新型蒸汽发生器泄漏监测装置的研制

本装置的工作原理是基于堆芯中子与冷却剂中轻水或重水中的氧同位素16O、18O核反应时,其放射性产物16N、19O的半衰期各不相同,由于16N和19O从堆芯通过不同的泄漏点到达探测点所经历的路程不同,因此16N和19O的活度比值也随之不同,通过所测得的不同活度比,则可以反推出U形管泄漏的位置.将研制的监测装置在本院游泳池反应堆一回路水取样室进行了测量.结果表明,本装置性能良好,达到了设计的要求.     

Design and development of a synchronized operation control system for Thomson scattering diagnostic on J-TEXT

A Thomson scattering diagnostic system is under construction at the Joint Texas Experimental Tokamak (J-TEXT).A 1064 nm Nd:YAG laser with 50 Hz repetition rate is used as the laser source.We have used a software for careful and precise control of the laser through serial communication.A time sequence operating system has been developed to synchronize the laser control and data acquisition system with the central control system (CSS).The system operates commands from the CSS of J-TEXT and generates triggers for the laser and data acquisition system in the proper sequence.It also measures an asynchronous time value that is needed for accurate time stamping.All functions are served by a field-programmable gate array development platform that is suitable for high-speed data and signal processing applications.Several embedded peripherals,including Ethernet and USB 2.0,provide communication with the CSS and the server.     

On-line monitoring system development for single-phase flow accelerated corrosion

Aged nuclear piping has been reported to undergo corrosion-induced accelerated failures, often without giving signatures to current inspection campaigns. Therefore, we need diverse sensors which can cover a wide area in an on-line application. We suggest an integrated approach to monitor the flow accelerated corrosion (FAC) susceptible piping. Since FAC is a combined phenomenon, we need to monitor as many parameters as possible and that cover wide area, since we do not know where the FAC occurs. For this purpose, we introduce the wearing rate model which focuses on the electrochemical parameters. Using this model, we can predict the wearing rate and then compare testing results. Through analysis we identified feasibility and then developed electrochemical sensors for high temperature application; we also introduced a mechanical monitoring system which is still under development. To support the validation of the monitored results, we adopted high temperature ultrasonic transducer (UT), which shows good resolution in the testing environment. As such, all the monitored results can be compared in terms of thickness. Our validation tests demonstrated the feasibility of sensors. To support direct thickness measurement for a wide-area, the direct current potential drop (DCPD) method will be researched to integrate into the developed framework.     

环境辐射水平实时监测系统的构建与实现

介绍了三种结构的环境辐射水平实时监测系统的组成,以及其中最新一种结构的系统数据库内容.     

A semi-empirical approach for predicting two-phase flow discharge through branches of various orientations connected to a horizontal main pipe

The subdivision of two-phase flow in branching conduits consisting of a large horizontal main pipe with upward, downward, or lateral branches of reduced diameter is of great interest in various technological fields. For example, these conduits are important in light-water nuclear reactors (LWRs) in the case of a small break loss-of-coolant accident (SBLOCA) in a leg of the reactor's primary coolant loops, as well as for breaks or valve malfunctions in a large pipeline. In these kinds of circumstances, the relevant phenomenology often involves phase stratification coupled with possible liquid entrainment or gas pool-through phenomena. Therefore, these phenomena were studied in depth to evaluate the pressure drop across conduit elements resulting from the redistribution of flow phases and the discharged mass among them. In the past, several experiments have been performed along with studies in flow modelling. As a result, several formulae and models for branch exit quality and consequent discharge mass flow rate predictions have been proposed.In recent years, we have been engaged in extensive research on this subject, resulting in a new semi-empirical formulation to express branch exit quality in terms of the physical processes taking place in the conduits, the operating parameters and the branch geometry. In this paper, we applied these correlations to representative sets of experiments previously reported in the literature, comprising a wide range of branch-to-main-pipe diameter ratios and operating pressures, which proved our formulation to be very accurate.     

Experience with the TÜV pipe monitoring system at the Grohnde nuclear power station

A special pipe monitoring system has been developed by TÜV Rheinland during the construction, commissioning and operation of the Grohnde nuclear power station. On the basis of measurements during construction and commissioning a basic monitoring system has been developed, using not only a system of sophisticated sensors that had been permanently installed from the beginning but also a large number of quite simple additional sensors. Measurements were taken before, during and after inspections and led to the discovery of unexpected and high stresses during service as well as to long-term changes over a period of years.Special measurements were taken with high temperature strain gauges and thermocouples to identify problems such as temperature layering. A special on-line measuring device was developed and used for the continuous monitoring of temperatures during operation.All these measurements help to identify out areas with high stresses or service conditions giving rise to high loads, in order on the one hand to prevent damage and on the other hand to prove that the pipes are functioning within their design parameters without problems.     

An industrial CT system for monitoring a running aero-engine

In order to improve aerodynamic performance and efficiency, monitoring the geometry and position information of the internal structure with the aero-engine under various operational statuses is an important task. In this paper, a novel design of industrial computed tomography(ICT) system with a linac as X-ray source is proposed to complete the task. The major advantage of the proposed system is that it can provide visualized images of internal structures of the running aero-engine without physical disturbance, which makes it possible to extract the accurate geometry information. The main idea behind this design is to measure the projection data from various views for reconstructions making use of the rotations of the aero-engine blades, instead of the mechanical rotations in the conventional ICT system. However, due to high speed rotation of the aero-engine blades,the system faces more challenges than conventional ICT systems both in data acquisitions and reconstruction algorithms. The challenges and corresponding solutions are presented in this paper. In conclusion, the proposed ICT system provides a powerful tool for monitoring the running aero-engines.     

VXI平台直线加速器监控系统

介绍了直线加速器监控系统的研制。系统采用一套ＶＸＩ总线系统,实现了直线加速器的一些相关物理量的集中式控制、各种波形参数的实时监视和存储以及测试报告的生成,为运行人员调机带来方便,同时也为机器研究提供了可靠的数据。     

网格计算环境的信息和监视系统实现研究

整合全球范围多单位的资源,如计算资源、存储资源、网络资源,以及不同地域具有各种专长的人力资源和昂贵的智能设备。网格就是针对当今科学研究的这些特点提供支持的计算技术,因而将会成为未来科学的一种基础设施。作为一种全球范围内的计算技术,需要解决许多关键的技术。将介绍网格的体系结构、安全基础设施,以及设计的网格信息管理与监视系统等。     

A diagnostic system for identifying accident conditions in a nuclear reactor

The objective of this study is to develop a system, which assists the operator in identifying an accident quickly using ANNs that diagnoses the accidents based on reactor process parameters, and continuously displays the status of the nuclear reactor. A large database of transient data of reactor process parameters has been generated for reactor core, containment, environmental dispersion and radiological dose to train the ANNs. These data have been generated using various codes e.g., RELAP5—thermal-hydraulics code for the core. The present version of this system is capable of identifying large break LOCA scenarios of 220 MWe Indian PHWRs. The system has been designed to provide the necessary information to the operator to handle emergency situations when the reactor is operating. The diagnostic results obtained from ANNs study are satisfactory.     

Multi-Faraday-cup-type beam profile monitoring system for a dual-beam irradiation facility

A multi-Faraday-cup-type ion beam profile monitor (BPM) with simplified readout circuit for use in dual-beam irradiation experiments is described.     

Metrology forγ-radiation spectrometry in a radiation monitoring system

Rudgeofizika All-Union Scientific-Research Institute of Prospecting Geophysics. D. I. Mendeleev All-Union Scientific-Research Institute of Metrology Scientific-Production Enterprise. Translated from Atomnaya Énergiya, Vol. 73, No. 5, pp. 387–392, November, 1992.     

SSRF数字化电源巡检系统的设计

开发了SSRF数字电源巡检系统,实现远程巡检与本地巡检两种模式,采用LabVIEW软件开发平台设计了简单美观的用户界面,两种硬件结构在数字化电源巡检用户软件界面上不需修改.远程巡检用于模拟数字化电源与中央控制室间远程监控通讯的调试,及时排查远程通讯或电源的故障;本地巡检可同时检测18台数字化电源,长期(24 h)进行故障状态监视,并通过Excel或text记录与保存,进行电源性能指标验收.两种巡检模式已用于SSRF的数字化电源巡检.     

Data monitoring system of technical diagnosis system for EAST

<正>Technical diagnosis system(TDS)is an important subsystem to monitor status parameters of EAST (experimental advanced superconducting tokamak).The upgraded TDS data monitoring system is comprised of management floor,monitoring floor and field floor.Security protection,malfunction record and analysis are designed to make the system stable,robust and friendly.During the past EAST campaigns,the data monitoring system has been operated reliably and stably.The signal conditioning system and software architecture are described.     

Development of a novel system for monitoring tritium in gaseous form

Tritium real-time measurement in glovebox or workplace is important to ensure safe operation of tritium. A novel tritium monitor system including an open-walled ionization chamber, an electrometer and an IPC(Industrial Personal Computer) has been developed to measure tritium in gaseous form. Using mesh walls, instead of sealed wall, the open-walled ionization chamber has less tritium absorption and lower memory effect. In addition, tritium gas can diffuse into the chamber's sensitive region without the assistant of sampling system and ion trap, which are installed at the front-end of commonly used flow-through ionization chambers. Background signal of this monitor system is about 3.7 × 105Bq/m3, and after exposed to tritium concentration at about 1011Bq/m3 for 4h, background of the monitor can recover after purging it several times with dry air. It is suitable for longtime tritium measurements in both glovebox and workplace.     

An analysis of the water-level monitoring system for a boiling-water reactor

The water-level instrumentation system is very important to the overall safety of a BWR. This system is being monitored by the Safety Parameter Display System (SPDS) that is being installed in Georgia Power Company's Plant Hatch. One of the most significant functions of the SPDS is the comparison of redundant instrument readings and formation of the best estimate of each parameter from those readings which are consistent. When comparing water-level instrument readings, it is necessary to correct the individual readings for differences between current and calibration conditions as well as for differences between calibration conditions for the multiple instruments. This paper documents the examination of the water-level instrumentation system at Plant Hatch and presents the development of the equations that were used to determine the differences between indicated and actual water levels.     

Requirements for a radiation monitoring system in connection with risk and dose

Conclusions In summary, we have arrived at the seemingly paradoxical conclusion that the requirements for the radiation-monitoring system in region 2, where by definition the average individual dose is less than in region 1, are higher. Conversely, it would seem that if the dose load is smaller, then there is no need to complicate the monitoring system; for example, it is sufficient to establish a monitoring level that is the same as in region 1. The paradox is solved if one takes account of the fact that the lower dose loads in region 2 are associated with the lower content of radionuclides in objects in the environment, i.e., the relatively small useful signals, detected by the given monitoring system. This requires better monitoring systems, since weak signals must be detected and discriminated under conditions of random noise, due to background sources of inoizing radiation and other types of noise. In conclusion, we note that the materials presented in this paper make it possible to distinguish the radioecological environment in two regions quantitatively. Specifically, it must be assumed that regions 1 and 2 have the same radioecological state ifK ₁ ^* <K ₂ ^* ;D ₂<D ₁;N ₁≪N ₂ and ln(K ₁ ^* /K ₂ ^* )<K _thr(K ₂ ^* −K ₁ ^* )/(K ₁ ^* K ₂ ^* ). The latter approximate relation follows from Eq. (3) and the conditiong ₁(K _thr)<g ₂(K _thr), whereK _thr is the threshold value or the control level of the yearly effective collective dose andg(K) is the distribution density of the effective collective dose. Under these conditions, the requirements imposed on the radiation monitoring system in region 2 are more stringent than for an analogous system in region 1. Moscow Scientific and Industrial Association “Radon.” Translated from Atomnaya énergiya, Vol. 88, No. 6, pp. 476–480, June, 2000.     

EAST托卡马克装置的核辐射监测系统

EAST(Experimental Advanced Superconducting Tokamak)现阶段D-D运行产生2.45 Me V聚变中子及次级核反应γ射线,为了解EAST运行期间辐射场的分布及强度,确保运行期间人员及环境的核辐射安全。针对EAST运行期间装置大厅内部存在较强的中子、伽马瞬变辐射场的特征,结合环境低本底辐射监测的需要,采用宽动态范围、快时间响应的场所辐射监测探测器,与高灵敏度、稳定性好的环境辐射监测探测器相结合的方式,围绕EAST装置布置13个辐射监测点,每点分别安装一台中子、伽马监测器。采用自行编写的Lab VIEW辐射监测软件进行数据采集,组建了一套EAST托卡马克装置的中子、伽马辐射剂量监测系统。该系统在2015年春季EAST实验中连续稳定运行了三个月,可靠性较高,获取了大量实验数据。监测系统满足EAST核辐射监测的要求,同时为后续开展聚变堆辐射安全与防护研究提供实验平台。     

Design and development of the beamline for a proton therapy system

A proton therapy(PT)facility with multiple treatment rooms based on the superconducting cyclotron scheme is under development at Huazhong University of Science and Technology(HUST).This paper attempts to describe the design considerations and implementation of the PT beamline from a systematic viewpoint.Design considerations covering beam optics and the influence of high-order aberrations,beam energy/intensity modulation,and beam orbit correction are described.In addition to the technical implementation of the main beamline compo-nents and subsystems,including the energy degrader,fast kicker,beamline magnets,beam diagnostic system,and beamline control system are introduced.