硝酸介质中单甲基肼与亚硝酸的反应动力学

采用分光光度法研究硝酸介质中单甲基肼(MMH)与亚硝酸(HNO2)的反应。HNO2和MMH反应动力学速率方程为－dc(HNO2)/dt=kc(H+)c1.1(NO－3)c1.1(MMH)c(HNO2)。当t＝2.6℃、c(NO－3)＝0.50mol/L时,反应速率常数k=(115±2)(mol/L)－3.2•s－1,反应活化能Ea=(37.8±0.1)kJ/mol。研究结果表明：在硝酸介质中,甲基肼与亚硝酸能快速反应;提高酸度、MMH浓度或硝酸根浓度均有利于亚硝酸的还原。     

单甲基肼还原Np(Ⅴ)的反应动力学

用分光光度法研究了HNO3介质中单甲基肼(MMH)还原Np(Ⅴ)的动力学行为.通过考察还原剂浓度和酸度等条件对Np(Ⅴ)动力学过程的影响,确定了反应的动力学速率方程为-dc(Np(Ⅴ))/dt=kc(Np(Ⅴ))c0.36(MMH)c(H+),在温度θ=35℃,离子强度为2 mol/L时,反应速率常数k=0.004 79(mol/L)-1.36/min.研究了离子强度、c(U(Ⅵ))和温度对反应的影响.结果表明,离子强度和c(U(Ⅵ))对反应速率无显著影响;反应活化能为60.43 kJ/mol,随着温度的升高,反应速率加快.并在此基础上推测了可能的反应机理.     

Pu催化HNO_2氧化U(Ⅳ)的研究

研究了Pu存在条件下HNO2氧化U(Ⅳ)的反应,并考察了HNO2浓度、反应温度、HNO3浓度、Pu浓度对U(Ⅳ)氧化速率的影响。结果表明:Pu对HNO2氧化U(Ⅳ)的反应具有显著催化作用;获得了Pu催化条件下HNO2氧化U(Ⅳ)的动力学方程:-dc(U(Ⅳ))/dt=kc(U(Ⅳ))c1.3(HNO3)c1.3(NO-2),得到了29℃时的反应速率常数k=(0.69±0.04)L2.6/(mol 2.6·min)。并对反应历程进行了探讨。     

硝酸体系中AHA与HNO_2的反应动力学研究

本工作研究HNO3体系下AHA与HNO2的反应动力学。研究得到该反应的反应动力学速率方程式为-dc(HNO2)/dt=kc(HNO2)c0.25(AHA)c(HNO3)。在t=10℃、I=0.5mol·kg-1条件下,反应速率常数k=(0.4814±0.0375)L1.25·mol-1.25·s-1。实验研究了反应温度对反应速率的影响。结果表明,随着反     

双羟基脲与HNO2的反应动力学及对Pu(Ⅲ)的稳定作用

研究了HClO4和HNO3体系中双羟基脲(DHU)与HNO2的反应动力学.结果表明,HClO4和HNO3体系下DHU与HNO2的反应动力学速率方程式均为-dc(HNO2)/dt=k·c(HNO2 )1·c(DHU )0·c(H+)-0.15,反应对DHU均呈零级.在HClO4体系下,θ=15 ℃, I=0.5 mol/kg时,反应速率常数k1=(2.37±0.04) mol0.15/(L0.15·min);在HNO3体系下,θ=10 ℃, I=0.5 mol/kg时,反应速率常数k2= (1.29±0.06) mol0.15/(L0.15·min)(n=8).同时考察了反应温度对反应速率的影响,结果表明,随着温度的升高, 反应速率均明显加快, HClO4和HNO3体系对应的反应活化能分别为68.2 kJ/mol和76.8 kJ/mol.在HClO4和HNO3体系中,随着离子强度的增加,氧化还原反应的表观速率常数k'均下降.过量的DHU在HNO3溶液中可以很好的稳定Pu(Ⅲ)48 h而不被氧化.     

Ru3+和［RuNO］3+的速差动力学分析方法

建立了用速差动力学分光光度法分析同一体系中Ru³⁺和［RuNO］³⁺的方法。在盐酸羟胺存在下，测定了Ru³⁺和［RuNO］³⁺与bipy的反应表观速率常数、浓度级次及反应平衡常数。通过测量反应产物Ru(bipy)²⁺₃的起始反应速率和平衡时的浓度，由建立的相关线性方程组计算出Ru³⁺和［RuNO］³⁺的浓度。Ru³⁺和［RuNO］³⁺的回收率分别为96%~105%和95%~106%。加入EDTA能较好地掩蔽常见金属离子的干扰。     

高氯酸体系中AHA与HNO_2的反应动力学研究

本工作研究HNO3体系下AHA与HNO2的反应动力学。研究得到该反应的反应动力学速率方程式为-dc(HNO2)/dt=kc(HNO2)c0.25(AHA)c(HNO3)。在t=10℃、I=0.5mol·kg-1条件下,反应速率常数k=(0.4814±0.0375)L1.25·mol-1.25·s-1。实验研究了反应温度对反应速率的影响。结果表明,随着反应温度的升高,反应速率明显加快,相应的反应活化能?E=46.92kJ·mol-1。在离子强度I=0.5～3.0mol·kg-1范围内,氧化还原反应的表观速率常数k′随离子强度I的增加而有所增大,但增大幅度不甚明显。对该反应的机理进行了简要讨论。高氯酸体系中AHA与HNO_2…     

Purex流程中二甲基羟胺与甲基肼的分析

研究了在测定1BP中的N,N-甲基羟胺(DMHAN)和甲基肼(MMH)的浓度之前用TODGA将其中的Pu(Ⅲ)萃取出来;并基于所发现的在室温下pH为2.0～5.5时,Fe3+只与DMHAN反应而不与稀的MMH发生反应;以及在室温下pH为0～5.5时,稀的I2溶液只与MMH发生反应而不与稀的DMHAN反应;分别建立了用F...     

高氯酸、硝酸体系中乙异羟肟酸与

分别在HClO4和HNO3体系中用分光光度法研究了乙异羟肟酸(AHA)与HNO2的反应动力学,得到其反应动力学速率方程式为:—dc(HNO2)/dt=k.c(HNO2)1.c(AHA)0.75.c(HClO4)0.5和—dc(HNO2)/dt=k.c(HNO2)1.c(AHA)0.25.c(HNO3)1。在HClO4体系中,当θ=5℃,I=0.5 mol/kg时,反应速率常数k=(2.37±0.21)L1.25/(mol1.25.s);在HNO3体系中,当θ=10℃,I=0.5 mol/kg时,反应速率常数k=(0.482±0.048)L1.25/(mol1.25.s)。同时考察了反应温度对反应速率的影响。结果表明,在HClO4和HNO3体系中,随着温度的升高,反应速率均明显加快,反应活化能分别为99.0 kJ/mol和46.9 kJ/mol;随着离子强度的增加,氧化还原反应的表观速率常数k′均有所增加,但增幅不明显。     

甲醛肟与HNO_2氧化还原反应动力学

用分光光度法研究了高氯酸体系中甲醛肟(FO)与亚硝酸的还原动力学,其动力学方程式为:-dc(HNO2)/dt=kc(HNO2)c1.32(FO)c0.96(Cl O4-),其中在1.0℃时,k=(7.55±0.50)(mol/L)2.28/s,活化能Ea=(65.16±6.52)kJ/mol。增加甲醛肟浓度、高氯酸根浓度和温度,HNO2还原速度增加,H+浓度对还原反应基本无影响。     

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.     

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.