辐射监测系统通讯效率改进

Modbus是核电厂及其他核设施辐射监测系统设备常用的通讯协议,该协议通过串口通讯将辐射监测仪表的测量信息和设备状态传输至控制系统。目前国内辐射监测系统通讯效率仍存在一定问题,适当修改后可以大幅提高。本文介绍了基于该协议的通讯效率改进方法,并分析计算了改进前后的通讯时间及通讯效率。     

基于串口通讯的远距离辐射监测系统的体系构成

提出了一种基于RS—232通讯的远距离辐射集散监测系统的体系构成。该集散测控系统的优点是体系构成简单、性能可靠;通讯距离远、覆盖范围大,适合于核辐射环境下应用。还讨论了构成该系统的主要硬件设备及通讯协议。     

秦山核电基地第二代外围环境γ辐射连续监测系统运行10年回顾

浙江省辐射环境监测站于2002年底在秦山核电基地周围建造了第二代环境γ辐射连续监测系统,该系统主要由测量子系统、数据采集子系统、秦山数据汇总站和杭州数据处理中心组成,多次监测到由核电厂排放烟羽引起的剂量率升高现象。随着监测手段的日趋多样化、计算机技术的不断发展和通讯技术的快速进步,根据连续监测系统的运行情况和监测技术发展的需要,在运行过程中,适时地对连续监测系统的监测设备、通讯网络等硬件和软件进行了几次升级和改造。截至2013年1月该系统已经稳定运行了10年,文章介绍了该系统组成及系统升级与改造情况,并就这10年来系统运行中发现的问题进行了探讨,提出了环境γ辐射连续监测系统建设的建议。     

核电站辐射监测系统管理软件设计与关键技术研究

主要介绍了一种基于C/S架构的核电站辐射监测系统管理软件- KRTStudio.该系统管理软件用于核电站辐射监测系统的数据采集和信息管理,主要功能包括:核电站正常运行和事故情况下辐射场数据采集,数据存储、显示,打印,报警,用户管理以及对数据采集装置的管理,并具有与核电站DCS系统进行通讯的功能.该管理软件在中广核广西防城港核电站的辐射监测系统中得到应用,为推进核电设备国产化做出了有益的贡献.     

辐射监测仪表在深圳大运会上的应用

以深圳大运会项目为背景,全面介绍了辐射监测仪表在大运会辐射监测方面的应用.首先阐述了深圳大运会辐射监测项目及各个场馆对辐射监测的要求;然后针对大运会辐射监测要求,制定了相应的辐射监测方案,并对辐射监测仪表测量数据的传输以及数据处理系统进行了简要介绍.最后,以大运会辐射监测设备的调试为例,介绍了辐射监测数据的传输以及处理过程.     

合肥光源辐射剂量监测系统

合肥光源原有的辐射监测系统是为衰减运行模式而设计建造的。为了更好地促进用户实验的科研产出,合肥光源正在进行恒流运行关键系统改造。在改造中,为了保障实验人员和设备的安全,根据恒流运行要求增加了辐射剂量监测点和完善了安全联锁功能。系统基于EPICS开发,由探测器、通讯模块、数据采集监测软件、数据分析系统等组成。该系统既能监测光源区及周边的辐射剂量率水平,还具备计算积分剂量、历史剂量查询以及必要的安全联锁等功能。新系统已经运行三个多月,系统稳定可靠,能很好地满足合肥光源恒流运行模式对辐射监测的要求。     

应急环境辐射监测系统

本发明实施公开了一种应急环境辐射监测系统,该系统包括环境监测车和中心站应急环境辐射监测计算机网络系统,环境监测车配备车载7辐射自动监测仪、全球卫星定位系统GPS、两种可互为转换的无线通信设备以及安全可靠的车载供电设备,确保了系统设备运行的稳定性和实时监测和传输的可靠性。中心站应急环境辐射监测计算机网络系统采用以地理信息GIS为软件平台的数字化电子地图技术,     

基于LoRa的γ辐射监测系统设计及应用

核能科学与技术和人们的生活联系紧密,但同时核辐射也可能危害人们的身体健康,因此需要加强对核辐射的监测。有线核辐射监测系统布线复杂、施工周期长、成本较高,且移动性差、故障排查较为困难。为了满足便捷测量γ辐射环境的需求,基于LoRa无线通信技术,设计了γ辐射监测系统。该系统的主要功能包括数据采集、数据处理及数据传输,采用硅光电倍增管（Silicon Photomultiplier,SiPM）闪烁体探测器进行数据采集,STM32单片机作为核心处理器对采集的数据进行处理、打包,由LoRa无线通信模块进行数据传输。针对可能存在的因复杂电磁环境、传输距离等因素导致监测系统断线及数据传输频繁时造成的区域内信道拥堵问题,设计了动态最优路径通讯算法,通过筛选中继节点,寻找最优重连路径以及实现数据发送的优先级分配。实际测试结果表明：闪烁体探测器测试辐射数据结果可靠,且基于LoRa的γ辐射监测系统数据传输稳定性达到99.57%以上。该系统具有组网灵活、传输距离远、成本低、拓展性强等优点,具有广泛的应用前景。     

111-2#放射性排风中心完成PIG在线监测系统安装及试运行

正2015年7月,111-2#放射性排风中心原有PIG在线监测系统发生故障无法正常运行,经生产厂家现场检查后确认:1)气溶胶探测装置β本底异常升高;2)碘探测装置探测结果远高于真实水平;3)真空泵异常发热同时无法启动。以上问题厂家无法解决,院决定对PIG在线监测系统进行升级改造。2017年3月份辐射安全研究所与719所、放射化学研究所等相关单位,完成了111-2#放射性排风中心辐射监测控制室PIG在线监测设备的安装、调试和校准工作。现场安装,台架搭建过程顺     

核电厂辐射监测系统特点及发展趋势分析

辐射监测系统是保障核电厂工作人员、公众和环境辐射安全以及核动力系统安全运行的重要系统。本文介绍了二代、二代加及三代压水堆核电厂辐射监测系统的特点,探讨分析压水堆核电厂辐射监测系统的框架体系、智能化报警技术以及事故后监测技术等方面的发展趋势,为压水堆核电厂辐射监测系统的设计、运行管理以及新型辐射监测设备的研发提供参考。     

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.     

有效探测面积大于1000 cm2的正比计数器测量系统性能测试

为对自制的活性面积高达1 000 cm²的大面积源进行表面发射率定值,同时作为现有2πα、2πβ表面发射率标准装置能力的扩充,研制了一套内置式大面积2π多丝正比计数器测量系统,并利用活性区直径为8 mm的²⁴¹Am点源及活性区面积为10 cm×15 cm的大面积²⁴¹Am和⁹⁰Sr-⁹⁰Y源对其进行计量学性能测试。结果表明：计数器内计数响应均匀性优于±0.4%,有效探测面积达1 400 cm²;所得²⁴¹Am源高压坪曲线的坪长为1 400 V,坪斜为0.27%/100 V,坪区内计数变化为0.87%;⁹⁰Sr-⁹⁰Y源高压坪曲线的坪长为300 V,坪斜为0.75%/100 V,坪区内计数变化为0.80%;10次测量重复性好于0.4%,8 h内短期稳定性好于0.3%,1 a内长期稳定性好于0.8%。     

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.     

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.