~(241)Am混合α源中微量~(242)Cm测量技术研究

提出了一种~(241)Am中微量~(242)Cm的直接测量方法,确定了~(242)Cm α粒子可测量的计数率下限为1×10~(-5)/s,研究并确定~(241)Am对~(242)Cm测量的主要应影响是脉冲叠加效应的影响。采用组合测量方法,得到不同~(241)Am峰计数率条件下可测量的~(241)Am与~(242)Cm α强度比,对~(241)Am中微量~(242)Cm实验测量具有一定的指导意义,对类似混合α源实验测量有一定的参考意义。     

堆照钚靶中钚及超钚核素的核物理测定方法

本文介绍了用Si(Au)面垒型探测器α谱仪,α-γ符合谱仪,高纯锗γ谱仪,Si(Li)谱仪,栅网电离室α谱仪等探测装置,对在反应堆中辐照钚靶所生成的~(238)Pu,~(239 240)Pu,~(242)Pu,~(241)Am,~(243)Am,~(242)Cm,~(243)Cm和~(244)Cm等核素进行了定性和定量测定,描述了这些方法的特点、基本原理和测量装置,给出了相对和绝对测量的结果。     

Preparation of ~(242)Cm

This work concerns in the preparation of carrier-free 242Cm (T1/2=162.8 d,α-decay). The 242Cm was produced via reaction1 / 2241 242 β242Am(n, γ) Am ?T? =??16 h?→ Cm. The reaction cross section is 553× 10-28 m2,few reaction products are produced simul     

~(241)Am俘获反应中~(242)Cm α粒子测量方法研究

241Am发生中子俘获反应,主要生成激发态的242Amg(83.7%),242Amg通过β衰变生成242Cm,242Cmα粒子的最低能量比241Amα粒子的最高能量高约500 keV。用SRIM程序模拟了两种能量的α粒子在铝箔中的穿透情况,26μm的Al箔可以将241Am的α粒子完全吸收掉,242Cm的α粒子对26μm的Al箔穿透率达99.7%。在探测器前加26μm吸收铝箔,可以排除241Amα粒子对242Cm的α粒子测量的影响,实现242Cmα粒子的测量。     

应用几种谱仪测定大量~(242)Cm中的少量~(241)Am

本文介绍了用Si(Li)谱仪,Ge(Li)谱仪和α-γ符合谱仪测定大量~(242)Cm中少量~(241)Am杂质的方法。描述了三种方法的特点,并比较了它们的测量灵敏度和准确度。     

~(242)Cm的制备

242Cm(T1/2=162.8d,α衰变)可由1/2241242β242Am(n,γ)Am?T?=??16h?→Cm产生,活化截面为553×10-28m2,同时生成少量其他反应产物。采用阴离子交换法-甲醇-硝酸体系进行分离纯化,可获得纯度较高的242Cm。本工作选用HZ201型阴离子树脂,粒度为0.125～0.096mm,离子交换柱内径1.7mm     

锂玻璃微珠固体闪烁流线监测器

文章描述了一种新型的流线监测器,可直接用于监测高压离子交换流出液中的α和低能β放射性。采用铈激活锂玻璃微珠为固体闪烁体。监测器对~(241)Am,~(242)Cm α射线的绝对探测效率分别达到85.8%,92.8%。对~(14)C,~(90)Sr-~(90)Y的β射线则分别为62.1%和88.6%。在~(241)Am总加入最为7.4Bq,淋洗峰半宽度为0.22ml时,仍能给出清晰的淋洗曲线。     

居里级~(242)Cm的制备新工艺

~(242)Cm是一种α放射性比度很高(3.3Ci/mg)的核素,所以能应用于国民经济和科学研究。它的制备方法国内外都有报道,但都比较复杂。 本文根据近年来的研究成果和制备居里级~(242)Cm的具体要求制订了新的流程。将60mgAmO_2与少量的Al粉混合后制靶,置于我所重水反应堆Φ_(th)=6×10~(13)n/cm~2·s位置照射9.4     

综合提取锕系和镧系元素工艺流程中Am(Cm)的测定

本文研究了从强放废液中综合提取锕系和镧系元素过程中Am(Cm)的测定。采用0.05 MPMBP-0.025MTOP/环己烷溶液协同萃取Am(Cm),以三倍于有机相体积的二甲苯稀释荷载有机相,再用0.05M DTPA-1.0M乳酸(pH=3,下同)溶液定量反萃Am(Cm)。在0.2MHDEHP/煤油和0.05MDTPA-1.0M乳酸萃取体系中将Am(Cm)与剩余镧系元素分离。最后制源,测定Am(Cm)α放射性强度。方法对样品中Am(Cm)的回收率为(97.0±5.4)%     

α粒子在硅内产生电子-空穴对平均能耗的测定

利用~(242)Cm,~(241)Am,~(239)Pu,~(210)Po α放射源测量了α粒子在金硅面垒型半导体探测器中产生一对电子-空穴所消耗的平均能量,得到ε=3.64±0.02电子伏,与国外的测量结果进行了比较。     

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.