越低,硬化现象越明显;Zr-1Nb在较低应变幅下表现为循环硬化特性,而在较高应变幅下表现为循环软化。相对于单调拉伸行为,Zr-4合金在不同温度下的循环行为均表现出明显的强化特性。     

Zr-4合金低周疲劳特性研究

研究了再结晶态Zr-4合金板材在室温和400 ℃下的低周疲劳特性.Zr-4合金在室温下的循环变形行为与应变幅有关,当应变幅小于0.8%时,表现为循环软化;应变幅大于0.8%时,表现为循环硬化.在400 ℃下均表现为循环硬化.合金在室温和400 ℃下,均遵循Coffin-Manson关系.在低应变幅下,室温的低周疲劳性能明显优于400 ℃下的低周疲劳性能,随着应变幅的增加,两者寿命趋于接近.用扫描电子显微镜观察分析了合金在室温和400 ℃下的疲劳断口特征.     

Zr-Sn-Nb薄片合金高温低周疲劳行为

采用Zr-Sn-Nb合金薄片漏斗试样,完成了室温和500℃高温下的低周疲劳试验,提出基于漏斗根部节点轴向应变的疲劳损伤等效假设。根据有限元分析,建立了Zr-Sn-Nb合金室温和高温下薄片漏斗试样测试应变到漏斗根部轴向应变的转换模型。结合低周疲劳试验结果,建立了在室温和500℃高温条件下用于估算Zr-Sn-Nb合金疲劳寿命的Manson-Conffin模型。结果表明:Zr-Sn-Nb合金具有循环稳定性;高温严重影响了Zr-Sn-Nb合金低应变幅下的疲劳寿命,随着应变幅的增加,温度影响趋弱。     

N18合金薄壁管高温应变循环与疲劳行为研究

应用新型自研夹具对N18合金薄壁短管进行400℃下的单轴拉伸和等幅低周应变疲劳试验。试验结果表明：N18短管高温循环应力应变滞回线有良好对称性；等幅循环下短管试样在较低应变幅下表现出循环硬化特性，而在较高应变幅下表现出循环软化；在多级应变循环加载下短管试样应力幅在循环中均保持稳定，循环本构关系不受多级应变循环工况差异的影响；材料循环特性不符合Manson律。获得了用于N18合金在400℃高温下的几个寿命估算式。     

织构对Zr-4合金循环变形行为的影响

研究了织构对Zr-4合金循环变形行为的影响及其作用机制。结果表明，(1)合金的低周疲劳寿命遵循Coffin—Manson关系N^(β)f△εpC。在给定△εp时，轧向的寿命比横向的长。随△εp的降低，两个方向的疲劳寿命差别增大；(2)在低应变幅，合金表现为循环软化直至疲劳破坏在高应变幅，循环变形的初期表现为循环硬化，随后是循环软化直至疲劳破坏在应变幅恒定时，随着循环次数的增加，晶粒发生转动，使晶粒有更高的Schmid因子；(3)半寿命时的σs随εp的变化遵循乘幂关系σs=K^sε(^n^s),σid随σp的变化则遵循对数关系σid=K^blnεp Cb；(4)轧向和横向之间循环变形行为的差别是由于织构效应的缘故。     

N18锆合金的低周疲劳行为

在不同试验温度（室温～500℃）下,对N18合金进行了低周疲劳试验。试验结果表明：室温～300℃温区,合金表现为明显的循环软化;400、450℃时,合金逐渐呈现循环硬化,450℃时其硬化现象更为明显;500℃时则主要表现为循环饱和。随着温度的升高,疲劳寿命先增加后降低,300℃时疲劳寿命最高。低应变幅下,温度对疲劳寿命的影响更明显。通过疲劳断口SEM分析,室温下疲劳起源于单个裂纹源,疲劳裂纹扩展阶段的微观特征主要是疲劳条纹,局部区域出现轮胎状花样。在高温下为多裂纹源,大量二次裂纹的存在是高温疲劳断口的主要特征。     

考虑温度效应的钛合金钢低周疲劳行为研究

完成了在室温与３５０℃高温下国产新材料Ｔ４２ＮＧ和Ｔ２２５ＮＧ钛合金钢的拉伸与低周疲劳系列试验研究，获得了四个单调Ｒ－Ｏ本构模型和四个Ｍ－Ｃ寿命估算模型。以这些模型为基础，系统地研究了材料的循环强化与软化规律，研究了温度系数λσ、λ△σ和λＮｆ对材料静强度、循环强度和低周疲劳规律的影响效应。根据温度对寿命的影响系数λＮｆ与应变幅△ε／２呈线性规律这一重要发现，提出考虑了温度效应、用于高温低周疲劳寿     

316不锈钢室温和350℃低周疲劳性能研究

采用MTS材料试验机研究作为反应堆结构材料的316奥氏体不锈钢母材在350℃和室温,以及焊缝在室温,±0.3%~1.5%应变幅的低周疲劳性能试验,并采用扫描电镜对试验后样品进行了断口分析。研究结果表明,316不锈钢疲劳性能较好,室温下疲劳寿命高出350℃同一应变幅的30%~50%以上,且母材的疲劳寿命显著高出焊缝同一应变幅的一倍以上。随应变幅的增加,材料疲劳寿命相应下降,峰值应力增加。室温下母材和焊缝均呈现出随循环周次增加、峰值随应力逐渐下降的规律。母材在高温下,随应变幅的增加,逐渐由循环硬化过渡到饱和行为。低周疲劳试验后,断口表面可观察到裂纹源和疲劳条带。随应变幅增加,疲劳条带间距增大,且同一应变幅下,焊缝的间距大于母材,高温的疲劳间距大于室温,与疲劳试验结果相吻合。     

锆合金的低周疲劳行为及其机理

锆合金的低周疲劳寿命遵循Coffin-Manson关系NβfΔεp=C1 .冶金状态、试验条件等皆影响锆合金的低周疲劳寿命.疲劳裂纹易在塑性应变不协调的区域形核,其扩展速率可用Paris公式表示为dα/dN=C2(ΔK)n .循环变形中的流变应力可分为摩擦应力和背应力.锆合金在循环变形中所呈现出的循环硬化、软化以及循环饱和状态主要取决于试验温度和应变幅,其作用机制各不相同.位错线、位错条带、胞结构和迷宫结构是锆合金低周疲劳典型的位错组态.     

316LN不锈钢在高温高压水环境下的腐蚀疲劳行为研究

在室温纯水、高温纯水及高温硼锂水环境下开展了316LN不锈钢在不同应变幅加载下的腐蚀实验研究,并获得了3种条件下的腐蚀疲劳寿命曲线。结果表明,316LN不锈钢在加载过程中出现了先硬化后软化现象,且随循环周次增加,应力峰值逐渐下降;高温纯水及高温硼锂水环境下材料的腐蚀疲劳性能下降,加速了材料的腐蚀疲劳失效;在高应变幅条件下高温的软化作用占主要影响,低应变幅条件下腐蚀作用占主要影响;试验后的样品断面上均可观察到疲劳辉纹、滑移变形带及二次裂纹,高温水腐蚀环境会加速裂纹扩展,加速疲劳失效。     

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.