中国原子能科学研究院的PX-AMS系统及其应用(英文)

加速器质谱(AMS)中的入射离子X射线方法是为解决AMS测量中重核同量异位素而发展的一种方法(PX AMS),在中国原子能科学研究院建立了PX AMS方法之后,利用这套系统开展了79Se,75Se,64Cu等核素的PX AMS方法测量,基于此技术实现了79Se,75Se半衰期的测量和64Cu放射性核束强度及库仑激发截面的测量。     

79Se的AMS测量方法研究

测定⁷⁹Se时由于⁷⁹Se尚无标准样品,需要建立⁷⁹Se/Se（⁷⁹Se、Se原子个数比,余同）的AMS测量方法。在⁷⁹Se/Se的绝对测定中,为尽可能避免测量Se的同位素之间的差异,通常利用探测器测量⁷⁹Se离子,本文用法拉第筒对⁷⁸Se和⁸⁰Se进行测量,但这造成两个测量系统之间的系统误差。为避免这种系统误差,利用同一探测器测定⁷⁹Se、⁷⁸Se和⁸⁰Se。考虑到⁷⁸Se和⁸⁰Se的计数率非常高,在CIAE-AMS系统中的静电分析器前和靶室内安装衰减片以降低⁷⁸Se和⁸⁰Se的计数率。实验结果表明：通过两个衰减片的衰减作用,能将⁷⁸Se和⁸⁰Se的束流降低到半导体探测器的检测范围内,实现了样品中⁷⁹Se/Se的绝对测定,得到⁷⁹Se/Se为(2.08±0.10)×10^-7,为准确测定⁷⁹Se半衰期奠定了基础。     

79Se-AMS示踪研究亚毒性剂量亚硒酸钠摄入的硒代谢

长寿命放射性核素79Se的半衰期长达2．8×10^5a，其放射性比活度（单个原子的活度）约1×10^-14Bq。79Se衰变时仅放射出能量为150．7keY纯β射线，对生物组织甚至细胞的辐射损伤远小于75Se，而79Se的加速器质谱测量方法（795e—AMS）具有灵敏度高、相对测量准确性高以及测量精度高等特点，因而适合于长周期、无损伤的生物示踪研究。     

Determination of ^129I in IAEA-375 Reference Material

^79Se是一长寿命、纯β裂变产物核素，β能量为0．151MeV。^79Se半衰期已被测量过5次，每次测得数据间在误差范围内不吻合。随着新的测量手段的不断涌现，对^79Se半衰期重新进行测量很有必要。     

放化分析高放废液1AW中的~(78)Se

应用以溴化硒蒸馏和元素硒沉淀为主要步骤的放化流程,从高放废液1AW中分离出纯的~(79)Se。应用低本底液闪谱仪测量~(79)Se,得到了1AW中~(79)Se的含量。     

从高放废液中分离79 Se的流程研究

建立了离子交换法与沉淀法相结合的、从高放废液中分离79Se的放化流程.该流程具有去污效果好的特点,对137Cs,90Sr,90Y,99Tc,154Eu的去污因子大于104,对125Sb,113Sn的去污因子大于103,对237Np为2×102.整个流程的收率约为53%.由该流程分离出的79Se样品能够很好地满足液闪测量和质谱测量的要求.     

发射光子的放射性核素各向同性点源的剂量学常数(续Ⅰ)

发射光子的放射性核素各向同性点源的剂量学常数 1)Dosimetric constant table of isotropic point source of radionuclides emitting photons母　　　　　　体核素半衰期衰变方式放　射　性　子　体核素半衰期产　　额空气比释动能率常数(a Gy· m2 )照射量率常数[( a C/kg)· m2 ]周围剂量当量率常数(a Sv· m2 )定向剂量当量率常数(a Sv· m2 )7Be 5 .330× 10 1d EC 1.86× 10 0 5 .48× 10 -2 2 .30× 10 0 2 .30× 10 011C 2 .0 38× 10 1m EC,β+ 3.87× 10 11.14× 10 0 4.75× 10 14 .75× 10 113 N 9.96 5× 10 0 m EC,β+…     

Chemical Form of Selection for ~(79)Se Measurement With AMS

79Se is a long-lived radionuclide which is produced from nuclear waste, and the half-life is (2.80±0.40)×105 a. Recently, owing to the potential implications of Se in the field of biomedical research and environment science research, measuring the content of the trace element79Se in the biological     

液体闪烁谱仪测量~(90)Y半衰期及其不确定度分析

~(90) Y是一种非常重要的治疗用放射性核素,准确测定~(90) Y的半衰期对理论研究和实际应用均具有重要意义。目前对~(90 )Y半衰期的测定已有大量文献报道,但是测定结果不确定度较大,从63.46h到64.6h不等。本工作利用液体闪烁谱仪对HDEHP-甲苯直接萃取的纯~(90) Y半衰期进行测定,并给出了结果的不确定度。~(90) Y半衰期的测定结果为64.05h,不确定度为0.017%。     

~(65)Se半衰期的测定(英文)

通过β延迟质子发射鉴定出了在~(40)Ca(~(28)Si,3n)反应中产生的一个具有T_z=-3/2,A=4n 1的核素~(65)Se。观察到其单质子能量为3.70±0.08MeV,实验测定的半衰期为9.6_(-4.1)~( 5.3)ms,它相应于由~(65)Se基态到~(65)As中最低的T=3/2相似态的超允许β跃迁和随后由此态到~(64)Ge基态的质子发射。基于这些结果并结合库仑位移能计算,得到~(65)Se的质量剩余为-33.26±0.25MeV。     

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.