一起小剂量γ外照射事故剂量估算

本文叙述了一起小剂量γ外照射事故的情况。对受照射的六名男性儿童(9—12岁)给出了性腺剂量(9.5×10~(-3)—1.4mGy)和躯干中线平均剂量(2.6×10~(-2)—10×10~(-2)mGy。)     

无锡坠冰水的中子活化研究

本文用中子活化法研究了无锡坠冰水中的痕量元素丰度,发现坠冰水中的铱浓度为正异常,达3.16×10~(-12)g/g。利用实验结果,计算了一系列元素之间的相互比值,坠冰水中的Ir/Co、Ir/Cr、Ir/Sc、Ir/Sr、Sc/Cr和Sr/Cr比值分别为6.88×10~(-3)、2.40×10~(-4)、1.09×10~(-1)、6.28×10~(-3)、2.21×10~(-3)和3.8×10~(-2),与Cl型陨石的10.2×10~(-3)、2.08×10~(-4)、0.92     

~(60)Co和~(137)Csγ辐射场的照射量率的比对

用NPL防护水平次级标准NE2550剂量率仪对国防计量系统和有关厂矿的防护水平~(60)Co和~(187)Cs γ辐射场进行了照射量率的测量和反平方律的检验,并作了照射量率的比对。~(137)Cs γ辐射场照射量率最大相差+3.6％(2.58×10~(-6)-2.58×10~(-4)Ckg~(-1)h~(-1)),而~(60)Co γ辐射场最大相差分别为+1.4％(2.58×10~(-4)-2.58×10~(-3)Ckg~(-1)h~(-1))、+9.9％(2.58×10~(-6)-2.58×10~(-4)Ckg~(-1)h~(-1))和+24.5％(2.58×10~(-7)-2.58×10~(-6)Ckg~(-1)h~(-1))。~(60)Co和~(137)Cs γ辐射场的照射量率,在一定的距离范围内反平方律在±5％以内符合。     

饮用水中的放射性核素所造成的危险

本文对饮用水中放射性核素所造成的危险进行了评价。来自放射性核素的主要危险是自然产出的Ra、U和Rn。这些元素产出的平均水平为:~(226)Ra为1.11×10~(-2)—2.96×10~(-2)Bq/L,~(228)Ra为1.48×10~(-2)—3.7×10~(-2)Bq/L,天然铀为1.11×~(-2)—7.4×10~(-2)Bq/L,~(222)Rn为1.85—12.95Bq/L,~(210)pb为<0.41×10~(-2)Bq/L,     

用热释光剂量计对软X射线能注量的测量

本文给出两种热释光剂量计(TLD)对1.7—10keV软X射线能注量测量的刻度和使用结果。 TLD对软X射线注能量响应的刻度是以氙电离室为标准的。刻度用的X射线源包括:不同靶的荧光辐射源、~(55)Fe的X射线源和由管电压为5—15kV的X光机产生并经固有过滤的软X射线源。 关于LiF(Mg、Ti)和天然CaF_2两种TLD元件对3.3—8.64keV软X射线在全吸收(不全吸收时,给出了校正系数)情况下的响应,本文给出了灵敏度与能量无关的结果;其灵敏度分别为0.0331~(60)Co伦/尔格·厘米~(-2)和0.0327~(60)Co伦/尔格·厘米~(-2)。两种TLD在10~(-1)—10~4尔格/厘米~2能注量范围内都有良好的线性响应。     

海河水系天然放射性水平调查

通过对海河水系60个点位,720个样品的分析测定,给出了海河水系天然放射性核素浓度(Bq/L):~(238)U(21.8±1.29)×10~(-3)、~(232)Th(1.02±0.21)×10~(-3)、~(226)Ra(7.59±0.53)10~(-3) ~(49)K(87.4±18.5)×10~(-3)、总α放射性(4.50±0.50)×10~(-2),总β放射性(123.8±73.8)×10~(-2),属正常本底水平。本文还分析了海河水系天然放射性浓度分析情况及沿河系的变化规律。     

秦山核电厂辅助给水系统可靠性分析

用故障树分析方法对秦山核电厂辅助给水系统的可靠性作了点估算,使该系统在LMFW工况下的功能需求不可用度,从原设计的1,4×10~(-3)降低到改进方案之三的6.1×10~(-5),达到可接受范围10~(-4)—10~(-5),并且找出了进一步提高其可靠性的途径。     

一个机组供电的晶体管稳流电源

1983年我们制作了一台由机组供电的晶体管稳流电源,取代原苏制BT-4稳流装置,作为ЭГ-2.5质子静电加速器分析磁铁的激磁电源。主要技术指标为:(1)额定输出直流电压100 V;(2)额定输出直流电流30 A;(3)电流调节范围0—30 A;(4)电流稳定度为±1.4×10~(-5)(当负载变化±10%时),±1.0×10~(-5)(当电网电压变化±10%时);(5)长时间漂移为2.3×10~(-5)/h,5.26×10~(-5)/8 h;(6)电流纹波为8.7×10~(-5)。     

HFETR十年运行对公众辐射危害分析

根据高通量工程试验堆(HFETR)十年运行期间放射性流出物的排放量、剂量学模式与参数、以及危害估算模式,对堆址80km 范围内公众的有效剂量和辐射危害进行了计算和分析。辐射危害的最大个人危险1.34×10~(-10)—2.24×10~(-7),为可忽略的危害水平,且低于我国不同产业非辐射死亡的个人危险(10~(-5)—10~(-3));而群体危险8.45×10~(-7)—2.88×10~(-3)人·a~(-1),与堆址 80km 范围非辐射致死性癌症死亡人数(3.44—3.78)×10~3人·a~(-1)相比,也是可以忽略的。     

海相沉积物中的铀及其成矿

对内海和陆棚海沉积物及大洋沉积物中铀分布规律的研究,已能够确定海相沉积物铀的平均含量。在一些海湾的含碳黑色淤泥中,铀含量由5×10~(-3)％-6×10~(-3)％,其铀来自附近的花岗岩陆块。铀有由大洋淤泥(1.6×10~(-4)％)向内陆海淤泥(4.2×10~(-4)％-6.4×10~(-4)％)     

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.