电动势法研究HAN与Fe3+氧化还原反应动力学

采用电动势法研究了硝酸体系中硝酸羟胺(HAN)还原Fe3+离子的反应动力学,得到了动力学表观速率方程-dc(Fe3+)/dt=kc0.62(HAN)c-2.80(H+)c(Fe3+)c-0.85(Fe2+);当温度为50℃、离子强度I=1.0mol/L时,表观速率常数k=(2.9±0.1)×10-6(mol/L)3.02/s,反应表观活化能Ea=(125±3)kJ/mol。硝酸根的存在对反应起到抑制作用,离子强度的增大对反应有促进作用。     

Purex流程中界面物的形成和机理研究

论述了Purex流程中萃取界面物的成因和影响因素,包括不同浓度的磷酸二丁酯、磷酸一丁酯、锆、铀和硝酸以及辐照剂量不同的磷酸三丁酯正十二烷溶液。观察了锆、钼、铌和锝在形成界面物过程中的化学行为,在低于2mol/L的硝酸溶液中,钼会进入界面物中。给出了界面物组分的主要元素磷/锆和锆/钼之摩尔比;分析研究了红外光谱;深入讨论了界面物的形成机理;导出了主要反应方程式。结果指出:萃取过程中由于生成了Zr(NO_3)_(4-n)(DBP)_n,ZrO(NO_3)_(2-m)(DBP)_m和Zr(MBP)_2等络合物而成为界面物;体系中的酸度是影响界面物形成的最敏感因素,它与氢离子浓度的1至4次方成反比。为减少界面物,选择合适的酸度条件是有效的方法。     

硝酸溶液中钼锆沉淀溶度积的研究

应用X 射线荧光分析、热重分析、X 射线衍射以及红外光谱分析法研究了钼锆沉淀的组成和特征。结果表明 ,在 1 0mol/L硝酸溶液中 ,沉淀可能是ZrMo2 O7(OH ) 2 ·2H2 O和Zr(MoO4) 2 ·2H2 O的混合物 ;在浓度为2 0mol/L以上的硝酸溶液中 ,沉淀为Zr(MoO4) 2 ·2H2 O。实验还测定了 1 0 ,2 0 ,3 0mol/L硝酸溶液中钼锆沉淀的表观溶度积K′sp,讨论了硝酸浓度、钼锆初始浓度对表观溶度积的影响。结果发现 ,硝酸浓度增加 ,K′sp值变大 ,而钼锆初始浓度的不同对K′sp没有明显的影响。     

硝酸溶液中钼和锆溶解度的测定

一、前言在核裂变过程中,钼和锆是高产额的裂变产物元素,所以在乏燃料中钼和锆的含量较高。核燃料水法后处理工艺的常用介质是硝酸,因此测定硝酸溶液中钼和锆的溶解度是有意义的。对于裂变产物的过程化学的研究工作,溶解度数据也是必要的。关于硝酸溶液中钼和锆的溶解度,前人研究得很少,数据也不全。为此,我们测定了不同浓度的硝酸中不同温度下钼和锆溶解度;还观测了硝酸根和铀浓度对钼和锆的溶解度的影响;获取的数据较全面。     

亚硝酰钌的状态变化及其某些萃取行为

在热铀后处理萃取流程中,燃烧过的铀在用硝酸溶解后,~(106)Ru在溶液中主要以亚硝酰钌(RuNO~(3 ))状态存在,Ru(Ⅳ)仅占1%左右,Ru-O-Ru含量更低,且稳定性也较差。亚硝酰钌异常稳定,它有较强的络合能力,通常形成硝酸基络合物、亚硝酸基络合物以及含水分子、氢氧基的混合配位络合物。特别是高硝酸基络合物与磷酸三丁酯(TBP)更易形成可萃络合物而难以与U,Pu分离,因此RuNO~(3 )一直是萃取过程中     

在非离子型表面活性剂水溶液中用噻吩甲酰三氟丙酮和三辛基氧膦分光光度法测定铀

UO_2~(2+)—噻吩甲酰三氟丙酮(TTA)和三辛基氧膦(TOPO)混合络合物可溶于非离子型表面活性剂水溶液中,于376nm处产生最大吸收光谱。此种水溶液在pH3.4—4.8的范围内显示出恒定的吸光度,在每毫升溶液含0—16微克UO_2~(2+)的浓度范围内比尔定律成立。克分子消光系数为2.1×104cm~(-1)mol~(-1)dm~3。由于使用了EDTA为掩蔽剂可以排除钍、锆、铁等多种离子的干扰。     

甲基膦酸二(1-甲庚)酯萃取硝酸铀酰和硝酸钍机理研究

本文研究了甲基膦酸二(1-甲庚)酯(DMHMP)苯溶液萃取硝酸铀酰和硝酸钍的机理。分别测定了萃合物的组成为UO_2(NO_3)_2·2DMHMP和Th(NO_3)_4·3DMHMP。在恒定离子强度μ=2.0时,求得了DMHMP萃取硝酸铀酰和硝酸钍的平衡常数分别为1gK_U=4.6,1gK_(Th)=4.3。同时用Leden法求出了硝酸钍络合物的四级累积稳定常数β_1=8.0,β_2=5.2,β_3=0.8,β_4=1.3,与计算机算得结果基本一致。对萃取分配比的实验值和计算值进行了比较,结果相符。还比较了磷酸三丁酯(TBP)对铀钍的萃取数据,表明DMHMP用于铀钍的分离和纯化上是一种性能优于TBP的萃取剂。     

甲基膦酸二-(1-)甲庚酯萃取硝酸锆的机理

中性磷型萃取剂甲基膦酸二-(1-)甲庚酯(简称DMHMP)在硝酸溶液中萃取硝酸锆生成三种形式萃合物:Zr(NO_3)_4·2DMHMP,Zr(NO_3)_4·2DMHMP·2HNO_3和Zr(NO_3)_4·2DMHMP·3HNO_3。用对数函数外推和优选计算相结合的方法,求得萃取反应平衡常数:K_(020)=1.09×10~3,K_(022)=6.25×10~3,K_(023)=1.50×10~4,求得Zr(NO_3)_i~(4-i)的各级积累稳定常数β_1=2.13,β_2=2.62,β_3=3.39,β_4=6.18。     

铀酰溶液中游离酸pH测量法的改进

测定铀酰溶液中游离酸的各种方法,都必须考虑到消除UO_2~(2+)水解带来的影响。消除UO_2~(2+)水解影响的方法,可以采用沉淀法、离子交换法、萃取法等把UO_2~(2+)从样品液中分离出来,也可以利用某种络合剂与UO_2~(2+)形成稳定的络合物。Ahrland利用SO_4~(2-)与UO_2~(2+)形成稳定络合物后通过pH测量,测定了低酸度(<0.3M)铀酰溶液中的游离酸。     

冠醚与铀酰盐、钍盐的络合物

本文报道了硝酸铀酰、氯化铀酰和硝酸钍与冠醚DB18CR6、B15CR5、18CR6通过溶剂反应制得的8个固体络合物,对这些络合物进行了熔点测定、元素成分测定和红外光谱分析。其中4个络合物的化学组成与文献报道不同,它们的化学式为:UO_2(NO_3)_2·2H_2O·[DB18CR6]_2;[Th(NO_3)_4]_3·[DB18CR6]_5·3H_2O;[Th(NO_3)_4]_2·[B15CR5]_3·2H_2O;[Th(NO_3)_4]_2·[18CR6]_3·2H_2O。     

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.