Optimal sampling period of the digital control system for the nuclear power plant steam generator water level control

International Nuclear Information System (INIS)

Hur, Woo Sung; Seong, Poong Hyun

1995-01-01

A great effort has been made to improve the nuclear plant control system by use of digital technologies and a long term schedule for the control system upgrade has been prepared with an aim to implementation in the next generation nuclear plants. In case of digital control system, it is important to decide the sampling period for analysis and design of the system, because the performance and the stability of a digital control system depend on the value of the sampling period of the digital control system. There is, however, currently no systematic method used universally for determining the sampling period of the digital control system. Generally, a traditional way to select the sampling frequency is to use 20 to 30 times the bandwidth of the analog control system which has the same system configuration and parameters as the digital one. In this paper, a new method to select the sampling period is suggested which takes into account of the performance as well as the stability of the digital control system. By use of the Irving's model steam generator, the optimal sampling period of an assumptive digital control system for steam generator level control is estimated and is actually verified in the digital control simulation system for Kori-2 nuclear power plant steam generator level control. Consequently, we conclude the optimal sampling period of the digital control system for Kori-2 nuclear power plant steam generator level control is 1 second for all power ranges. 7 figs., 3 tabs., 8 refs. (Author)

Fault-tolerant design of adaptive digital control systems for power plant components

International Nuclear Information System (INIS)

Parlos, A.G.; Menon, S.K.

1992-01-01

An adaptive controller has been designed for the water level of a Westinghouse type U-tube steam generator, and its operation has been demonstrated in the entire power range via computer simulations. The proposed design exhibits improved performance, at low operating powers, a,s compared to existing controller types. The continuous-time controller design is performed systematically via the Linear Quadratic Gaussian/Loop Transfer Recovery method, followed by gain adaptation allowing controller operation in the entire power range. Digital implementation of the controller is accomplished by a digital redesign which results in matching the digital and continuous-time system and controller states. It is only at this stage of the control system design process that issues such as microprocessor induced quantization effects are taken into account. The use of computer-aided-design software greatly expedites the design cycle, allowing the designer to maximize the controller stability robustness to uncertainties via numerous iterations. This inherent controller robustness can be exploited to tolerate incipient plant faults, such as deteriorating U-tube heat transfer properties, without significant loss of controller performance

Advanced digital computers, controls, and automation technologies for power plants: Proceedings

International Nuclear Information System (INIS)

Bhatt, S.C.

1992-08-01

This document is a compilation of the papers that were presented at an EPRI workshop on Advances in Computers, Controls, and Automation Technologies for Power Plants. The workshop, sponsored by EPRI's Nuclear Power Division, took place February 1992. It was attended by 157 representatives from electric utilities, equipment manufacturers, engineering consulting organizations, universities, national laboratories, government agencies and international utilities. More than 40% of the attendees were from utilities representing the majority group. There were 30% attendees from equipment manufacturers and the engineering consulting organizations. The participants from government agencies, universities, and national laboratories were about 10% each. The workshop included a keynote address, 35 technical papers, and vendor's equipment demonstrations. The technical papers described the state-of-the-art in the areas of recent utility digital upgrades such as digital feedwater controllers, steam generator level controllers, integrated plant computer systems, computer aided diagnostics, automated testing and surveillance and other applications. A group of technical papers presented the ongoing B ampersand W PWR integrated plant control system prototype developments with the triple redundant advanced digital control system. Several international papers from France, Japan and U.K. presented their programs on advance power plant design and applications. Significant advances in the control and automation technologies such as adaptive controls, self-tuning methods, neural networks and expert systems were presented by developers, universities, and national laboratories. Individual papers are indexed separately

Retrofit of new digital control systems in existing power stations

International Nuclear Information System (INIS)

Smith, J.E.; Baird, C.F.

1986-01-01

With the notable exception of the Canadian CANDU nuclear power stations, little use has been made of digital control in North American nuclear stations. Recently, however, there has been renewed interest in such systems within the nuclear industry in response to demands for better ergonomics in control room design and the obsolescence of control equipment whose fundamental design has changed little in 20 yr. Early in 1985, Atomic Energy of Canada Limited was asked by New Brunswick Power to advise on the redesign of the control systems for two fossil-fired generating stations, Coleson Cove and Courtenay Bay Unit 4. Coleson Cove is to be converted from oil to coal firing with consequent extensive control system changes and Courtenay Bay Unit 4 required a low-cost solution to the problem of relocating its control room from the existing isolated location to the combined control center used by units 1, 2, and 3. In both cases, the recommended solution involves the retrofit of state-of-the-art digital control systems. Although the units involved are nonnuclear the experience is applicable

Controlled power delivery for super-resolution imaging of biological samples using digital micromirror device

Science.gov (United States)

Valiya Peedikakkal, Liyana; Cadby, Ashley

2017-02-01

Localization based super resolution images of a biological sample is generally achieved by using high power laser illumination with long exposure time which unfortunately increases photo-toxicity of a sample, making super resolution microscopy, in general, incompatible with live cell imaging. Furthermore, the limitation of photobleaching reduces the ability to acquire time lapse images of live biological cells using fluorescence microscopy. Digital Light Processing (DLP) technology can deliver light at grey scale levels by flickering digital micromirrors at around 290 Hz enabling highly controlled power delivery to samples. In this work, Digital Micromirror Device (DMD) is implemented in an inverse Schiefspiegler telescope setup to control the power and pattern of illumination for super resolution microscopy. We can achieve spatial and temporal patterning of illumination by controlling the DMD pixel by pixel. The DMD allows us to control the power and spatial extent of the laser illumination. We have used this to show that we can reduce the power delivered to the sample to allow for longer time imaging in one area while achieving sub-diffraction STORM imaging in another using higher power densities.

Experimental direct digital control of the power plant A1 reactor based on a modern control theory approach

International Nuclear Information System (INIS)

Karpeta, C.

1979-01-01

The objective of the project was to accumulate technical experience with application of modern control theory in nuclear power by carrying out a case study of an experimental direct digital control at the A1 reactor about its nominal steady state. The research has proved that slightly modified method of solution of the linear stochastic regulator problem can be successfully applied in design of digital control system of nuclear power reactors

Migration of Older to New Digital Control Systems in Nuclear Power Plant Main Control Rooms

Energy Technology Data Exchange (ETDEWEB)

Kovesdi, Casey Robert [Idaho National Lab. (INL), Idaho Falls, ID (United States); Joe, Jeffrey Clark [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-04-01

The United States (U.S.) Department of Energy (DOE) Office of Nuclear Energy (NE) has the primary mission to advance nuclear power by resolving socio-technical issues through research and development (R&D). One DOE-NE activity supporting this mission is the Light Water Reactor Sustainability (LWRS) program. LWRS has the overall objective to sustain the operation of existing commercial nuclear power plants (NPPs) through conducting R&D across multiple “pathways,” or R&D focus areas. The Advanced Instrumentation, Information, and Control (II&C) Systems Technologies pathway conducts targeted R&D to address aging and reliability concerns with the legacy instrumentation and control (I&C) and related information systems in operating U.S. NPPs. This work involves (1) ensuring that legacy analog II&C systems are not life-limiting issues for the LWR fleet, and (2) implementing digital II&C technology in a manner that enables broad innovation and business improvement in the NPP operating model. Under the LWRS Advanced II&C pathway, Human Factors experts at Idaho National Laboratory (INL) have been conducting R&D in support of NPP main control room (MCR) modernization activities. Work in prior years has focused on migrating analog I&C systems to new digital I&C systems (). In fiscal year 2016 (FY16), one new focus area for this research is migrating older digital I&C systems to new and advanced digital I&C systems. This report summarizes a plan for conducting a digital-to-digital migration of a legacy digital I&C system to a new digital I&C system in support of control room modernization activities.

Migration of Older to New Digital Control Systems in Nuclear Power Plant Main Control Rooms

International Nuclear Information System (INIS)

Kovesdi, Casey Robert; Joe, Jeffrey Clark

2016-01-01

The United States (U.S.) Department of Energy (DOE) Office of Nuclear Energy (NE) has the primary mission to advance nuclear power by resolving socio-technical issues through research and development (R&D). One DOE-NE activity supporting this mission is the Light Water Reactor Sustainability (LWRS) program. LWRS has the overall objective to sustain the operation of existing commercial nuclear power plants (NPPs) through conducting R&D across multiple ''pathways,'' or R&D focus areas. The Advanced Instrumentation, Information, and Control (II&C) Systems Technologies pathway conducts targeted R&D to address aging and reliability concerns with the legacy instrumentation and control (I&C) and related information systems in operating U.S. NPPs. This work involves (1) ensuring that legacy analog II&C systems are not life-limiting issues for the LWR fleet, and (2) implementing digital II&C technology in a manner that enables broad innovation and business improvement in the NPP operating model. Under the LWRS Advanced II&C pathway, Human Factors experts at Idaho National Laboratory (INL) have been conducting R&D in support of NPP main control room (MCR) modernization activities. Work in prior years has focused on migrating analog I&C systems to new digital I&C systems (). In fiscal year 2016 (FY16), one new focus area for this research is migrating older digital I&C systems to new and advanced digital I&C systems. This report summarizes a plan for conducting a digital-to-digital migration of a legacy digital I&C system to a new digital I&C system in support of control room modernization activities.

Digital remote control system for power supplies of particle channel magnetooptical elements

International Nuclear Information System (INIS)

Vetrov, P.B.; Ermolina, G.P.; Kuznetsov, V.S.; Mojbenko, A.N.

1986-01-01

Current control of magnetooptical elements of accelerator particle channels is based on control of reference voltage of current stabilizers. Advent of industrial multidigit (12 bits) integral analog-to-digital converters permitted to develop simple digital sources of reference voltage. A digital control system of 30 spatially remoted power supplies of magnetooptical elements of particle channels on the basis of the ''Elektronika-60'' microcomputer is described. The microcomputer is connected by the standard communication line (20 mA) with the SM-4 computer. The ''Summa'' crate is connected with the microcomputer through the branch driver. Digit data are transmitted by the multibranch trunk of sequential communication (Manchester-2 code) at the rate of 0.5 Mband. Feedback was realized by connection of analog signals through the distributed commutator to the measuring line with a digital voltmeter

The test and control system for high performance digital power supplies of SSRF

International Nuclear Information System (INIS)

Tang Junlong; Li Deming; Shen Tianjian

2009-01-01

A test and control system was designed to evaluate performance of the digital power supplies for SSRF. The software of serial communication (RS-232) and Ethernet interface was developed with Lab VIEW. The system can perform functions of instrument and power supply control, data acquisition and display, and store data for 24 h. LAN users can access the system and acquire data conveniently. The data are stored in Excel for analysis and establishment of database of digital PS in the future. (authors)

Trends in the use of digital technology for control and regulation of power supplies

International Nuclear Information System (INIS)

Carwardine, J.; Lenkszus, F.

1999-01-01

Since the availability of computers, accelerator power supplies have relied on digital technology in some way, from such simple tasks as turning the supplies on and off to the supplying of computer-controlled references. However, advances in digital technology, both in performance and cost, allow considerably more than simple control and monitoring. This, coupled with increasing demand for higher performance and monitoring capabilities, has made it appealing to integrate such technology into power supply designs. This paper will review current trends in the use of such advanced technology as embedded DSP controllers, and the application of real-time algorithms to the regulation and control of power supplies for accelerators and other large-scale physics applications

Experimental Learning of Digital Power Controller for Photovoltaic Module Using Proteus VSM

Directory of Open Access Journals (Sweden)

Abhijit V. Padgavhankar

2014-01-01

Full Text Available The electric power supplied by photovoltaic module depends on light intensity and temperature. It is necessary to control the operating point to draw the maximum power of photovoltaic module. This paper presents the design and implementation of digital power converters using Proteus software. Its aim is to enhance student’s learning for virtual system modeling and to simulate in software for PIC microcontroller along with the hardware design. The buck and boost converters are designed to interface with the renewable energy source that is PV module. PIC microcontroller is used as a digital controller, which senses the PV electric signal for maximum power using sensors and output voltage of the dc-dc converter and according to that switching pulse is generated for the switching of MOSFET. The implementation of proposed system is based on learning platform of Proteus virtual system modeling (VSM and the experimental results are presented.

Recent digital control and protection retrofits in power plants

International Nuclear Information System (INIS)

Fournier, R.D.; Hammer, M.; Smith, J.E.

1987-01-01

Digital computers are now being retrofitted to all types of power plants, replacing analog equipment and solving problems such as equipment obsolescence and low reliability. Three diverse examples of retrofits are presented in this paper, representing trends in man/machine interface design at an oil-fired plant, protection system in pressurized heavy-water reactors, and control systems in light water reactors (LWRs). The examples have been chosen to illustrate diverse reasons for the retrofits and the benefits derived. The cases presented report retrofits at Northern States Power's Monticello boiling water reactor, New Brunswick Electric Power Commission's (NBEPC's) Point Lepreau Nuclear Generating Station, and finally NBEPC's oil-fired plant at Courtney Bay

New digital control and power protection system of VR 1 training reactor

International Nuclear Information System (INIS)

Kropik, M.; Matejka, K.; Juoeickova, M.

2005-01-01

The contribution describes the new VR-1 training reactor control and power protection system at the Czech Technical University in Prague. The control system provides safety and control functions, calculates average values of the important variables and sends data and system status to the human-machine interface. The upgraded control system is based on a high quality industrial PC. The operating system of the PC is the Microsoft Windows XP with the real time support RTX of the VentureCom Company. The software was developed according to requirements in MS Visual C. The independent power protection system is a component of the reactor safety (protection) system with high quality and reliability requirements. The digital system is redundant; each channel evaluates the reactor power and the velocity of power changes and provides safety functions. The digital part of the channel is multiprocessor-based. The software was developed with respect to nuclear standards. The software design was coded in the C language regarding the NRC restrictions. Configuration management, verification and validation accompanied the software development. Both systems were thoroughly tested. Firstly, the non active tests were carried out. During these tests, the active core of the reactor was subcritical; the input signals were generated from HPIB and VXI controlled instruments to simulate different operational and safety events. The software for instruments control and tests evaluation utilized Agilent VEE development system. After the successful non active checking, the active tests followed. (author)

Investigation on the use digital controls instead of PID analog controls in the level control of steam generators of nuclear power PWR

International Nuclear Information System (INIS)

Alvarenga, Marco Antonio Bayout

2012-01-01

The aim of this study is to identify current alternatives for the implementation of digital controllers in the level control of steam generators of nuclear power PWR (Pressurized Water Reaetor). It is intended to identify the types of digital controls that are available from the theoretical and conceptual viewpoints for this purpose. We investigate the advantages and disadvantages of each controller model. From this assessment are pointed the most suitable models in hierarchical scale. This evaluation also serves to suggest possible types of control installation as a whole, where the level control of the steam generators becomes just one of many controls that are part of the plant. In this case, the use of digital controls allows the non-linear and multivariable treatment which is characteristic of complex systems, such as the nuclear power generation. The treatment of nonlinearities and multivariable aspects allows a more detailed study of the stability of these plants when they are subject to transients or several accidents, such as the case of losing external power of transients. In the specific case of steam generators, the instabilities result from the emergence of the shrink and swell phenomenas, depending on the load variations of thermonuclear plant. The application of several types and digital controllers, considering these inherent characteristics of the level control of steam generators, allows to infer which types of controllers are more appropriate to treat instabilities of this type and to make conjectures in its use for the cases of more complex instabilities, considering the integration of all nucleus-plant controls.

Design of coordinated controller in nuclear power plant based on digital instrument and control technology

International Nuclear Information System (INIS)

Cheng Shouyu; Peng Minjun; Liu Xinkai; Zhao Qiang; Deng Xiangxin

2014-01-01

Nuclear power plant (NPP) is a multi-input and multi-output, no-linear and time-varying complex system. The conventional PID controller is usually used in NPP control system which is based on analog instrument. The system parameters are easy to overshoot and the response time is longer in the control mode of the conventional PID. In order to improve this condition, a new coordinated control strategy which is based on expert system and the original controllers in the digital instrument and control technology was presented. In order to verify and validate it, the proposed coordinated control technology was tested by the full-scope real-time simulation system. The results prove that using digital instrument and control technology to achieve coordinated controller is feasible, the coordinated controller can effectively improve the dynamic operating characteristics of the system, and the coordinated controller is superior to the conventional PID controller in control performance. (authors)

Efficiency and hardware comparison of analog control-based and digital control-based 70 W two-stage power factor corrector and DC-DC converters

DEFF Research Database (Denmark)

Török, Lajos; Munk-Nielsen, Stig

2011-01-01

A comparison of an analog and a digital controller driven 70 W two-stage power factor corrector converter is presented. Both controllers are operated in average current-mode-control for the PFC and peak current control for the DC-DC converter. Digital controller design and converter modeling...... is described. Results show that digital control can compete with the analog one in efficiency, PFC and THD....

Fault tolerant digital control systems for boiling water reactors

International Nuclear Information System (INIS)

Chakraborty, S.; Cash, N.R.

1986-01-01

In a Boiling Water Reactor nuclear power plant, the power generation control function is divided into several systems, each system controlling only a part of the total plant. Presently, each system is controlled by conventional analog or digital logic circuits with little interaction for coordinated control. The advent of microprocessors has allowed the development of distributed fault-tolerant digital controls. The objective is to replace these conventional controls with fault-tolerant digital controls connected together with digital communication links to form a fully integrated nuclear power plant control system

On the simulation of transients and accidents in PWRs with digital instrumentation and control using an LQR digital controller

International Nuclear Information System (INIS)

Alvarenga, M.A.B.; Melo, P.F. Frutuoso e; Medeiros, J.A.C.C.; Oliva, J.J. Rivero

2015-01-01

New nuclear power plant designs are including integrated I and C digital systems for protection, control, alarming and monitoring. Existing operating nuclear power plants, as is the case of Angra 1 nuclear power plant, have to consider the replacement of their I and C analog systems by digital systems for retrofitting their facilities. However, before replacing the analog control loops by digital ones it is necessary to design and evaluate their performance, which requires modeling of the plant and its control system with extensive simulations under several normal and abnormal operation conditions. This paper discusses the use of a linear quadratic regulator (LQR) digital controller for evaluating the plant stability behavior before the actuation of the reactor protection system. The objective is to evaluate the effect of digital controllers on plant behavior for several transients and accident conditions. For this purpose, a numerical model was developed and implemented as a MatlabTM tool. This paper discusses an adequate framework in order to simulate a set of transients and accidents that constitute the design basis in the final safety analysis report of PWR power plants to evaluate the performance of digital controllers such as LQR regulators.(author)

Digitized operator evaluation system for main control room of nuclear power plant

International Nuclear Information System (INIS)

Chen Yu; Yan Shengyuan; Chen Wenlong

2014-01-01

In order to evaluate the human-machine system matching relation of main control room in nuclear power plant accurately and efficiently, the expression and parameters of operator human body model were analyzed, and the evaluation required function of digital operator was determined. Based on the secondary development technology, the digital operator evaluation body model was developed. It could choose generation, gender, operation posture, single/eyes horizon, and left/right hand up to the domain according to the needs of specific evaluation, it was used to evaluate whether display information can be visible and equipment can be touch, and it also has key evaluation functions such as workspace and character visibility at the same time. The examples show that this method can complete the evaluation work of human-machine matching relation for main control room of nuclear power plant accurately, efficiently and quickly, and achieve the most optimal human-machine coordination relationship. (authors)

Digital electro-hydraulic control system for nuclear turbine

International Nuclear Information System (INIS)

Yokota, Yutaka; Tone, Youichi; Ozono, Jiro

1985-01-01

The unit capacity of steam turbines for nuclear power generation is very large, accordingly their unexpected stop disturbs power system, and the lowering of their capacity ratio exerts large influence on power generation cost. Therefore, very high reliability is required for turbine EHC controllers which directly control the turbines for nuclear power generation. In order to meet such requirement, Toshiba Corp. has developed high reliability type analog tripled turbine EHC controllers, and delivered them to No. 3 plant in the Fukushima No. 2 Nuclear Power Station and No. 1 plant in the Kashiwazaki Kariwa Nuclear Power Station, Tokyo Electric Power Co., Inc. At present, the trial operation is under way. The development of digital EHC controllers was begun in 1976, and through the digital EHC for a test turbine and that for a small turbine, the digital EHC controllers for the turbines for nuclear power generation were developed. In this paper, the function, constitution, features and maintenance of the digital tripled EHC controllers for the turbines for nuclear power generation, the application of new technology to them, and the confirmation of the control function by simulation are reported. (Kako, I.)

Implementation of a digital feedwater control system at Dresden Nuclear Power Plant, Units 2 and 3: Final report

International Nuclear Information System (INIS)

Zapotocky, A.; Popovic, J.R.; Fournier, R.D.

1988-12-01

This report describes the Digital Feedwater Control System Implementation at the Dresden 2 or 3 Units of the BWR Nuclear Power Plant owned by the Commonwealth Edison Company. The digital system has been operational in Unit 3 since August 1986, and in Unit 2 since April 1987. The Bailey Control's Network 90 based digital control system replaced the obsolete GE/MAC 5000 analog control system in the reactor feedwater control loop as a ''like-for-like'' replacement. Operational experience from the Digital Feedwater Control installations has been good and the system demonstrated better performance than the old analog systems. 14 refs., 15 figs., 17 tabs

Implementing digital instrumentation and control systems in the modernization of nuclear power plants

International Nuclear Information System (INIS)

2009-01-01

The IAEA encourages greater use of good engineering and management practices by Member States. In particular, it supports activities such as nuclear power plant (NPP) performance improvement, plant life management, training, power uprating, operational license renewal and the modernization of instrumentation and control (I and C) systems of NPPs in Member States. The subject of implementing digital I and C systems in nuclear power plants was suggested by the Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI) in 2003. It was then approved by the IAEA and included in the programmes for 2006-2008. As the current worldwide fleet of nuclear power plants continues ageing, the need for improvements to maintain or enhance plant safety and reliability is increasing. Upgrading NPP I and C systems is one of the possible approaches to achieving this improvement, and in many cases upgrades are a necessary activity for obsolescence management. I and C upgrades at operating plants require the use of digital I and C equipment. While modernizing I and C systems is a significant undertaking, it is an effective means to enhance plant safety and system functionality, manage obsolescence, and mitigate the increasing failure liability of ageing analog systems. Many of the planning and implementation tasks of a digital I and C upgrade project described here are also relevant to new plant design and construction since all equipment in new plants will be digital. This publication explains a process for planning and conducting an I and C modernization project. Numerous issues and areas requiring special consideration are identified, and recommendations on how to integrate the licensing authority into the process are made. To complement this report, a second publication is planned which will illustrate many of the aspects described here through experience based descriptions of I and C projects and lessons learned from those activities. It is upon these

Digitally Controlled Envelope Tracking Power Supply for an RF Power Amplifier

DEFF Research Database (Denmark)

Jakobsen, Lars Tønnes; Andersen, Michael Andreas E.

2007-01-01

due to clock frequency quantization. An envelope tracking power supply for an RF Power Amplifier (RFPA) can help improve system efficiency by reducing the power consumption of the RFPA. To show the advantage of the DiSOM over traditional counter based Digital PWM modulators two designs were compared...... in both simulation and by experiment. The results shows that the DiSOM could give an increase in open loop bandwidth by more than a factor of two and an reduce the closed loop output impedance of the power supply by a factor of 5 at the output filter resonance frequency....

REVIEW OF NRC APPROVED DIGITAL CONTROL SYSTEMS ANALYSIS

International Nuclear Information System (INIS)

Markman, D.W.

1999-01-01

Preliminary design concepts for the proposed Subsurface Repository at Yucca Mountain indicate extensive reliance on modern, computer-based, digital control technologies. The purpose of this analysis is to investigate the degree to which the U. S. Nuclear Regulatory Commission (NRC) has accepted and approved the use of digital control technology for safety-related applications within the nuclear power industry. This analysis reviews cases of existing digitally-based control systems that have been approved by the NRC. These cases can serve as precedence for using similar types of digitally-based control technologies within the Subsurface Repository. While it is anticipated that the Yucca Mountain Project (YMP) will not contain control systems as complex as those required for a nuclear power plant, the review of these existing NRC approved applications will provide the YMP with valuable insight into the NRCs review process and design expectations for safety-related digital control systems. According to the YMP Compliance Program Guidance, portions of various NUREGS, Regulatory Guidelines, and nuclear IEEE standards the nuclear power plant safety related concept would be applied to some of the designs on a case-by-case basis. This analysis will consider key design methods, capabilities, successes, and important limitations or problems of selected control systems that have been approved for use in the Nuclear Power industry. An additional purpose of this analysis is to provide background information in support of further development of design criteria for the YMP. The scope and primary objectives of this analysis are to: (1) Identify and research the extent and precedence of digital control and remotely operated systems approved by the NRC for the nuclear power industry. Help provide a basis for using and relying on digital technologies for nuclear related safety critical applications. (2) Identify the basic control architecture and methods of key digital control

Application of LabVIEW in SSRF digital power supply development

International Nuclear Information System (INIS)

Tang Junlong; Chen Huanguang; Ke Xinhua; Chinese Academy of Science, Beijing; Xu Ruinian; Li Deming

2007-01-01

During development of the Shanghai Synchrotron Radiation Facility (SSRF) digital power supply, a digital pulse-width modulator (PWM) directly controls the power circuit insulated gate bipolar transistor (IGBT). A program in LabVIEW language has been developed to perform computer control and monitor for the digital PS via serial communication (RS232). The program provides a friendly user interface to the digital PS that makes it easy to observe its behavior and modify its parameters. Another program, also in LabVIEW language, has been developed to test long term stability of the digital power supply and store the experimental data via extremely precise Keithley instrument and computer. The experimental data are stored in an Excel file which can be processed and analyzed in the future. (authors)

Digital Control of a power conditioner for fuel cell/super-capacitor hybrid system

DEFF Research Database (Denmark)

Caballero, Juan C Trujillo; Gomis-Bellmunt, Oriol; Montesinos-Miracle, Daniel

2014-01-01

This article proposes a digital control scheme to operate a proton exchange membrane fuel cell module of 1.2 kW and a super-capacitor through a DC/DC hybrid converter. A fuel cell has been proposed as a primary source of energy, and a super-capacitor has been proposed as an auxiliary source...... of energy. Experimental validation of the system implemented in the laboratory is provided. Several tests have been performed to verify that the system achieves excellent output voltage (V0) regulation and super-capacitor voltage (V SC) control under disturbances from fuel cell power (PFC) and output power...

Regulatory perspective on digital instrumentation and control systems for future advanced nuclear power plants

International Nuclear Information System (INIS)

Chiramal, M.

1993-01-01

This paper deals with the question of using digital technology in instrumentation and control systems for modern nuclear power reactors. The general opinion in the industry and among NRC staff is that such technology provides the opportunity for enhanced safety and reliable reactor operations. The major concern is the safe application of this technology so as to avoid common mode or common cause failures in systems. There are great differences between digital and analog system components. SECY-91-292 identifies some general regulatory concerns with regard to digital systems. There is clearly a lack of adequate regulatory direction on the application of digital equipment at this time, but the issue is being addressed by the industry, outside experts, and NRC staff. NRC staff presents a position on the issue of defense-in-depth and diversity with regard to insuring plant safety. Independent manual controls and readouts must be available to allow safe shutdown and monitoring of the plant in the event of safety system failures

Key Regulatory Issues for Digital Instrumentation and Control Systems at Nuclear Power Plants

International Nuclear Information System (INIS)

Korsah, Kofi; Wood, Richard Thomas

2008-01-01

To help reduce the uncertainty associated with application of digital instrumentation and controls (I and C) technology in nuclear power plants, the Nuclear Regulatory Commission (NRC) has issued six Interim Staff Guidance (ISG) documents that address the current regulatory positions on what are considered the significant digital I and C issues. These six documents address the following topics: Cyber Security, Diversity and Defense-in-Depth, Risk Informed Digital I and C Regulation, Communication issues, Human Factors and the Digital I and C Licensing Process (currently issued as Draft). After allowing for further refinement based on additional technical insight gathered by NRC staff through near-term research and detailed review of relevant experience, it is expected that updated positions ultimately will be incorporated into regulatory guides and staff review procedures. This paper presents an overview of the guidance provided by the NRC-issued ISGs on key technology considerations (i.e., the first five documents above) for safety-related digital I and C systems.

Method for fault diagnosis of digital control systems in nuclear power plant

International Nuclear Information System (INIS)

Suzuki, Satoshi; Nagaoka, Yukio; Ohga, Yukiharu; Ito, Tetsuo

1990-01-01

This paper presents a method for localizing faulty components of control systems by replaceable parts such as print boards and cables, in a large scale plant like a nuclear power plant. Most of today's control systems form a distributed configuration including many digital controllers interconnected by data communication networks. Usually, to localize the faulty components in nuclear plant control systems, suspected faulty components are narrowed down by executing manual tests to examine whether the objects are normal or abnormal based on design documents and personnel know-how, besides the uses of self-diagnosis functions built into the control systems. In the present method, procedures of various tests including the know-how and checking of self-diagnosis functions are provided as knowledge of tests. The tests to be executed is determined by considering failure probabilities of objects, and easiness and effectiveness of testing. Then, the suspects are narrowed down sequentially based on the test result. In checking feasibility of this diagnosis method for a simulated control system, intended faults are satisfactorily localized. This method is confirmed to be practicable for diagnosis of large scale digital control systems. (author)

Unified Digital Periodic Signal Filters for Power Converter Systems

DEFF Research Database (Denmark)

Yang, Yongheng; Xin, Zhen; Zhou, Keliang

2017-01-01

Periodic signal controllers like repetitive and resonant controllers have demonstrated much potential in the control of power electronic converters, where periodic signals (e.g., ac voltages and currents) can be precisely regulated to follow references. Beyond the control of periodic signals, ac...... signal processing (e.g., in synchronization and pre-filtering) is also very important for power converter systems. Hence, this paper serves to unify digital periodic signal filters so as to maximize their roles in power converter systems (e.g., enhance the control of ac signals). The unified digital...... periodic signal filters behave like a comb filter, but it can also be configured to selectively filter out the harmonics of interest (e.g., the odd-order harmonics in single-phase power converter systems). Moreover, a virtual variable-sampling-frequency unit delay that enables frequency adaptive periodic...

Simulation of Digital Control Computer of Nuclear Power Plant Based on Virtual Machine Technology

International Nuclear Information System (INIS)

Hou, Xue Yan; Li, Shu; Li, Qing

2011-01-01

Based on analyzing DCC (Digital Control Computer) instruction sets, memory map, display controllers and I/O system, virtual machine of DCC (abbr. VM DCC) has been developed. The executive and control programs, same as running on NPP (Nuclear Power Plant) unit's DCC, can run on the VM DCC smoothly and get same control results. Dual VM DCC system has been successfully applied in NPP FSS(Full Scope Simulator) training. It not only improves FSS's fidelity but also makes maintaining easier

1985 seminar on power plant digital control and fault-tolerant microcomputers: proceedings

International Nuclear Information System (INIS)

Divakaruni, S.M.

1986-09-01

An EPRI Seminar to address Power Plant Digital Controls and Fault-Tolerant Microcomputers Technology was hosted by Arizona Public Service Company in Phoenix, Arizona on April 9-12, 1986. The attendees represented a broad spectrum of US and foreign utilities, architect and consulting firms, and NSSS and computer system hardware vendors. These proceedings contain the text of the formal presentations as well as the papers and slides used during the short courses offered

A review of the MIT experiments on the closed-loop digital control of reactor power

International Nuclear Information System (INIS)

Bernard, J.A.

1989-01-01

In this paper a review is provided of certain major experiments conducted from 1985 to 1988 as part of the MIT program on the development and demonstration of advanced technologies for the closed-loop digital control of nuclear reactors. Included are demonstrations of the supervisory control of neutronic power using an alternate formulation of the dynamic period equation, the use of the MIT-SNL Period-Generated Minimum Time Control Laws for the time-optimal control of neutronic power, and the evaluation of predictive displays as an operator aid. The significance of each of these advances is discussed in terms of the overall development of a multi-tiered controller that includes supervisory algorithms, predictive control laws, and automated reasoning

LEITTEC '96. Digitization of instrumentation and control in nuclear power plants

International Nuclear Information System (INIS)

Bauer, K.G.

1997-01-01

The nuclear power plants in operation in Germany have been commissioned in the years from 1968 until 1988. Their control and safety systems likewise correspond to the electronic technology available then, as e.g. discrete semi-conductor technology. The high reliability of those systems contributed a major share to the excellent operating results achieved by German nuclear power plants. However, aging of existing systems as well as spare part availability and integration of older and more recent hardware generations now are posing specific problems. Intensive work has been devoted to the retrofitting of existing systems and integration of computer-assisted control systems as well as conversion to programmable systems in order to achieve a basis permitting economically justifiable operation, acceptable also from the angle of hardware and software inspection requirements, so that the German Atomforum thought that these activities and the underlying problems would make a suitable topic for a conference. There were about 150 experts attending the one-day meeting for intensive discussion and exchange of information. The proceedings volume contains 11 of the conference papers and provides an overview of the current status and expected developments in the field of digitization of instrumentation and control in nuclear power plants.(orig./CB) [de

Digitally Controlled Converter with Dynamic Change of Control Law and Power Throughput

DEFF Research Database (Denmark)

Nesgaard, Carsten; Andersen, Michael Andreas E.; Nielsen, Nils

2003-01-01

the substitution of analog controllers with their digital counterparts are considered. The outline of the paper is divided into two segments – the first being an experimental analysis of the timing behavior by means of code optimization – the second being an examination of the dynamics of incorporating two control......With the continuous development of faster and cheaper microprocessors the field of applications for digital control is constantly expanding. Based on this trend the paper at hand describes the analysis and implementation of multiple control laws within the same controller. Also, implemented within...

Simulation of Digital Control Computer of Nuclear Power Plant Based on Virtual Machine Technology

Energy Technology Data Exchange (ETDEWEB)

Hou, Xue Yan; Li, Shu; Li, Qing [China Nuclear Power Operation Technology Co., Wuhan (China)

2011-08-15

Based on analyzing DCC (Digital Control Computer) instruction sets, memory map, display controllers and I/O system, virtual machine of DCC (abbr. VM DCC) has been developed. The executive and control programs, same as running on NPP (Nuclear Power Plant) unit's DCC, can run on the VM DCC smoothly and get same control results. Dual VM DCC system has been successfully applied in NPP FSS(Full Scope Simulator) training. It not only improves FSS's fidelity but also makes maintaining easier.

Reliability analysis of operator's monitoring behavior in digital main control room of nuclear power plants and its application

International Nuclear Information System (INIS)

Zhang Li; Hu Hong; Li Pengcheng; Jiang Jianjun; Yi Cannan; Chen Qingqing

2015-01-01

In order to build a quantitative model to analyze operators' monitoring behavior reliability of digital main control room of nuclear power plants, based on the analysis of the design characteristics of digital main control room of a nuclear power plant and operator's monitoring behavior, and combining with operators' monitoring behavior process, monitoring behavior reliability was divided into three parts including information transfer reliability among screens, inside-screen information sampling reliability and information detection reliability. Quantitative calculation model of information transfer reliability among screens was established based on Senders's monitoring theory; the inside screen information sampling reliability model was established based on the allocation theory of attention resources; and considering the performance shaping factor causality, a fuzzy Bayesian method was presented to quantify information detection reliability and an example of application was given. The results show that the established model of monitoring behavior reliability gives an objective description for monitoring process, which can quantify the monitoring reliability and overcome the shortcomings of traditional methods. Therefore, it provides theoretical support for operator's monitoring behavior reliability analysis in digital main control room of nuclear power plants and improves the precision of human reliability analysis. (authors)

Digital control programmer for temperature control

International Nuclear Information System (INIS)

Rajore, S.B.; Kumar, S.V.

1993-01-01

This report describes a PC based digital control programmer for controlling and programming temperature of a high vacuum resistance heating furnace and the software developed to control power using PID algorithm. It also describes the amplifier specially developed to suit the input requirement of the non-standard W5 thermocouple and the software and hardware protections introduced in the system. (author). 5 refs., 8 figs., 1 appendix

Analogue to digital upgrade project-boiler feedwater control system for Bruce Power nuclear units 1 & 2

International Nuclear Information System (INIS)

Long, R.

2012-01-01

Bruce Power Nuclear Generating Station A, “Bruce A” is in the final stages of its Restart Project. This capital project will see a large scale rehabilitation of Units 1 and 2 resulting in addition of 1500MW of safe, reliable, clean electricity to the Ontario grid. Restart Project Scope 375, Boiler Feedwater Controls Upgrade was sanctioned to replace obsolete analog devices with a modern digital control system. This project replaced the existing Foxboro H Line analog controls which comprised of 81 individual control modules and support instrumentation. The replacement system was a Triconex Triple Modular Redundant PLC which interfaces with two redundant touch screen monitors. The upgraded digital system incorporates the following controls: 1. Boiler Level Control Loops 2. Dearator Level Control Loops 3. Dearator Pressure Control Loops 4. Boiler Feedwater Recirculation Flow Control Loops A number of technical challenges were addressed when installing a new digital system within the existing plant configuration. Interfaces to new, old and refurbished field devices must be understood as well as implications of connecting to the plant’s Digital Control Computers (DCC’s) and newly installed Steam Generators. The overall project involved many stakeholders to address various requirements from conceptual / design stage through procurement, construction, commissioning and return to service. In addition, the project highlighted the unique requirements found in Nuclear Industry with respect to Human Factors and Software Quality Assurance. (author)

Programmable Digital Controller

Science.gov (United States)

Wassick, Gregory J.

2012-01-01

An existing three-channel analog servo loop controller has been redesigned for piezoelectric-transducer-based (PZT-based) etalon control applications to a digital servo loop controller. This change offers several improvements over the previous analog controller, including software control over proportional-integral-derivative (PID) parameters, inclusion of other data of interest such as temperature and pressure in the control laws, improved ability to compensate for PZT hysteresis and mechanical mount fluctuations, ability to provide pre-programmed scanning and stepping routines, improved user interface, expanded data acquisition, and reduced size, weight, and power.

Digital control system of advanced reactor

International Nuclear Information System (INIS)

Peng Huaqing; Zhang Rui; Liu Lixin

2001-01-01

This article produced the Digital Control System For Advanced Reactor made by NPIC. This system uses Siemens SIMATIC PCS 7 process control system and includes five control system: reactor power control system, pressurizer level control system, pressurizer pressure control system, steam generator water level control system and dump control system. This system uses three automatic station to realize the function of five control system. Because the safety requisition of reactor is very strict, the system is redundant. The system configuration uses CFC and SCL. the human-machine interface is configured by Wincc. Finally the system passed the test of simulation by using RETRAN 02 to simulate the control object. The research solved the key technology of digital control system of reactor and will be very helpful for the nationalization of digital reactor control system

Digital Controller For Acoustic Levitation

Science.gov (United States)

Tarver, D. Kent

1989-01-01

Acoustic driver digitally controls sound fields along three axes. Allows computerized acoustic levitation and manipulation of small objects for such purposes as containerless processing and nuclear-fusion power experiments. Also used for controlling motion of vibration-testing tables in three dimensions.

Active power filter for harmonic compensation using a digital dual-mode-structure repetitive control approach

DEFF Research Database (Denmark)

Zou, Zhixiang; Wang, Zheng; Cheng, Ming

2012-01-01

This paper presents an digital dual-mode-structure repetitive control approach for the single-phase shunt active power filter (APF), which aims to enhance the tracking ability and eliminate arbitrary order harmonic. The proposed repetitive control scheme blends the characteristics of both odd......-harmonic repetitive control and even-harmonic repetitive control. Moreover, the convergence rate is faster than conventional repetitive controller. Additionally, the parameters have been designed and optimized for the dual-mode structure repetitive control to improve the performance of APF system. Experimental...

Investigation of the impact of main control room digitalization on operators cognitive reliability in nuclear power plants.

Science.gov (United States)

Zhou, Yong; Mu, Haiying; Jiang, Jianjun; Zhang, Li

2012-01-01

Currently, there is a trend in nuclear power plants (NPPs) toward introducing digital and computer technologies into main control rooms (MCRs). Safe generation of electric power in NPPs requires reliable performance of cognitive tasks such as fault detection, diagnosis, and response planning. The digitalization of MCRs has dramatically changed the whole operating environment, and the ways operators interact with the plant systems. If the design and implementation of the digital technology is incompatible with operators' cognitive characteristics, it may have negative effects on operators' cognitive reliability. Firstly, on the basis of three essential prerequisites for successful cognitive tasks, a causal model is constructed to reveal the typical human performance issues arising from digitalization. The cognitive mechanisms which they impact cognitive reliability are analyzed in detail. Then, Bayesian inference is used to quantify and prioritize the influences of these factors. It suggests that interface management and unbalanced workload distribution have more significant impacts on operators' cognitive reliability.

Application of digital control systems in nuclear power plants

International Nuclear Information System (INIS)

Keiper, J.T.

1993-01-01

This paper describes a sampling of recent digital applications, both safety related and non-safety related, in four nuclear power plants and discusses a few of the unique application experiences. Each application accrues unique benefits, but also poses unique problems. A few of the benefits and problems are discussed

Applying Human Factors Evaluation and Design Guidance to a Nuclear Power Plant Digital Control System

Energy Technology Data Exchange (ETDEWEB)

Thomas Ulrich; Ronald Boring; William Phoenix; Emily Dehority; Tim Whiting; Jonathan Morrell; Rhett Backstrom

2012-08-01

The United States (U.S.) nuclear industry, like similar process control industries, has moved toward upgrading its control rooms. The upgraded control rooms typically feature digital control system (DCS) displays embedded in the panels. These displays gather information from the system and represent that information on a single display surface. In this manner, the DCS combines many previously separate analog indicators and controls into a single digital display, whereby the operators can toggle between multiple windows to monitor and control different aspects of the plant. The design of the DCS depends on the function of the system it monitors, but revolves around presenting the information most germane to an operator at any point in time. DCSs require a carefully designed human system interface. This report centers on redesigning existing DCS displays for an example chemical volume control system (CVCS) at a U.S. nuclear power plant. The crucial nature of the CVCS, which controls coolant levels and boration in the primary system, requires a thorough human factors evaluation of its supporting DCS. The initial digital controls being developed for the DCSs tend to directly mimic the former analog controls. There are, however, unique operator interactions with a digital vs. analog interface, and the differences have not always been carefully factored in the translation of an analog interface to a replacement DCS. To ensure safety, efficiency, and usability of the emerging DCSs, a human factors usability evaluation was conducted on a CVCS DCS currently being used and refined at an existing U.S. nuclear power plant. Subject matter experts from process control engineering, software development, and human factors evaluated the DCS displays to document potential usability issues and propose design recommendations. The evaluation yielded 167 potential usability issues with the DCS. These issues should not be considered operator performance problems but rather opportunities

Technical Challenges in the Application and Licensing of Digital Instrumentation and Control Systems in Nuclear Power Plants

International Nuclear Information System (INIS)

2015-01-01

With the modernization of existing analogue instrumentation and control (I&C) systems in nuclear power plants through digital I&C technology, and the implementation of digital I&C systems in new plants, the industry is faced with significant challenges. These challenges appear in the form of difficulties in managing the necessarily incremental transition, highly integrated (and interdependent) architectures, the flexible configurability enabled by digital technology, and uncertainty and inconsistency in licensing digital I&C systems and equipment in the different Member States. This publication discusses 17 major issues that utilities, developers, suppliers and regulatory stakeholders need to consider, so that the industry can capture and benefit from shared experience, recent technological developments, and emerging best practices

Non-linear hybrid control oriented modelling of a digital displacement machine

DEFF Research Database (Denmark)

Pedersen, Niels Henrik; Johansen, Per; Andersen, Torben O.

2017-01-01

Proper feedback control of digital fluid power machines (Pressure, flow, torque or speed control) requires a control oriented model, from where the system dynamics can be analyzed, stability can be proven and design criteria can be specified. The development of control oriented models for hydraulic...... Digital Displacement Machines (DDM) is complicated due to non-smooth machine behavior, where the dynamics comprises both analog, digital and non-linear elements. For a full stroke operated DDM the power throughput is altered in discrete levels based on the ratio of activated pressure chambers....... In this paper, a control oriented hybrid model is established, which combines the continuous non-linear pressure chamber dynamics and the discrete shaft position dependent activation of the pressure chambers. The hybrid machine model is further extended to describe the dynamics of a Digital Fluid Power...

IAEA technical meeting on integrating analog and digital instrumentation and control systems in hybrid main control rooms at nuclear power plants. Book of abstracts

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

The majority of instrumentation and control (I and C) equipment in nuclear power plants in the world was designed 30 to over 45 years ago with analog and relay components, and in some cases rudimentary digital technology. Today, most of these plants continue to operate with a substantial amount of this original I and C equipment that is or soon will be obsolete. Much of this equipment is approaching or exceeding its life expectancy, resulting in increasing maintenance efforts to sustain acceptable system performance. Decreasing availability of replacement parts, and the accelerating deterioration of the infrastructure of manufacturers that support analog technology, accentuate the obsolescence problems and cause operation and maintenance (O and M) cost increases. Refurbishments and license extensions mean that a plant must be supported longer, which will increase the obsolescence issues. In addition, the older technology limits the possibilities for adding new beneficial capabilities to the plant systems and interfaces. New technology provides the opportunity to improve plant performance, human system interface (HSI) functionality, and reliability; to enhance operator performance and reliability, and to address difficulties in finding young professionals with education and experience with older analog technology. Finally, there may be changes in regulatory requirements that could necessitate modernization activities. Modernization of I and C systems and components, using digital equipment to address these obsolescence issues and the need to improve plant performance (e.g., increase power output capacity, reliability, and availability) while maintaining high levels of safety, is a current major issue for nuclear power plants throughout the world. A number of nuclear power utilities are committing to major modernization programs. The need for this modernization will accelerate as plants age, obsolescence issues increase, plants receive license renewals, and features

47 CFR 73.6019 - Digital Class A TV station protection of low power TV, TV translator, digital low power TV and...

Science.gov (United States)

2010-10-01

... power TV, TV translator, digital low power TV and digital TV translator stations. 73.6019 Section 73... low power TV, TV translator, digital low power TV and digital TV translator stations. An application... A TV station will not be accepted if it fails to protect authorized low power TV, TV translator...

Human Reliability analysis for digitized nuclear power plants: Case study on the LingAo II nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Zou, Yan Hua; Zhang, Li [Institute of Human Factors Engineering AND Safety Management, Hunan Institute of Technology, Hengyang (China); Dai, Cao; Li, Peng Cheng; Qing, Tao [Human Factors Institute, University of South China, Hengyang (China)

2017-03-15

The main control room (MCR) in advanced nuclear power plants (NPPs) has changed from analog to digital control system (DCS). Operation and control have become more automated, centralized, and accurate due to the digitalization of NPPs, which has improved the efficiency and security of the system. New issues associated with human reliability inevitably arise due to the adoption of new accident procedures and digitalization of main control rooms in NPPs. The LingAo II NPP is the first digital NPP in China to apply the state-oriented procedure. In order to address issues related to human reliability analysis for DCS and DCS + state-oriented procedure, the Hunan Institute of Technology conducted a research project based on a cooperative agreement with the LingDong Nuclear Power Co. Ltd. This paper is a brief introduction to the project.

Human Reliability Analysis for Digitized Nuclear Power Plants: Case Study on the LingAo II Nuclear Power Plant

Directory of Open Access Journals (Sweden)

Yanhua Zou

2017-03-01

Full Text Available The main control room (MCR in advanced nuclear power plants (NPPs has changed from analog to digital control system (DCS. Operation and control have become more automated, centralized, and accurate due to the digitalization of NPPs, which has improved the efficiency and security of the system. New issues associated with human reliability inevitably arise due to the adoption of new accident procedures and digitalization of main control rooms in NPPs. The LingAo II NPP is the first digital NPP in China to apply the state-oriented procedure. In order to address issues related to human reliability analysis for DCS and DCS + state-oriented procedure, the Hunan Institute of Technology conducted a research project based on a cooperative agreement with the LingDong Nuclear Power Co. Ltd. This paper is a brief introduction to the project.

General digitalized system on nuclear power plants

International Nuclear Information System (INIS)

Akagi, Katsumi; Kadohara, Hozumi; Taniguchi, Manabu

2000-01-01

Hitherto, instrumentation control system in a PWR nuclear power plant has stepwisely adopted digital technology such as application of digital instrumentation control device to ordinary use (primary/secondary system control device, and so on), application of CRT display system to monitoring function, and so forth, to realize load reduction of an operator due to expansion of operation automation range, upgrading of reliability and maintenance due to self-diagnosis function, reduction of mass in cables due to multiple transfer, and upgrading of visual recognition due to information integration. In next term PWR plant instrumentation control system, under consideration of application practice of conventional digital technology, application of general digitalisation system to adopt digitalisation of overall instrumentation control system containing safety protection system, and central instrumentation system (new type of instrumentation system) and to intend to further upgrade economics, maintenance, operability/monitoring under security of reliability/safety is planned. And, together with embodiment of construction program of the next-term plant, verification at the general digitalisation proto-system aiming at establishment of basic technology on the system is carried out. Then, here was described on abstract of the general digitalisation system and characteristics of a digital type safety protection apparatus to be adopted in the next-term plant. (G.K.)

Simple Digital Control of a Two-Stage PFC Converter Using DSPIC30F Microprocessor

DEFF Research Database (Denmark)

Török, Lajos; Munk-Nielsen, Stig

2010-01-01

The use of dsPIC digital signal controllers (DSC) in Switch Mode Power Supply (SMPS) applications opens new perspectives for cheap and flexible digital control solutions. This paper presents the digital control of a two stage power factor corrector (PFC) converter. The PFC circuit is designed...... and built for 70W rated output power. Average current mode control for boost converter and current programmed control for forward converter are implemented on a dsPIC30F1010. Pulse Width Modulation (PWM) technique is used to drive the switching MOSFETs. Results show that digital solutions with ds...

AN ANALYSIS OF TECHNICAL SECURITY CONTROL REQUIREMENTS FOR DIGITAL I&C SYSTEMS IN NUCLEAR POWER PLANTS

Directory of Open Access Journals (Sweden)

JAE-GU SONG

2013-10-01

Full Text Available Instrumentation and control systems in nuclear power plants have been digitalized for the purpose of maintenance and precise operation. This digitalization, however, brings out issues related to cyber security. In the most recent past, international standard organizations, regulatory institutes, and research institutes have performed a number of studies addressing these systems cyber security. In order to provide information helpful to the system designers in their application of cyber security for the systems, this paper presents methods and considerations to define attack vectors in a target system, to review and select the requirements in the Regulatory Guide 5.71, and to integrate the results to identify applicable technical security control requirements. In this study, attack vectors are analyzed through the vulnerability analyses and penetration tests with a simplified safety system, and the elements of critical digital assets acting as attack vectors are identified. Among the security control requirements listed in Appendices B and C to Regulatory Guide 5.71, those that should be implemented into the systems are selected and classified in groups of technical security control requirements using the results of the attack vector analysis. For the attack vector elements of critical digital assets, all the technical security control requirements are evaluated to determine whether they are applicable and effective, and considerations in this evaluation are also discussed. The technical security control requirements in three important categories of access control, monitoring and logging, and encryption are derived and grouped according to the elements of attack vectors as results for the sample safety system.

The cyclical monitoring system for digital power supplies at SSRF

International Nuclear Information System (INIS)

Tang Junlong; Li Deming; Shen Tianjian

2009-01-01

Based on available digital PS testing system and long-distance monitoring hardwares, the cyclical monitoring system for digital power supplies (PS) was developed at SSRF. Two models, i.e.long-distance cyclical monitoring and local cyclical monitoring, were established. The software developed in LabVIEW language was applied to the two models without any user interface modification. The user interface is simple. The system is suitable for debugging the digital PSs during long-distance monitoring and examining the performance. The long-distance model imitates the digital PSs' status for fault analysis and communication between the digital PS and the centre control room. The local model simultaneously examines stability of 18 new PSs for 24 h, monitors the PS controller, and detects malfunction. Parameters and status of the controller can be stored in Excel or Text file. The two models have been used at SSRF for monitoring the digital PSs. (authors)

The development of ZPRL digital control system

International Nuclear Information System (INIS)

Hsu, Jin-Den; Yang, Sheau-Yieh; Shieh, Der-Jhy.

1992-01-01

Zero Power Reactor at Lung-Tan (ZPRL) is a small open-pool type research reactor located at Lung-Tan, Taiwan. The reactor achieved its first criticality in 1971. An analog control system has been used for almost over 20 years and the power regulating function is found gradually out of order. Therefore, we decided to develop a digital control system to replace the existing analog one. A prototype system has been developed and under on-line test now. The proposed ZPRL digital control system consists of three personal computers. These computers are used as (1) operator console, (2) data acquisition and control system, and (3) auxiliary and backup system. The operator console contains all the man-machine interface functions in the form of graphic display. The data acquisition and control system converts the analog signals into digital ones and feeds to the other two computers. The auxiliary and backup system normally emulates a strip chart recorder for the linear and logarithmic neutron powers and also acts as a transient recorder to keep the trace of the operating conditions on demand or when the reactor scrams. On-line test shows that the system does assure a satisfactory performance. It is not only as good as the analog system but also has the advantages of flexibility, testibility, and a user friendly man-machine interface. (author)

Bus-oriented digital control techniques in nuclear power plants

International Nuclear Information System (INIS)

Salm, M.

1987-01-01

The author states the conservative principles which govern the authorization procedures for nuclear reactor control systems. Using the example of a feedwater supply regulator, employing a digital, bus-oriented control system, he describes how the stigma attached to the word nuclear can be alleviated. (G.T.H.)

HIGH RESOLUTION ANALOG / DIGITAL POWER SUPPLY CONTROLLER

International Nuclear Information System (INIS)

Medvedko, Evgeny A

2003-01-01

Corrector magnets for the SPEAR-3 synchrotron radiation source require precision, high-speed control for use with beam-based orbit feedback. A new Controller Analog/Digital Interface card (CANDI) has been developed for these purposes. The CANDI has a 24-bit DAC for current control and three 24-bit Δ-Σ ADCs to monitor current and voltages. The ADCs can be read and the DAC updated at the 4 kHz rate needed for feedback control. A precision 16-bit DAC provides on-board calibration. Programmable multiplexers control internal signal routing for calibration, testing, and measurement. Feedback can be closed internally on current setpoint, externally on supply current, or beam position. Prototype and production tests are reported in this paper. Noise is better than 17 effective bits in a 10 mHz to 2 kHz bandwidth. Linearity and temperature stability are excellent

76 FR 11680 - Digital Low Power Television, Television Translator, and Television Booster Stations and Digital...

Science.gov (United States)

2011-03-03

...] Digital Low Power Television, Television Translator, and Television Booster Stations and Digital Class A... Commission's Rules to Establish Rules for Digital Low Power, Television Translator, and Television Booster... Digital Low Power Television Translator, Television Booster Stations, and to Amend Rules for Digital Class...

Revolution of Nuclear Power Plant Design Through Digital Technology

International Nuclear Information System (INIS)

Zhang, L.; Shi, J.; Chen, W.

2015-01-01

In the digital times, digital technology has penetrated into every industry. As the highest safety requirement standard, nuclear power industry needs digital technology more to breed high quality and efficiency. Digital power plant is derived from digital design and the digitisation of power plant transfer is an inevitable trend. This paper introduces the technical solutions and features of digital nuclear power plant construction by Shanghai Nuclear Engineering Research & Design Institute, points out the key points and technical difficulties that exist in the process of construction and can serve as references for further promoting construction of digital nuclear power plant. Digital technology is still flourishing. Although many problems will be encountered in construction, it is believed that digital technology will make nuclear power industry more safe, cost-effective and efficient. (author)

Digital I and C for nuclear power plant

International Nuclear Information System (INIS)

Gemst, P. van

1993-01-01

A summary is given of the past experience (process I and C, digital controllers, Power Range Monitoring system) and future plans (integrated plant I and C, control room) of ABB Atom for programmable I and C at nuclear power plants. ABB Atom has designed and supplied an appreciable quantity of software based equipment for nuclear power plants. These have been supplied for both new plants as well as for backfitting. The well proven ABB Master system has been used for the supply of I and C equipment for these projects and will continue to be used in the future. (Z.S.) 1 fig

Digital signal array processor for NSLS booster power supply upgrade

International Nuclear Information System (INIS)

Olsen, R.; Dabrowski, J.; Murray, J.

1993-01-01

The booster at the NSLS is being upgraded from 0.75 to 2 pulses per second. To accomplish this, new power supplied for the dipole, quadrupole, and sextupole have been installed. This paper will outline the design and function of the digital signal processor used as the primary control element in the power supply control system

Some aspects of programmable digital systems usage in nuclear power plants

International Nuclear Information System (INIS)

Mandic, D.; Smolej, M.; Sucic, B.

2004-01-01

During the operation of the NPP Krsko - NEK and other nuclear power plants, it has been recognized that certain issues related to the usage of digital equipment and associated software in NPP technological process protection, control and monitoring, are usually not adequately addressed in the existing programs and procedures. Moreover, often the problems related to the programmable digital systems usage are not understood correctly, which means that they can not be treated properly. Owing to the specifics of the programmable digital systems usage they have to be treated in a different way than other plant equipment and related documentation. The term as well as the process of Process Computers Configuration Control was introduced to control, among other issues, three 10CFR50 Appendix B quality requirements related to the Process Computers application in NPP: Design Control, Document Control, Identification and Control of Materials, Parts and Components. Based on the experience from NEK and published experience from other NPP and other organizations, this paper sheds light on specifics of the programmable digital systems usage in nuclear power plants. The wording Programmable Digital Systems was used rather than Process Computers, to emphasize wide area of applicability of this term: from simple digital components with burned-in programs to the PLC (Programmable Logic Controllers) and large process computer systems. In order to satisfy requirements of the Process Computer Configuration Control, specific characteristics and specific problems related to the usage of programmable digital systems require specific treatment of these issues. This paper describes those specific characteristics and traditional misunderstandings, false beliefs, false expectations and common errors that are most frequently committed in the life cycle of the programmable digital systems, as well as consequences and problems that could develop. The paper also refers to the regulations, industry

Digital computer control of a research nuclear reactor

International Nuclear Information System (INIS)

Crawford, Kevan

1986-01-01

Currently, the use of digital computers in energy producing systems has been limited to data acquisition functions. These computers have greatly reduced human involvement in the moment to moment decision process and the crisis decision process, thereby improving the safety of the dynamic energy producing systems. However, in addition to data acquisition, control of energy producing systems also includes data comparison, decision making, and control actions. The majority of the later functions are accomplished through the use of analog computers in a distributed configuration. The lack of cooperation and hence, inefficiency in distributed control, and the extent of human interaction in critical phases of control have provided the incentive to improve the later three functions of energy systems control. Properly applied, centralized control by digital computers can increase efficiency by making the system react as a single unit and by implementing efficient power changes to match demand. Additionally, safety will be improved by further limiting human involvement to action only in the case of a failure of the centralized control system. This paper presents a hardware and software design for the centralized control of a research nuclear reactor by a digital computer. Current nuclear reactor control philosophies which include redundancy, inherent safety in failure, and conservative yet operational scram initiation were used as the bases of the design. The control philosophies were applied to the power monitoring system, the fuel temperature monitoring system, the area radiation monitoring system, and the overall system interaction. Unlike the single function analog computers that are currently used to control research and commercial reactors, this system will be driven by a multifunction digital computer. Specifically, the system will perform control rod movements to conform with operator requests, automatically log the required physical parameters during reactor

Centralized digital computer control of a research nuclear reactor

International Nuclear Information System (INIS)

Crawford, K.C.

1987-01-01

A hardware and software design for the centralized control of a research nuclear reactor by a digital computer are presented, as well as an investigation of automatic-feedback control. Current reactor-control philosophies including redundancy, inherent safety in failure, and conservative-yet-operational scram initiation were used as the bases of the design. The control philosophies were applied to the power-monitoring system, the fuel-temperature monitoring system, the area-radiation monitoring system, and the overall system interaction. Unlike the single-function analog computers currently used to control research and commercial reactors, this system will be driven by a multifunction digital computer. Specifically, the system will perform control-rod movements to conform with operator requests, automatically log the required physical parameters during reactor operation, perform the required system tests, and monitor facility safety and security. Reactor power control is based on signals received from ion chambers located near the reactor core. Absorber-rod movements are made to control the rate of power increase or decrease during power changes and to control the power level during steady-state operation. Additionally, the system incorporates a rudimentary level of artificial intelligence

An analysis of Technical Security Control Requirements For Digital I and C Systems in Nuclear Power Plants

International Nuclear Information System (INIS)

Song, Jaegu; Lee, Jungwoon; Park, Geeyong; Kwon, Keechoon; Lee, Dongyoung; Lee, Cheolkwon

2013-01-01

Instrumentation and control systems in nuclear power plants have been digitalized for the purpose of maintenance and precise operation. This digitalization, however, brings out issues related to cyber security. In the most recent past, international standard organizations, regulatory institutes, and research institutes have performed a number of studies addressing these systems cyber security. In order to provide information helpful to the system designers in their application of cyber security for the systems, this paper presents methods and considerations to define attack vectors in a target system, to review and select the requirements in the Regulatory Guide 5.71, and to integrate the results to identify applicable technical security control requirements. In this study, attack vectors are analyzed through the vulnerability analyses and penetration tests with a simplified safety system, and the elements of critical digital assets acting as attack vectors are identified. Among the security control requirements listed in Appendices B and C to Regulatory Guide 5.71, those that should be implemented into the systems are selected and classified in groups of technical security control requirements using the results of the attack vector analysis. For the attack vector elements of critical digital assets, all the technical security control requirements are evaluated to determine whether they are applicable and effective, and considerations in this evaluation are also discussed. The technical security control requirements in three important categories of access control, monitoring and logging, and encryption are derived and grouped according to the elements of attack vectors as results for the sample safety system

An analysis of Technical Security Control Requirements For Digital I and C Systems in Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Song, Jaegu; Lee, Jungwoon; Park, Geeyong; Kwon, Keechoon; Lee, Dongyoung; Lee, Cheolkwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2013-10-15

Instrumentation and control systems in nuclear power plants have been digitalized for the purpose of maintenance and precise operation. This digitalization, however, brings out issues related to cyber security. In the most recent past, international standard organizations, regulatory institutes, and research institutes have performed a number of studies addressing these systems cyber security. In order to provide information helpful to the system designers in their application of cyber security for the systems, this paper presents methods and considerations to define attack vectors in a target system, to review and select the requirements in the Regulatory Guide 5.71, and to integrate the results to identify applicable technical security control requirements. In this study, attack vectors are analyzed through the vulnerability analyses and penetration tests with a simplified safety system, and the elements of critical digital assets acting as attack vectors are identified. Among the security control requirements listed in Appendices B and C to Regulatory Guide 5.71, those that should be implemented into the systems are selected and classified in groups of technical security control requirements using the results of the attack vector analysis. For the attack vector elements of critical digital assets, all the technical security control requirements are evaluated to determine whether they are applicable and effective, and considerations in this evaluation are also discussed. The technical security control requirements in three important categories of access control, monitoring and logging, and encryption are derived and grouped according to the elements of attack vectors as results for the sample safety system.

Application of 2DOF controller for reactor power control. Verification by numerical simulation

International Nuclear Information System (INIS)

Ishikawa, Nobuyuki; Suzuki, Katsuo

1996-09-01

In this report the usefulness of the two degree of freedom (2DOF) control is discussed to improve the reference response characteristics and robustness for reactor power control system. The 2DOF controller consists of feedforward and feedback elements. The feedforward element was designed by model matching method and the feedback element by solving the mixed sensitivity problem of H ∞ control. The 2DOF control gives good performance in both reference response and robustness to disturbance and plant perturbation. The simulation of reactor power control was performed by digitizing the 2DOF controller with the digital control periods of 10[msec]. It is found that the control period of 10[msec] is enough not to make degradation of the control performance by digitizing. (author)

Innovative Digitally Controlled Particle Accelerator Magnet Power Supply

DEFF Research Database (Denmark)

Nielsen, Rasmus Ørndrup; Bidoggia, Benoit; Maheshwari, Ram Krishan

2013-01-01

Particle accelerator magnet power supplies needs to be extremely precise. A new and innovative power supply for particle accelerator magnets is proposed. The topologies for the input and the output converter are shown and the control architecture is described.......Particle accelerator magnet power supplies needs to be extremely precise. A new and innovative power supply for particle accelerator magnets is proposed. The topologies for the input and the output converter are shown and the control architecture is described....

An Accurate Transmitting Power Control Method in Wireless Communication Transceivers

Science.gov (United States)

Zhang, Naikang; Wen, Zhiping; Hou, Xunping; Bi, Bo

2018-01-01

Power control circuits are widely used in transceivers aiming at stabilizing the transmitted signal power to a specified value, thereby reducing power consumption and interference to other frequency bands. In order to overcome the shortcomings of traditional modes of power control, this paper proposes an accurate signal power detection method by multiplexing the receiver and realizes transmitting power control in the digital domain. The simulation results show that this novel digital power control approach has advantages of small delay, high precision and simplified design procedure. The proposed method is applicable to transceivers working at large frequency dynamic range, and has good engineering practicability.

Tribodynamic Modeling of Digital Fluid Power Motors

DEFF Research Database (Denmark)

Johansen, Per

. In fluid power motoring and pumping units, a significant problem is that loss mechanisms do not scale down with diminishing power throughput. Although machines can reach peak efficiencies above 95%, the actual efficiency during operation, which includes part-load situations, is much lower. The invention...... of digital fluid power displacement units has been able to address this problem. The main idea of the digital fluid power displacement technology is to disable individual chambers, by use of electrical actuated valves. A displacement chamber is disabled by keeping the valve, between the chamber and the low...... design methods and tools are important to the development of digital fluid power machines. The work presented in this dissertation is part of a research program focusing on the development of digital fluid power MW-motors for use in hydraulic drive train in wind turbines. As part of this development...

A digital joint controller for manipulators

International Nuclear Information System (INIS)

Holt, E.J.; Palmer, D.E.B.

1993-01-01

Nuclear Electric's hydraulic heavy duty manipulators are used at a number of Magnox Power Stations for a wide variety of tasks. In recent years there has been a trend towards the use of manipulators for tasks requiring increasing precision of tip positioning. In order to meet this requirement, a digital controller has been designed to replace the analogue controller board used in almost all manipulator control systems. The new controller allows the programming of a wide range of closed loop control algorithms. Position and drive signal data may be passed to and from the controller by digital means, allowing direct connection to a graphical display system and/or a computer executing a guidance algorithm. The hardware and software design are outlined and performance in the laboratory and the field is reported. (author)

Digital power - Electricity gets intelligent; Digitalstrom - Strom wird intelligent

Energy Technology Data Exchange (ETDEWEB)

Lieberherr, M.; Staub, R.

2007-07-01

This article takes a look at the setting up of the 'Viagialla' digital power alliance on the 7{sup th} of July 2007 at the Swiss Federal Institute of Technology in Zurich, Switzerland. The name 'Viagialla' is derived from the Italian for 'the yellow way'. The idea behind the project - to encourage the work of young students on machines and new developments - is discussed. The alliance encourages the use of energy forms that are available in great abundance such as solar energy and wind, thus preventing the so-called 'power-gap' and making the construction of new nuclear power stations unnecessary. The name 'digital power' refers to a new method of transmitting data over power lines on the basis of a new microchip controller. This chip can even be placed in small terminal blocks thus allowing electrical apparatus to communicate with switches and other devices. In this way, the apparatus can be remotely controlled. The developers of the system hope that their system will enable 'intelligent living' and intercommunication between normal domestic devices. External communication over the Internet is also foreseen.

Digital Signal Processing and Control for the Study of Gene Networks

Science.gov (United States)

Shin, Yong-Jun

2016-04-01

Thanks to the digital revolution, digital signal processing and control has been widely used in many areas of science and engineering today. It provides practical and powerful tools to model, simulate, analyze, design, measure, and control complex and dynamic systems such as robots and aircrafts. Gene networks are also complex dynamic systems which can be studied via digital signal processing and control. Unlike conventional computational methods, this approach is capable of not only modeling but also controlling gene networks since the experimental environment is mostly digital today. The overall aim of this article is to introduce digital signal processing and control as a useful tool for the study of gene networks.

Design of full digital 50 kV electronic gun high voltage power supply

International Nuclear Information System (INIS)

Ge Lei; Shang Lei

2014-01-01

The design of full digital electronic gun high voltage power supply based on DSP was introduced in this paper. This power supply has innovations of full digital feedback circuit and PID closed-loop control mode. The application of high frequency resonant converter circuit reduces the size of the resonant element and transformer. The current-coupling distributed high voltage transformer and rectifier circuit were employed in this power supply. By this way, the power supply efficiency is improved and the number of distributed parameters is reduced, and the rectifier circuit could work under the oil-free environment. This power supply has been used in electronic grid-control high voltage system of the irradiation accelerator. (authors)

Optimal control of a wind turbine with digital fluid power transmission

DEFF Research Database (Denmark)

Pedersen, Niels Henrik; Johansen, Per; Andersen, Torben O.

2018-01-01

. The power throughput of a full stroke operated digital displacement machine is quantized by the number of pressure chambers. The dynamics of each pressure chamber may be described by highly nonlinear continuous differential equations, whereas the input is discretely updated and binary (active or inactive...

Recent control and instrumentation systems for BWR nuclear power plant

International Nuclear Information System (INIS)

Fujii, Hiroaki; Higashikawa, Yuichi; Sato, Hideyuki

1990-01-01

For the needs of the more stable operation of nuclear power stations, the upgrading of the measurement and control system for BWRs has been promoted by positively introducing remarkably advancing electronic technology. Further, it is aimed at to construct the synthetic digitized measurement and control system for nuclear power stations to heighten the operation reliability in ABWRs. As the first step of the development in the synthetic digitization, the monitoring and control system for radioactive waste treatment was put in practical use for No.5 plant of Kashiwazaki, Kariwa Nuclear Power Station, Tokyo Electric Power Co., Inc. Hitachi Ltd. has promoted the development and the application to actual plants of the measurement and control system for BWRs, in which digital control technology, optical information transmission technology and the operation-supporting technology using a computer were utilized. Hereafter, it is intended to expand the application of digital measurement and control aiming at improving the reliability, operation performance and maintainability. The nuclear power plant control complex with advanced man-machine interface-90 (NUCAMM-90) was developed, and its application to actual plants is planned. (K.I.)

Use of a graphical user interface approach for digital and physical simulation in power systems control education

International Nuclear Information System (INIS)

Shoults, R.R.; Barrera-Cardiel, E.

1992-01-01

This paper presents the design of a laboratory with software and hardware structures for digital and physical simulation in the area of Power Systems Control Education. The hardware structure includes a special man-machine interface designed with a graphical user interface approach. This interface allows the user full control over the simulation and provides facilities for the study of the response of the simulated system. This approach is illustrated with the design of a control system for a physically based HVDC transmission system model

Digital control system of a steam generator water level by LQG optimal method

International Nuclear Information System (INIS)

Lee, Yoon Joon

1993-01-01

A digital control system for the steam generator water level control is developed using LQG optimal design method. To describe the more realistic situaton, a feedwater valve actuator is assumed to be of the first order lagger and is included in the overall control system. By composing the digital control circuit in such a way that the overall control system consists of two sub-systems of feedwater station and feedback loop digital controller, the design procedure is divided into two independent steps. The feedwater station system is described in the error dynamics of an ordinary regulator system. The optimal gains are obtained by LQ method which imposes the constraints of the feedwater valve motion as well as on the output deviations. Developed also is a Kalman observer on account of the flow measurement uncertainty at low power. Then a digital controller on the feedback loop is designed so that the system maintains the same stability margins for all power ranges. The simulation results show thst the optimal digital system has a good control characteristics despite the adverse dynamics of a steam generator at low power. (Author)

Digital control in nuclear power plants

International Nuclear Information System (INIS)

Bouzon, B.

1984-01-01

This document presents the latest automatic control structures used in the programmable control systems of 13.00 MW nuclear power plants constructed by Electricite de France. The impact of this technological innovation goes beyond a straightforward design modification; in addition to the new range of processes made possible, it permits far-reaching changes in the working method employed at the design office and in the field. (author)

Design of DSP-based high-power digital solar array simulator

Science.gov (United States)

Zhang, Yang; Liu, Zhilong; Tong, Weichao; Feng, Jian; Ji, Yibo

2013-12-01

To satisfy rigid performance specifications, a feedback control was presented for zoom optical lens plants. With the increasing of global energy consumption, research of the photovoltaic(PV) systems get more and more attention. Research of the digital high-power solar array simulator provides technical support for high-power grid-connected PV systems research.This paper introduces a design scheme of the high-power digital solar array simulator based on TMS320F28335. A DC-DC full-bridge topology was used in the system's main circuit. The switching frequency of IGBT is 25kHz.Maximum output voltage is 900V. Maximum output current is 20A. Simulator can be pre-stored solar panel IV curves.The curve is composed of 128 discrete points .When the system was running, the main circuit voltage and current values was feedback to the DSP by the voltage and current sensors in real-time. Through incremental PI,DSP control the simulator in the closed-loop control system. Experimental data show that Simulator output voltage and current follow a preset solar panels IV curve. In connection with the formation of high-power inverter, the system becomes gridconnected PV system. The inverter can find the simulator's maximum power point and the output power can be stabilized at the maximum power point (MPP).

Digital control of plasma position in Damavand tokamak

Energy Technology Data Exchange (ETDEWEB)

Emami, M.; Babazadeh, A.R.; Roshan, M.V.; Memarzadeh, M.; Habibi, H. [Atomic Energy Organization of Iran (AEOI), Tehran (Iran, Islamic Republic of). Nuclear Fusion Research Center. Plasma Physics Lab.

2002-03-01

Plasma position control is one of the important issues in the design and operation of tokamak fusion research device. Since a tokamak is basically an electrical system consisting of power supplies, coils, plasma and eddy currents, a model in which these components are treated as an electrical circuits is used in designing Damavand plasma position control system. This model is used for the simulation of the digital control system and its parameters have been verified experimentally. In this paper, the performance of a high-speed digital controller as well as a simulation study and its application to the Damavand tokamak is discussed. (author)

Experimental development of power reactor intelligent control

International Nuclear Information System (INIS)

Edwards, R.M.; Garcia, H.E.; Lee, K.Y.

1992-01-01

The US nuclear utility industry initiated an ambitious program to modernize the control systems at a minimum of ten existing nuclear power plants by the year 2000. That program addresses urgent needs to replace obsolete instrumentation and analog controls with highly reliable state-of-the-art computer-based digital systems. Large increases in functionality that could theoretically be achieved in a distributed digital control system are not an initial priority in the industry program but could be logically considered in later phases. This paper discusses the initial development of an experimental sequence for developing, testing, and verifying intelligent fault-accommodating control for commercial nuclear power plant application. The sequence includes an ultra-safe university research reactor (TRIGA) and a passively safe experimental power plant (Experimental Breeder Reactor 2)

Integrating software reliability concepts into risk and reliability modeling of digital instrumentation and control systems used in nuclear power plants

International Nuclear Information System (INIS)

Arndt, S. A.

2006-01-01

As software-based digital systems are becoming more and more common in all aspects of industrial process control, including the nuclear power industry, it is vital that the current state of the art in quality, reliability, and safety analysis be advanced to support the quantitative review of these systems. Several research groups throughout the world are working on the development and assessment of software-based digital system reliability methods and their applications in the nuclear power, aerospace, transportation, and defense industries. However, these groups are hampered by the fact that software experts and probabilistic safety assessment experts view reliability engineering very differently. This paper discusses the characteristics of a common vocabulary and modeling framework. (authors)

A new digital pulse power supply in heavy ion research facility in Lanzhou

Science.gov (United States)

Wang, Rongkun; Chen, Youxin; Huang, Yuzhen; Gao, Daqing; Zhou, Zhongzu; Yan, Huaihai; Zhao, Jiang; Shi, Chunfeng; Wu, Fengjun; Yan, Hongbin; Xia, Jiawen; Yuan, Youjin

2013-11-01

To meet the increasing requirements of the Heavy Ion Research Facility in Lanzhou-Cooler Storage Ring (HIRFL-CSR), a new digital pulse power supply, which employs multi-level converter, was designed. This power supply was applied with a multi H-bridge converters series-parallel connection topology. A new control model named digital power supply regulator system (DPSRS) was proposed, and a pulse power supply prototype based on DPSRS has been built and tested. The experimental results indicate that tracking error and ripple current meet the requirements of this design. The achievement of prototype provides a perfect model for HIRFL-CSR power supply system.

A study on the optimal replacement periods of digital control computer's components of Wolsung nuclear power plant unit 1

International Nuclear Information System (INIS)

Mok, Jin Il; Seong, Poong Hyun

1993-01-01

Due to the failure of the instrument and control devices of nuclear power plants caused by aging, nuclear power plants occasionally trip. Even a trip of a single nuclear power plant (NPP) causes an extravagant economical loss and deteriorates public acceptance of nuclear power plants. Therefore, the replacement of the instrument and control devices with proper consideration of the aging effect is necessary in order to prevent the inadvertent trip. In this paper we investigated the optimal replacement periods of the control computer's components of Wolsung nuclear power plant Unit 1. We first derived mathematical models of optimal replacement periods to the digital control computer's components of Wolsung NPP Unit 1 and calculated the optimal replacement periods analytically. We compared the periods with the replacement periods currently used at Wolsung NPP Unit 1. The periods used at Wolsung is not based on mathematical analysis, but on empirical knowledge. As a consequence, the optimal replacement periods analytically obtained and those used in the field show a little difference. (Author)

75 FR 63766 - Digital Low Power Television, Television Translator, and Television Booster Stations and Digital...

Science.gov (United States)

2010-10-18

...] Digital Low Power Television, Television Translator, and Television Booster Stations and Digital Class A... TV, TV Translator or TV Booster Station, FCC Form 346; 47 CFR 74.793(d); LPTV Out-of-Core Digital... collection requirements: 47 CFR 74.793(d) proposes that certain digital low power and TV translator stations...

Rolls-Royce digital Rod Control System

International Nuclear Information System (INIS)

Pouillot, M.

2010-01-01

Full text of publication follows: Rolls-Royce has developed a new generation of Rod Control System, based on 40 years of experience. The fifth-generation Rod Control System (RCS) from Rolls-Royce offers a reliable, modular design with adaptability to your preferred platform, for modernization projects or new reactors. Flexible implementation provides the option for you to keep existing cabinets, which permits you to optimize installation approach. Main features for the power part: - Control Rod Drive Mechanism (CRDM) type: 3-coil. - Independent control of each sub-bank. - Each sub-bank is controlled by a cycler unit and 3 identical power racks, each including 4 identical power modules and a common power-supply module. - Coil-per-coil digital control: each power module embeds power-conversion, current-control, and current-monitoring functions for one coil. Control and monitoring are carried out by separate electronics in the module. Current is digitized and fully monitored by means of min-max templates. - A double-hold function is included: a power module assigned to a gripper will activate its coil if a fault risking to cause a reactor trip occurs. - Power modules are standardized, hot-pluggable and self-configured: a power module includes a set of parameters for each type of coil SG, MG, LC. The module recognizes the rack it is plugged in, and chooses automatically parameters to be used. Main benefits: - Reduced operational, maintenance, training, and inventory costs: standardization of power modules and integration of control and monitoring on the same PC-card lead to a drastic reduction of spare part types, and simplification of the system. - Easy maintenance: - Replacement of a power module solves nearly all failures due to current control or monitoring for a coil. It is done instantly thanks to hot-plug capability. - On the front plate of power-modules, LEDs provide useful information for diagnostic: current setpoint from cycler, output current bar

Impact of Advanced Alarm Systems and Information Displays on Human Reliability in the Digital Control Room of Nuclear Power Plants

International Nuclear Information System (INIS)

Kim, Jong Hyun; Dang, Vinh N

2011-01-01

This paper discusses the potential impacts of two advanced features of digital control rooms, alarm systems and information display systems, on the Human Reliability Analysis (HRA) in nuclear power plants. Although the features of digital control rooms have already been implemented in new or upgraded nuclear power plants, HRAs have so far not taken much credit for these features. In this circumstance, this paper aims at examining the potential effects of these features on human performance and discussing how these effects can be addressed with existing HRA methods. A conclusion derivable from past experimental studies is that those features are supportive in the severe conditions such as complex scenarios and knowledge-based works. However, in the less complex scenarios and rule-based work, they may have no difference with or sometimes negative impacts on operator performance. The discussion about the impact on the HRA is provided on the basis on the THERP method

Modernization of control system using the digital control system

International Nuclear Information System (INIS)

Carrasco, J. A.; Fernandez, L.; Jimenez, A.

2002-01-01

Nowadays, all plant automation tendencies are based on the use of Digital Control System. In big industrial plants the control systems employed are Distributed Control Systems (DCS). The addition of these systems in nuclear power plants,implies an important adaptation process, because most of them were installed using analog control systems. This paper presents the objectives and the first results obtained, in a modernization project, focused in obtaining an engineering platform for making test and analysis of changes prior to their implementation in a nuclear plant. Modernization, Upgrade, DCS, Automation, Simulation, Training. (Author)

Control system security in nuclear power plant

International Nuclear Information System (INIS)

Li Jianghai; Huang Xiaojin

2012-01-01

The digitalization and networking of control systems in nuclear power plants has brought significant improvements in system control, operation and maintenance. However, the highly digitalized control system also introduces additional security vulnerabilities. Moreover, the replacement of conventional proprietary systems with common protocols, software and devices makes these vulnerabilities easy to be exploited. Through the interaction between control systems and the physical world, security issues in control systems impose high risks on health, safety and environment. These security issues may even cause damages of critical infrastructures and threaten national security. The importance of control system security by reviewing several control system security incidents that happened in nuclear power plants was showed in recent years. Several key difficulties in addressing these security issues were described. Finally, existing researches on control system security and propose several promising research directions were reviewed. (authors)

Atucha II nuclear power plant digital simulation

International Nuclear Information System (INIS)

Santome, D.; Rovere, L.A.T.

1987-01-01

This paper describes the start-up of a digital simulation code apt to be performed in real time of Atucha II nuclear power plant, foreseeing its subsequent usage in a Basic Principles Simulator. Adaptability and modification of existing routines and development of modules in order to incorporate the necessary variables dynamics to couple the different modes, were the main tasks. The mathematical model used allows the representation of the following sub-systems: a) a reactor's core point model, which comprehends the neutronic kinetics, fission and decaying powers, thermal transfer and Xe-poisoning calculation; b) pressurizer, which considers two sub-systems that may or may not be in thermodynamic equilibrium, both in two phases; c) coolants and moderators bonds considering separate moderator loops with the aim of introducing asymmetric perturbations; d) secondary sub-subsystem, which includes the feed water loop, pumps, steam generators and control valves; e) steam generators; f) control and safety systems, including power control, steam generators levels, moderator's temperature primary loop system, limitations and protection. (Author)

Advanced digital technology - improving nuclear power plant performance through maintainability

International Nuclear Information System (INIS)

Ford, J.L.; Senechal, R.R.; Altenhein, G.D.; Harvey, R.P.

1998-01-01

In today's energy sector there is ever increasing pressure on utilities to operate power plants at high capacity factors. To ensure nuclear power is competitive into the next century, it is imperative that strategic design improvements be made to enhance the performance of nuclear power plants. There are a number of factors that affect a nuclear power plant's performance; lifetime maintenance is one of the major contributors. The maturing of digital technology has afforded ABB the opportunity to make significant design improvements in the area of maintainability. In keeping with ABB's evolutionary advanced nuclear plant design approach, digital technology has systematically been incorporated into the control and protection systems of the most recent Korean nuclear units in operation and under construction. One example of this was the multi-functional design team approach that was utilized for the development of ABB's Digital Plant Protection System (DPPS). The design team consisted of engineers, maintenance technicians, procurement specialists and manufacturing personnel in order to provide a complete perspective on all facets of the design. The governing design goals of increased reliability and safety, simplicity of design, use of off-the-shelf products and reduced need for periodic surveillance testing were met with the selection of proven ABB-Advant Programmable Logic Controllers (PLCs) as the heart of the DPPS. The application of digital PLC technology allows operation for extended periods without requiring routine maintenance or re-calibration. A well documented commercial dedication program approved by the United States Nuclear Regulatory Commission (US NRC) as part of the System 80+ TM Advanced Light Water Reactor Design Certification Program, allowed the use of off-the shelf products in the design of the safety protection system. In addition, a number of mechanical and electrical improvements were made which support maintainability. The result is a DPPS

LQR Feedback Control Development for Wind Turbines Featuring a Digital Fluid Power Transmission System

DEFF Research Database (Denmark)

Pedersen, Niels Henrik; Johansen, Per; Andersen, Torben O.

2016-01-01

with a DFP motor, which has been combined with the NREL 5-MW reference wind turbine model. A classical variable speed control strategy for wind speeds below rated is proposed for the turbine, where the pump displacement is fixed and the digital motor displacement is varied for pressure control. The digital...... for such digital systems are complicated by its non-smooth behavior. In this paper a control design approach for a digital displacement machine® is proposed and a performance analysis of a wind turbine using a DFP transmission is presented. The performance evaluation is based on a dynamic model of the transmission...... invariant model. Using full-field flow wind profiles as input, the design approach and control performance is verified by simulation in the dynamic model of the wind turbine featuring the DFP transmission. Additionally, the performance is compared to that of the conventional NREL reference turbine...

Digital Components in Swedish NPP Power Systems

International Nuclear Information System (INIS)

Karlsson, Mattias; Eriksson, Tage

2015-01-01

Swedish nuclear power plants have over the last 20 years of operation modernised or exchanged several systems and components of the electrical power system. Within these works, new components based on digital technology have been employed in order to realize functionality that was previously achieved by using electro-mechanical or analogue technology. Components and systems such as relay protection, rectifiers, inverters, variable speed drives and diesel-generator sets are today equipped with digital components. Several of the systems and components fulfil functions with a safety-role in the NPP. Recently, however, a number of incidents have occurred which highlight deficiencies in the design or HMI of the equipment, which warrants questions whether there are generic problems with some applications of digital components that needs to be addressed. The use of digital components has presented cost effective solutions, or even the only available solution on the market enabling a modernisation. The vast majority of systems using digital components have been operating without problems and often contribute to improved safety but the challenge of non-detectable, or non-identifiable, failure modes remain. In this paper, the extent to which digital components are used in Swedish NPP power systems will be presented including a description of typical applications. Based on data from maintenance records and fault reports, as well as interviews with designers and maintenance personnel, the main areas where problems have been encountered and where possible risks have been identified will be described. The paper intends to investigate any 'tell-tales' that could give signals of unwanted behaviour. Furthermore, particular benefits experienced by using digital components will be highlighted. The paper will also discuss the safety relevance of these findings and suggest measures to improve safety in the application of digital components in power systems. (authors)

Digital control for the Penn State Breazeale reactor

International Nuclear Information System (INIS)

Raiskums, G.A.

1991-01-01

Digital control has been an integral part of Canada deuterium uranium (CANDU) nuclear power reactor technology since the 1960s. Much of the high CANDU production reliability can be attributed to the fault-tolerant and flexible control algorithms achievable with digital control. Atomic Energy of Canada Limited (AECL) has now transported this technology to research reactors, using industrial-grade microcomputers to solve equipment aging and spares obsolescence problems so prevalent at older installations. The open architecture of the Intel 8086-based computers provides for wide availability and reasonably priced, quality hardware from numerous sources. AECL recently supplied the Pennsylvania State University Breazeale Reactor (PSBR) with a new console containing a digital control and monitoring system. The reactor safety system (RSS) was also replaced with hardwired relay logic and truly analog state-of-the-art wide range nuclear instrumentation supplied by AECL's subcontractor, Gamma-Metrics. Retaining analog hardware for the mandated RSS functions was key to minimizing licensing efforts and the extensive verification and validation that would be required for safety system software. This paper elaborates on the digital control and monitoring portion of the PSBR console replacement, with emphasis on the key system objectives

Progress of nuclear safety for symbiosis and sustainability advanced digital instrumentation, control and information systems for nuclear power plants

CERN Document Server

Yoshikawa, Hidekazu

2014-01-01

This book introduces advanced methods of computational and information systems allowing readers to better understand the state-of-the-art design and implementation technology needed to maintain and enhance the safe operation of nuclear power plants. The subjects dealt with in the book are (i) Full digital instrumentation and control systems and human?machine interface technologies (ii) Risk? monitoring methods for large and? complex? plants (iii) Condition monitors for plant components (iv) Virtual and augmented reality for nuclear power plants and (v) Software reliability verification and val

Analysis and control of a shunt active power filter

Energy Technology Data Exchange (ETDEWEB)

Ottersten, R.; Petersson, Andreas [Chalmers Univ. of Technology, Goeteborg (Sweden). Dept. of Electric Power Engineering

1999-09-01

This report deals with active power filtering of low-frequency current harmonics. The active filter consists of a forced-commutated voltage source inverter with a digital control system. The aim of this master thesis is to investigate the performance of a shunt active power filter, and the parameters influence on the system performance. Three different harmonic identification methods are presented and compared. The shunt active power filter is very well suited for harmonic current reduction, provided that the phase shift due to the digital implementation of the control system is compensated. The performance of the active power filter depends on the switching frequency. When using individual harmonic detection methods the amount of compensation can be fully controlled for each current harmonic.

Digital control in LLRF system for CYCIAE-100 cyclotron

Energy Technology Data Exchange (ETDEWEB)

Yin, Zhiguo, E-mail: bitbearAT@hotmail.com; Fu, Xiaoliang; Ji, Bin; Zhang, Tianjue; Wang, Chuan

2016-05-21

As a driven accelerator, the CYCIAE-100 cyclotron is designed by China Institute of Atomic Energy for the Beijing Radio Ion-beam Facility project. The cyclotron RF system is designed to use two RF power sources of 100 kW to drive two half-wavelength cavities respectively. Two Dee accelerating electrodes are kept separately from each other inside the cyclotron, while their accelerating voltages are maintained in phase by the efforts of LLRF control. An analog–digital hybrid LLRF system has been developed to achieve cavity tuning control, dee voltage amplitude and phase stabilization etc. The analog subsystems designs are focused on RF signal up/down conversion, tuning control, and dee voltage regulation. The digital system provides an RF signal source, aligns the cavity phases and maintains a Finite State Machine. The digital parts combine with the analog functions to provide the LLRF control. A brief system hardware introduction will be given in this paper, followed by the review of several major characteristics of the digital control in the 100 MeV cyclotron LLRF system. The commissioning is also introduced, and most of the optimization during the process was done by changing the digital parts.

Digital simulation of power electronic systems

International Nuclear Information System (INIS)

Mehring, P.; Jentsch, W.; John, G.; Kraemer, D.

1981-01-01

The following paper contains the final report on the NETSIM-Project. The purpose of this project is to develop a special digital simulation system, which could serve as a base for routine application of simulation in planning and development of power electronic systems. The project is realized in two steps. First a basic network analysis system is established. With this system the basic models and methods in treating power electronic networks could be probed. The resulting system is then integrated into a general digital simulation system for continous systems (CSSL-System). This integrated simulation system allows for convenient modeling and simulation of power electronic systems. (orig.) [de

Market and Labour Control in Digital Capitalism

Directory of Open Access Journals (Sweden)

Philipp Staab

2016-11-01

Full Text Available Theorists of post capitalism have recently argued for a more or less inevitable end to capitalism. They assume that private accumulation is systematically blocked by the inability of capitalist corporations to create revenues by setting prices as they lose control over the reproduction of their commodities and that in this process, capitalist labour will eventually disappear. Drawing on a case study of Amazon and thoughts on the policies of other leading digital corporations, we challenge these assumptions. Key corporate players of digitization are trying to become powerful monopolies and have partly succeeded in doing so, using the network effects and scaling opportunities of digital goods and building socio-technical ecosystems. These strategies have led to the development of in part isomorphic structures, hence creating a situation of oligopolistic market competition. We draw on basic assumptions of monopoly capital theory to argue that in this situation labour process rationalization becomes key to the corporation’s competitive strategies. We see the expansion of digital control and the organizational structures applied by key corporate players of the digital economy as evidence for the expansion of capitalist labour, not its reduction.

Research on transfer rule of the monitoring of operator in digital main control room of nuclear power plant

International Nuclear Information System (INIS)

Zhang Li; Li Linfeng; Li Pengcheng; Lu Changshen; Huang Weigang; Dai Zhonghua; Huang Yuanzheng; Chen Qingqing

2013-01-01

In the digital main control room of nuclear power plants, monitoring the operating status of the system of reactor is not only one of the most important tasks of the operators, but also the basis and premise of controlling the system of reactor running correctly. After analyzing, inducing, summarizing the data obtained, we found the operators' monitor behavior could be classified as procedure transfer, abnormal transfer, and exchange transfer. The times of exchange transfer is 29% of the total transfer times, abnormal transfer is 14%, regulation transfer is 36%, and others are 21%. (authors)

PULSE MODULATION POWER AMPLIFIER WITH ENHANCED CASCADE CONTROL METHOD

DEFF Research Database (Denmark)

1998-01-01

a single local feedback path A (7) with a lowpass characteristic and local forward blocks B¿1? or B (3, 4). The leads to a much improved system with a very low sensitivity to errors in the switching power stage. In the second preferred embodiment of the invention the control structure is extended...... and feedback path A to determine stable self-oscillating conditions. An implemented 250W example MECC digital power amplifier has proven superior performance in terms of audio performance (0.005 % distortion, 115 dB dynamic range) and efficiency (92 %).......A digital switching power amplifier with Multivariable Enhanced Cascade Controlled (MECC) includes a modulator, a switching power stage and a low pass filter. In the first preferred embodiment an enhanced cascade control structure local to the switching power stage is added, characterised by having...

Digital control rod blocking monitor

International Nuclear Information System (INIS)

Funayama, Yoshio.

1996-01-01

The present invention system is used for monitoring of a power region of a reactor, and used for monitoring of simultaneous withdrawal of a plurality of control rods without increasing the size or complicating the system. Namely, the system processes signals from a neutron flux detectors at the periphery of control rods controlled for withdrawal. As a result of the processing, the digital monitoring system generates an alarm when the reactor power at the periphery of the control rods fluctuates exceeding an allowable range. In the system, a control rod information forming means prepares frame data comprising front data, positions of the control rods to be withdrawn, frame numbers and completion data. A serial data transmitting means transmits the frame data successively as repeating frame data rows. A control rod information receiving means takes up the frame data of each of control rods to be withdrawn from the transmitted frame data rows. Since the system of the present invention can monitor the withdrawal of a plurality of control rods simultaneously without increasing the size or complicating the system, cost can be saved and the maintenance can be improved. (I.S.)

Optimization of geometry of annular seat valves suitable for Digital Displacement fluid power pumps/motors

DEFF Research Database (Denmark)

Rømer, Daniel; Johansen, Per; Pedersen, Henrik C.

2013-01-01

Digital Displacement Fluid Power is an upcoming technology setting new standards for the achievable efficiency of fluid power pumps and motors. The core element of the Digital Displacement technology is high performance electronically controlled seat valves, which must exhibit very low flow...... work an annular seat valve suitable for use in Digital Displacement units is considered, and the ring geometry is optimized using finite element analysis including non-linear material behaviour, contact elements and fluid pressure penetrating load, closely reflecting the actual load of the seat valve...

Verification of failover effects from distributed control system communication networks in digitalized nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Min, Moon Gi; Lee, Jae Ki; Lee, Kwang Hyun; Lee, Dong Il; Lim, Hee Taek [Korea Hydro and Nuclear Power Co., Ltd, Daejeon (Korea, Republic of)

2017-08-15

Distributed Control System (DCS) communication networks, which use Fast Ethernet with redundant networks for the transmission of information, have been installed in digitalized nuclear power plants. Normally, failover tests are performed to verify the reliability of redundant networks during design and manufacturing phases; however, systematic integrity tests of DCS networks cannot be fully performed during these phases because all relevant equipment is not installed completely during these two phases. In additions, practical verification tests are insufficient, and there is a need to test the actual failover function of DCS redundant networks in the target environment. The purpose of this study is to verify that the failover functions works correctly in certain abnormal conditions during installation and commissioning phase and identify the influence of network failover on the entire DCS. To quantify the effects of network failover in the DCS, the packets (Protocol Data Units) must be collected and resource usage of the system has to be monitored and analyzed. This study introduces the use of a new methodology for verification of DCS network failover during the installation and commissioning phases. This study is expected to provide insight into verification methodology and the failover effects from DCS redundant networks. It also provides test results of network performance from DCS network failover in digitalized domestic nuclear power plants (NPPs)

High-performance digital triggering system for phase-controlled rectifiers

International Nuclear Information System (INIS)

Olsen, R.E.

1983-01-01

The larger power supplies used to power accelerator magnets are most commonly polyphase rectifiers using phase control. While this method is capable of handling impressive amounts of power, it suffers from one serious disadvantage, namely that of subharmonic ripple. Since the stability of the stored beam depends to a considerable extent on the regulation of the current in the bending magnets, subharmonic ripple, especially that of low frequency, can have a detrimental effect. At the NSLS, we have constructed a 12-pulse, phase control system using digital signal processing techniques that essentially eliminates subharmonic ripple

State-of-art report on digital I and C system reliability issues for nuclear power plants

International Nuclear Information System (INIS)

Hwang, In Koo; Lee, Dong Gyoung; Cha, Kyung Ho; Kwon, Kee Choon; Wood, Richard T.

2000-01-01

As the instrumentation and control (Iand C) equipment suppliers tend to provide digital components rather than conventional analog type components for instrument and control systems of nuclear power plants(NPPs), it is unavoidable to adopt digital equipment for safety I and C systems as well as non-safety systems. However, the full introduction of digital equipment to I and C systems of nuclear power plants raises several concerns which have not been considered for conventional analog I and C systems. The two major examples of the issues of digital systems are electromagnetic compatibility (EMC) and software reliability. KAERI invited a technical expert, Dr. Richard T. Wood, from Oak Ridge National Laboratory (ORNL) in Unites States and held seminars to recognize the state-of-art of the above issues and to share the information on techniques dealing with the problems. Dr. Wood has been working on the development of EMC guidelines and technical basis in using digital equipment for safety systems in nuclear power plants on the sponsorship of US Nuclear Regulatory Commission (NRC). Being based on his statements and discussions during his visit, this report describes technical considerations and issues on digital safety I and C system application in NPPs, EMC methods, environmental effects vulnerable to digital components, reliability assurance methods, etc. (author)

Design of High-Voltage Switch-Mode Power Amplifier Based on Digital-Controlled Hybrid Multilevel Converter

Directory of Open Access Journals (Sweden)

Yanbin Hou

2016-01-01

Full Text Available Compared with conventional Class-A, Class-B, and Class-AB amplifiers, Class-D amplifier, also known as switching amplifier, employs pulse width modulation (PWM technology and solid-state switching devices, capable of achieving much higher efficiency. However, PWM-based switching amplifier is usually designed for low-voltage application, offering a maximum output voltage of several hundred Volts. Therefore, a step-up transformer is indispensably adopted in PWM-based Class-D amplifier to produce high-voltage output. In this paper, a switching amplifier without step-up transformer is developed based on digital pulse step modulation (PSM and hybrid multilevel converter. Under the control of input signal, cascaded power converters with separate DC sources operate in PSM switch mode to directly generate high-voltage and high-power output. The relevant topological structure, operating principle, and design scheme are introduced. Finally, a prototype system is built, which can provide power up to 1400 Watts and peak voltage up to ±1700 Volts. And the performance, including efficiency, linearity, and distortion, is evaluated by experimental tests.

Power system stabilizers based on modern control techniques

Energy Technology Data Exchange (ETDEWEB)

Malik, O P; Chen, G P; Zhang, Y; El-Metwally, K [Calgary Univ., AB (Canada). Dept. of Electrical and Computer Engineering

1994-12-31

Developments in digital technology have made it feasible to develop and implement improved controllers based on sophisticated control techniques. Power system stabilizers based on adaptive control, fuzzy logic and artificial networks are being developed. Each of these control techniques possesses unique features and strengths. In this paper, the relative performance of power systems stabilizers based on adaptive control, fuzzy logic and neural network, both in simulation studies and real time tests on a physical model of a power system, is presented and compared to that of a fixed parameter conventional power system stabilizer. (author) 16 refs., 45 figs., 3 tabs.

Advanced digital instrumentation and control system for nuclear power plant protection

Energy Technology Data Exchange (ETDEWEB)

Sabino, D [VVER Engineering, Westinghouse Electric Corporation (United States)

1998-12-31

The Diverse Protection System is a back-up to the Primary Reactor Protection System developed for use at the Temelin nuclear power plant. The DPS is a digital system which provides a wealth of benefits from today`s advanced technology. These benefits include a compact hardware design with high performance microprocessors and a structured software design using a high level language. An overview of the DPS functions, hardware and software is provided. (author). 1 fig., 1 tab.

Digitally controlled oscillator design with a variable capacitance XOR gate

International Nuclear Information System (INIS)

Kumar, Manoj; Arya, Sandeep K.; Pandey, Sujata

2011-01-01

A digitally controlled oscillator (DCO) using a three-transistor XOR gate as the variable load has been presented. A delay cell using an inverter and a three-transistor XOR gate as the variable capacitance is also proposed. Three-, five- and seven-stage DCO circuits have been designed using the proposed delay cell. The output frequency is controlled digitally with bits applied to the delay cells. The three-bit DCO shows output frequency and power consumption variation in the range of 3.2486–4.0267 GHz and 0.6121–0.3901 mW, respectively, with a change in the control word 111–000. The five-bit DCO achieves frequency and power of 1.8553–2.3506 GHz and 1.0202–0.6501 mW, respectively, with a change in the control word 11111–00000. Moreover, the seven-bit DCO shows a frequency and power consumption variation of 1.3239–1.6817 GHz and 1.4282–0.9102 mW, respectively, with a varying control word 1111111–0000000. The power consumption and output frequency of the proposed circuits have been compared with earlier reported circuits and the present approaches show significant improvements. (semiconductor integrated circuits)

Safety and security analysis for distributed control system in nuclear power plants

International Nuclear Information System (INIS)

Lu Zhigang; Liu Baoxu

2011-01-01

The Digital Distributed Control System (DCS) is the core that manages all monitoring and operation tasks in a Nuclear Power Plant (NPP). So, Digital Distributed Control System in Nuclear Power Plant has strict requirements for control and automation device safety and security due to many factors. In this article, factors of safety are analyzed firstly, while placing top priority on reliability, quality of supply and stability have also been carefully considered. In particular, advanced digital and electronic technologies are adopted to maintain sufficient reliability and supervisory capabilities in nuclear power plants. Then, security of networking and information technology have been remarked, several design methodologies considering the security characteristics are suggested. Methods and technologies of this article are being used in testing and evaluation for a real implement of a nuclear power plant in China. (author)

Digital Resonant Controller based on Modified Tustin Discretization Method

Directory of Open Access Journals (Sweden)

STOJIC, D.

2016-11-01

Full Text Available Resonant controllers are used in power converter voltage and current control due to their simplicity and accuracy. However, digital implementation of resonant controllers introduces problems related to zero and pole mapping from the continuous to the discrete time domain. Namely, some discretization methods introduce significant errors in the digital controller resonant frequency, resulting in the loss of the asymptotic AC reference tracking, especially at high resonant frequencies. The delay compensation typical for resonant controllers can also be compromised. Based on the existing analysis, it can be concluded that the Tustin discretization with frequency prewarping represents a preferable choice from the point of view of the resonant frequency accuracy. However, this discretization method has a shortcoming in applications that require real-time frequency adaptation, since complex trigonometric evaluation is required for each frequency change. In order to overcome this problem, in this paper the modified Tustin discretization method is proposed based on the Taylor series approximation of the frequency prewarping function. By comparing the novel discretization method with commonly used two-integrator-based proportional-resonant (PR digital controllers, it is shown that the resulting digital controller resonant frequency and time delay compensation errors are significantly reduced for the novel controller.

Estimation of reliability on digital plant protection system in nuclear power plants using fault simulation with self-checking

International Nuclear Information System (INIS)

Lee, Jun Seok; Kim, Suk Joon; Seong, Poong Hyun

2004-01-01

Safety-critical digital systems in nuclear power plants require high design reliability. Reliable software design and accurate prediction methods for the system reliability are important problems. In the reliability analysis, the error detection coverage of the system is one of the crucial factors, however, it is difficult to evaluate the error detection coverage of digital instrumentation and control system in nuclear power plants due to complexity of the system. To evaluate the error detection coverage for high efficiency and low cost, the simulation based fault injections with self checking are needed for digital instrumentation and control system in nuclear power plants. The target system is local coincidence logic in digital plant protection system and a simplified software modeling for this target system is used in this work. C++ based hardware description of micro computer simulator system is used to evaluate the error detection coverage of the system. From the simulation result, it is possible to estimate the error detection coverage of digital plant protection system in nuclear power plants using simulation based fault injection method with self checking. (author)

Investigation on the use digital controls instead of PID analog controls in the level control of steam generators of nuclear power PWR; Investigacao sobre o uso de controladores digitais em substituicao aos controladores analogicos PID para o controle de nivel de geradores de vapor de centrais nucleares PWR

Energy Technology Data Exchange (ETDEWEB)

Alvarenga, Marco Antonio Bayout

2012-07-01

The aim of this study is to identify current alternatives for the implementation of digital controllers in the level control of steam generators of nuclear power PWR (Pressurized Water Reaetor). It is intended to identify the types of digital controls that are available from the theoretical and conceptual viewpoints for this purpose. We investigate the advantages and disadvantages of each controller model. From this assessment are pointed the most suitable models in hierarchical scale. This evaluation also serves to suggest possible types of control installation as a whole, where the level control of the steam generators becomes just one of many controls that are part of the plant. In this case, the use of digital controls allows the non-linear and multivariable treatment which is characteristic of complex systems, such as the nuclear power generation. The treatment of nonlinearities and multivariable aspects allows a more detailed study of the stability of these plants when they are subject to transients or several accidents, such as the case of losing external power of transients. In the specific case of steam generators, the instabilities result from the emergence of the shrink and swell phenomenas, depending on the load variations of thermonuclear plant. The application of several types and digital controllers, considering these inherent characteristics of the level control of steam generators, allows to infer which types of controllers are more appropriate to treat instabilities of this type and to make conjectures in its use for the cases of more complex instabilities, considering the integration of all nucleus-plant controls.

Digital control application for the advanced boiling water reactor

International Nuclear Information System (INIS)

Fennern, L.E.; Pearson, T.; Wills, H.D.; Swire Rhodes, L.; Pearson, R.L.

1986-01-01

The Advanced Boiling Water Reactor (ABWR) is a 1300 MWe class Nuclear Power Plant whose design studies and demonstration tests are being performed by the three manufacturers, General Electric, Toshiba and Hitachi, under requirement specifications from the Tokyo Electric Power Company. The goals are to apply new technology to the BWR in order to achieve enhanced operational efficiencies, improved safety measures and cost reductions. In the plant instrumentation and control areas, traditional analog control equipment and wire cables will be replaced by distributed digital microprocessor based control units communicating with each other and the control room over fiber optic multiplexed data buses

Application of digital process controller for automatic pulse operation in the NSRR

International Nuclear Information System (INIS)

Ishijima, K.; Ueda, T.; Saigo, M.

1992-01-01

The NSRR at JAERI is a modified TRIGA Reactor. It was built for investigating reactor fuel behavior under reactivity initiated accident (RIA) conditions. Recently, there has been a need to improve the flexibility of pulsing operations in the NSRR to cover a wide range of accidental situations, including RIA events at elevated power levels, and various abnormal power transients. To satisfy this need, we developed a new reactor control system which allows us to perform 'Shaped Pulse Operation: SP' and 'Combined Pulse Operation: CP'. Quick, accurate and complicated manipulation of control rods was required to realize these operations. Therefore we installed a new reactor control system, which we call an automatic pulse control system. This control system is composed of digital processing controllers and other digital equipments, and is fully automated and highly accurate. (author)

Real-Time Hardware-in-the-Loop Testing for Digital Controllers

DEFF Research Database (Denmark)

Cha, Seung-Tae; Kwon, Park In; Wu, Qiuwei

2012-01-01

of the power electronics hardware are not included in the RTDS. Instead, the control algorithms are coded using the native C code and downloaded to the dedicated digital signal processor (DSP)/microcontrollers. The two experimental applications illustrate the effectiveness of the HIL controller testing...

A Digital Power Quality Monitoring Equipment Designed for Digital Substation

Science.gov (United States)

Li, Wei; Wang, Xin; Geng, Jiewen

2018-01-01

Taking into account both current status and development trend of digital substation, this paper proposed a design of a new multi-channelled digital power quality monitoring equipment with high compatibility. The overall functional structure, hardware architecture, software architecture, interface architecture and some key techniques such as IEC 61850 modelling of transient event and harmonic measurement method under the condition of non-synchronous sampling are described in this paper.

A new on-chip all-digital three-phase full-bridge dc/ac power inverter with feedforward and frequency control techniques.

Science.gov (United States)

Chen, Jiann-Jong; Kung, Che-Min

2010-09-01

The communication speed between components is far from satisfactory. To achieve high speed, simple control system configuration, and low cost, a new on-chip all-digital three-phase dc/ac power inverter using feedforward and frequency control techniques is proposed. The controller of the proposed power inverter, called the shift register, consists of six-stage D-latch flip-flops with a goal of achieving low-power consumption and area efficiency. Variable frequency is achieved by controlling the clocks of the shift register. One advantage regarding the data signal (D) and the common clock (CK) is that, regardless of the phase difference between the two, all of the D-latch flip-flops are capable of delaying data by one CK period. To ensure stability, the frequency of CK must be six times higher than that of D. The operation frequency of the proposed power inverter ranges from 10 Hz to 2 MHz, and the maximum output loading current is 0.8 A. The prototype of the proposed circuit has been fabricated with TSMC 0.35 μm 2P4M CMOS processes. The total chip area is 2.333 x 1.698 mm2. The three-phase dc/ac power inverter is applicable in uninterrupted power supplies, cold cathode fluorescent lamps, and motors, because of its ability to convert the dc supply voltage into the three-phase ac power sources.

Digital protection in power plants. Electrical unit and line protection. Digital protection systems for NPP

International Nuclear Information System (INIS)

Kaczmarek, A.

2000-01-01

In this presentation author deals with the digital protection systems for nuclear power plants. The evolution of protection devices, protection concept for power plants, concept of functional redundancy, references for digital protection, benefits for the customer well as concept fault recorder are presented. (author)

Experience with the New Digital RF Control System at the CESR Storage Ring

CERN Document Server

Liepe, Matthias; Dobbins, John; Kaplan, Roger; Strohman, Charles R; Stuhl, Benjamin K

2005-01-01

A new digital control system has been developed, providing great flexibility, high computational power and low latency for a wide range of control and data acquisition applications. This system is now installed in the CESR storage ring and stabilizes the vector sum field of two of the superconducting CESR 500 MHz cavities and the output power from the driving klystron. The installed control system includes in-house developed digital and RF hardware, very fast feedback and feedforward control, a state machine for automatic start-up and trip recovery, cw and pulsed mode operation, fast quench detection, and cavity frequency control. Several months of continuous operation have proven high reliability of the system. The achieved field stability surpasses requirements.

Some aspects of digital I and C and digital human-system interface upgrades in nuclear power plants

International Nuclear Information System (INIS)

Mandic, D.

2005-01-01

Digital I and C technology introduces some new terms and new processes like software life cycle, process computer configuration control, digital human-system interface (HSI), software V and V (Verification and Validation), software common mode failure potential, software documentation, etc. Based on the experience from NEK, and other NPPs and published reports from other organizations, this paper sheds light on challenging tasks related to some aspects of the digital I and C upgrades and especially the NPP MCR/MCB HSI (Nuclear Power Plant Main Control Room / Main Control Board Human-System Interface) upgrade. The Ref. [1], EPRI Report TR-1008122 was used as a guidance to analyze original NEK MCR/MCB HSI design (1970s), to describe migration from the original MCR/MCB HSI design to the 2005 AS-BUILT status and to propose the authors vision for the key planning aspects for I and C upgrades and MCR modernization. This paper submits the justified proposal for the endpoint vision and the migration path applicable to NEK MCR/MCB HSI modernization, as well as some of the possible risks and lessons learned. (author)

Digital control card based on digital signal processor

International Nuclear Information System (INIS)

Hou Shigang; Yin Zhiguo; Xia Le

2008-01-01

A digital control card based on digital signal processor was developed. Two Freescale DSP-56303 processors were utilized to achieve 3 channels proportional- integral-differential regulations. The card offers high flexibility for 100 MeV cyclotron RF system development. It was used as feedback controller in low level radio frequency control prototype, with the feedback gain parameters continuously adjustable. By using high precision analog to digital converter with 500 kHz sampling rate, a regulation bandwidth of 20 kHz was achieved. (authors)

Graphical Evaluation of Time-Delay Compensation Techniques for Digitally Controlled Converters

DEFF Research Database (Denmark)

Lu, Minghui; Wang, Xiongfei; Loh, Poh Chiang

2018-01-01

A main design constraint of the digitally controlled power electronics converters is the time delay of control systems, which may lead to the reduced control loop bandwidth and even unstable dynamics. Numerous time-delay compensation methods have been developed, of which the model-free schemes...

Construction and application research of Three-dimensional digital power grid in Southwest China

Science.gov (United States)

Zhou, Yang; Zhou, Hong; You, Chuan; Jiang, Li; Xin, Weidong

2018-01-01

With the rapid development of Three-dimensional (3D) digital design technology in the field of power grid construction, the data foundation and technical means of 3D digital power grid construction approaches perfection. 3D digital power grid has gradually developed into an important part of power grid construction and management. In view of the complicated geological conditions in Southwest China and the difficulty in power grid construction and management, this paper is based on the data assets of Southwest power grid, and it aims at establishing a 3D digital power grid in Southwest China to provide effective support for power grid construction and operation management. This paper discusses the data architecture, technical architecture and system design and implementation process of the 3D digital power grid construction through teasing the key technology of 3D digital power grid. The application of power grid data assets management, transmission line corridor planning, geological hazards risk assessment, environmental impact assessment in 3D digital power grid are also discussed and analysed.

Digitizing instrumentation and control systems in nuclear power plants. DAtF autumn meeting Leittec '96, October 8, 1996 in Koenigswinter

International Nuclear Information System (INIS)

Aleite, W.

1997-01-01

Recently, digitization for upgrading and retrofitting of instrumentation and control systems has been extended to German nuclear power plants, and initial action to commence modification started with a very suitable system, the limiters of the Neckar-1 reactor unit of GKN. This action is generally welcomed. Systems of the control room of relevance to safety -even if not belonging to priority classes - are systems for process information for example, or operator guidance, as well as diagnostic systems for inspection and maintenance. (orig./DG) [de

47 CFR 74.785 - Low power TV digital data service pilot project.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 4 2010-10-01 2010-10-01 false Low power TV digital data service pilot project... Power TV, TV Translator, and TV Booster Stations § 74.785 Low power TV digital data service pilot project. Low power TV stations authorized pursuant to the LPTV Digital Data Services Act (Public Law 106...

Advanced digital instrumentation and control system for nuclear power plant protection

International Nuclear Information System (INIS)

Sabino, D.

1997-01-01

The Diverse Protection System (DPS) is described. The DPS is a state-of-the-art digital protection system developed as a back-up to the primary reactor protection system at the Temelin nuclear power plant, featuring a compact hardware design based on VMEbus technology. This technology allows for ease in adding or modifying the number and type of input modules and processors. The DPS software is written in a high level language suitable for safety critical applications. The software is both modular and configurable allowing for potential future modifications and software reuse

Closed-loop digital control of nuclear reactors characterized by spatial dynamics

International Nuclear Information System (INIS)

Bernard, J.A.; Henry, A.F.; Lanning, D.D.; Meyer, J.E.

1991-03-01

This report describes the theoretical development and the evaluation via both simulation and, to a lesser degree, experiment of a digital method for the closed-loop control of power and temperature in reactors characterized by spatial dynamics. The major conclusions of the research are that (1) the sophistication of advanced reactor physics and thermal-hydraulic nodal methods is now such that accurate, real-time models of spatially-dependent, heterogeneous reactor cores can be run on present-generation minicomputers; (2) operation of both present-day commercial reactors as well as the multi-modular reactors now being considered for construction in the United States could be significantly improved by incorporating model-generated information on in-core conditions in a digital controller; and (3) digital controllers for spatially-dependent reactors should have a hierarchical or multi-tiered structure consisting of supervisory algorithms that preclude challenges to the safety system, global control laws designed to provide an optimal response to temperature and power perturbations, and local control laws that maintain parameters such as the margin to departure from nucleate boiling within specification. The technology described is appropriate to present-day pressurized water reactors and to the proposed multi-modular designs. The end-product of this research was a (near) real-time analytic plant-estimation code that was given the acronym POPSICLE for POwer Plant SImulator and ControlLEr. POPSICLE's core neutronics model is based on a quasi-static transient solution of the analytic nodal diffusion equations. 126 refs., 159 figs., 17 tabs

Closed-loop digital control of nuclear reactors characterized by spatial dynamics

Energy Technology Data Exchange (ETDEWEB)

Bernard, J.A. (Massachusetts Inst. of Tech., Cambridge, MA (USA). Nuclear Reactor Lab.); Henry, A.F.; Lanning, D.D.; Meyer, J.E. (Massachusetts Inst. of Tech., Cambridge, MA (USA). Dept. of Nuclear Engineering)

1991-03-01

This report describes the theoretical development and the evaluation via both simulation and, to a lesser degree, experiment of a digital method for the closed-loop control of power and temperature in reactors characterized by spatial dynamics. The major conclusions of the research are that (1) the sophistication of advanced reactor physics and thermal-hydraulic nodal methods is now such that accurate, real-time models of spatially-dependent, heterogeneous reactor cores can be run on present-generation minicomputers; (2) operation of both present-day commercial reactors as well as the multi-modular reactors now being considered for construction in the United States could be significantly improved by incorporating model-generated information on in-core conditions in a digital controller; and (3) digital controllers for spatially-dependent reactors should have a hierarchical or multi-tiered structure consisting of supervisory algorithms that preclude challenges to the safety system, global control laws designed to provide an optimal response to temperature and power perturbations, and local control laws that maintain parameters such as the margin to departure from nucleate boiling within specification. The technology described is appropriate to present-day pressurized water reactors and to the proposed multi-modular designs. The end-product of this research was a (near) real-time analytic plant-estimation code that was given the acronym POPSICLE for POwer Plant SImulator and ControlLEr. POPSICLE's core neutronics model is based on a quasi-static transient solution of the analytic nodal diffusion equations. 126 refs., 159 figs., 17 tabs.

Integration of analog and digital instrumentation and control systems in hybrid control rooms

International Nuclear Information System (INIS)

2010-01-01

he IAEA's activities in the area of nuclear power plant operating performance and life cycle management are aimed at increasing Member State capabilities in utilizing good engineering and management practices as developed and transferred by the IAEA. In particular, the IAEA supports the improvement of nuclear power plant performance, plant life management, training, power uprating, operational license renewal, and the modernization of instrumentation and control (I and C) systems of plants. The issue of the integration of analog and digital I and C systems in hybrid control rooms was suggested by the IAEA Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI) at its meetings in 2003 and 2005. The subject was then approved by the IAEA and included in its work programmes for 2006-2009. The purpose of this report is to help nuclear utilities in planning control room and other human system interface (HSI) changes, making appropriate use of modern technologies. These technologies would aid in managing ageing and obsolescence, and facilitate improvements in plant performance and safety. This report covers a broad spectrum of potential changes to the control room ranging from the replacement of a few obsolete components with newer digital devices to a fully computerized control room. New digital technologies offer significant opportunities to improve access to and presentation of information to the user, e.g. operators, maintenance staff and management. However, this technology should be used prudently. In some cases, modernization is undertaken to resolve ageing and obsolescence or to meet regulatory requirements for license renewal. The integration of new technologies during main control room (MCR) modernizations should be performed cautiously and all affected aspects of plant maintenance, and operation should be carefully considered, paying particular attention to the human factors elements of these aspects. This report describes a

Digitally Controlled Point of Load Converter with Very Fast Transient Response

DEFF Research Database (Denmark)

Jakobsen, Lars Tønnes; Andersen, Michael Andreas E.

2007-01-01

voltage mode control and very fast transient response. The DiSOM modulator is combined with a digital PID compensator algorithm is implemented in a hybrid CPLD/FPGA and is used to control a synchronous Buck converter, which is used in typical Point of Load applications. The computational time is only......This paper presents a new Digital Self-Oscillating Modulator (DiSOM) that allows the duty cycle to be changed instantly. The DiSOM modulator is shown to have variable switching that is a function of the duty cycle. Compared to a more traditional digital PWM modulator based on a counter...... and comparator the DiSOM modulator allows the sampling frequency of the output voltage control loop to be higher than the switching frequency of the power converter, typically a DC/DC converter. The features of the DiSOM modulator makes it possible to design a digitally controlled DC/DC converter with linear...

A low-power and low-phase-noise LC digitally controlled oscillator featuring a novel capacitor bank

Energy Technology Data Exchange (ETDEWEB)

Tian Huanhuan; Li Zhiqiang; Chen Pufeng; Wu Rufei; Zhang Haiying, E-mail: thuan8@126.com [Institute of Microelectronics, Chinese Academy of Sciences, Beijing 100029 (China)

2010-12-15

A monolithic low-power and low-phase-noise digitally controlled oscillator (DCO) based on a symmetric spiral inductor with center-tap and novel capacitor bank was implemented in a 0.18 {mu}m CMOS process with six metal layers. A third new way to change capacitance is proposed and implemented in this work. Results show that the phase noise at 1 MHz offset frequency is below -122.5 dBc/Hz while drawing a current of only 4.8 mA from a 1.8 V supply. Also, the DCO can work at low supply voltage conditions with a 1.6 V power supply and 4.1 mA supply current for the DCO's core circuit, achieving a phase-noise of -21.5 dBc/Hz at offset of 1 MHz. It demonstrates that the supply pushing of DCO is less than 10 MHz/V. (semiconductor integrated circuits)

Harmonization of the licensing process for digital instrumentation and control systems in nuclear power plants. Report prepared within the framework of the Technical Working Group on Nuclear Power Plant Control and Instrumentation

International Nuclear Information System (INIS)

2002-12-01

This report was prepared in response to the recommendation of the Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG-NPPCI). This recommendation was based on the recognition of the present diversity in national practices in licensing digital Instrumentation and control (I and C). The goal of this report is to promote harmonization of I and C licensing requirements in the Member States. It applies to I and C modernization, retrofits, upgrades, replacement, new installation, and other aspects of digital I and C in both existing and new nuclear power plants. It should be pointed out that a single publication, like this report, can only take the first step towards initiating a process leading to licensing requirements, which are more harmonized. It is therefore hoped that that this report will get a broad readership among those who can influence requirements that are set on digital I and C. This report provides general and high level recommendations to assist senior officials at utilities, vendor organizations, regulatory bodies, and their support organizations who are involved in the licensing of digital I and C. It is also intended to be read by persons participating in technical committees which are writing standards. The authors of this report believe that harmonization can be achieved through a consideration of the technical and scientific basis of high integrity digital I and C systems. It is also believed that many benefits can be reached in resolving various issues of a technical and engineering nature, which presently are creating controversies in the licensing of digital I and C in NPP safety applications. This publication is based on a consideration of the licensing process of I and C in a top down fashion to discuss generic principles to be applied when assessing digital I and C in NPP safety applications. This report gives an overview of the confidence building process in which evidence is created that digital I and C fulfils

Centralized digital control of accelerators

International Nuclear Information System (INIS)

Melen, R.E.

1983-09-01

In contrasting the title of this paper with a second paper to be presented at this conference entitled Distributed Digital Control of Accelerators, a potential reader might be led to believe that this paper will focus on systems whose computing intelligence is centered in one or more computers in a centralized location. Instead, this paper will describe the architectural evolution of SLAC's computer based accelerator control systems with respect to the distribution of their intelligence. However, the use of the word centralized in the title is appropriate because these systems are based on the use of centralized large and computationally powerful processors that are typically supported by networks of smaller distributed processors

Digitalizing upgrade of the power supplies for the extraction septum magnets in HIRFL-CSR

International Nuclear Information System (INIS)

Zhao Jiang; Zhang Huajian; Wu Fengjun; Yuan Zhendong; Chen Youxin; Huang Yuzhen; Gao Daqing

2014-01-01

This paper introduces the working principle of the power supplies for the septum magnets in HIRFL-CSR and presents a feasible scheme of digitalizing these power supplies. The scheme employed the SOPC (system-on-a-programmable-chip) technology based on FPGA, the software framework of NIOSII and the polycyclic adjustment algorithm realized by the hardware description language. Then, several key problems that could be encountered in realizing the power supply control algorithm on FPGA were discussed. After the power supplies were upgraded, the beam of HIRFL-CSR was extracted more reliably and the stability of beam spot position at the experimental terminals has been obviously improved. This work would provide a valuable reference for the engineers of digitalizing other magnetic power supplies in HIRFL-CSR and of developing magnetic power supplies for heavy ion cancer therapy. (authors)

A COMPREHENSIVE MODEL FOR THE POWER TRANSFORMER DIGITAL DIFFERENTIAL PROTECTION FUNCTIONING RESEARCH

Directory of Open Access Journals (Sweden)

Yu. V. Rumiantsev

2016-01-01

Full Text Available This article presents a comprehensive model for the two-winding power transformer digital differential protection functioning research. Considered comprehensive model is developed in MatLab-Simulink dynamic simulation environment with the help of SimPowerSystems component library and includes the following elements: power supply, three-phase power transformer, wye-connected current transformers and two-winding power transformer digital differential protection model. Each element of the presented model is described in the degree sufficient for its implementation in the dynamic simulation environment. Particular attention is paid to the digital signal processing principles and to the ways of differential and restraining currents forming of the considered comprehensive model main element – power transformer digital differential protection. With the help of this model the power transformer digital differential protection functioning was researched during internal and external faults: internal short-circuit, external short-circuit with and without current transformers saturation on the power transformer low-voltage side. Each experiment is illustrated with differential and restraining currents waveforms of the digital differential protection under research. Particular attention was paid to the digital protection functioning analysis during power transformer abnormal modes: overexcitation and inrush current condition. Typical current waveforms during these modes were showed and their harmonic content was investigated. The causes of these modes were analyzed in details. Digital differential protection blocking algorithms based on the harmonic content were considered. Drawbacks of theses algorithms were observed and the need of their further technical improvement was marked.

PowerPoint Use and Misuse in Digital Innovation

DEFF Research Database (Denmark)

Ciriello, Raffaele; Richter, Alexander; Schwabe, Gerhard

2015-01-01

insights into PowerPoint use and misuse through an ethnographically informed field study of employee-driven innovation inside a multinational European banking software provider. Drawing on primary data consisting of 62 interviews, 41 slide decks, and longitudinal series of observations and workshops......PowerPoint continues to permeate the presentation genre in general and business communication in particular. Whereas PowerPoint’s role in organizational practices has caught increasing research interest, research on PowerPoint in digital innovation is still scarce. This study provides comprehensive......, the paper illustrates how deeply entangled PowerPoint is in digital innovation. Our in-depth analysis of PowerPoint use at different innovation process stages suggests that the tool cannot be simply regarded as beneficial or detrimental for innovation. Instead, we provide a revised dialectical examination...

Introduction of digital control

International Nuclear Information System (INIS)

Kim, Sang Jin

1988-01-01

This book is one of mechatronics series. It deals with digital control, which includes what is digital control?, display way of control system, output of primary system, secondary system like example of system and display way of the system, stabilizing of control system such as method to decide stability and system out of control, displaying equation of state into vector, good control such as the right characteristic, transient behavior and design of position control system using DC servo motor.

Effects of digital human-machine interface characteristics on human error in nuclear power plants

International Nuclear Information System (INIS)

Li Pengcheng; Zhang Li; Dai Licao; Huang Weigang

2011-01-01

In order to identify the effects of digital human-machine interface characteristics on human error in nuclear power plants, the new characteristics of digital human-machine interface are identified by comparing with the traditional analog control systems in the aspects of the information display, user interface interaction and management, control systems, alarm systems and procedures system, and the negative effects of digital human-machine interface characteristics on human error are identified by field research and interviewing with operators such as increased cognitive load and workload, mode confusion, loss of situation awareness. As to the adverse effects related above, the corresponding prevention and control measures of human errors are provided to support the prevention and minimization of human errors and the optimization of human-machine interface design. (authors)

Digital control of research reactors

International Nuclear Information System (INIS)

Crump, J.C. III.; Richards, W.J.; Heidel, C.C.

1991-01-01

Research reactors provide an important service for the nuclear industry. Developments and innovations used for research reactors can be later applied to larger power reactors. Their relatively inexpensive cost allows research reactors to be an excellent testing ground for the reactors of tomorrow. One area of current interest is digital control of research reactor systems. Digital control systems offer the benefits of implementation and superior system response over their analog counterparts. At McClellan Air Force Base in Sacramento, California, the Stationary Neutron Radiography System (SNRS) uses a 1,000-kW TRIGA reactor for neutron radiography and other nuclear research missions. The neutron radiography beams generated by the reactor are used to detect corrosion in aircraft structures. While the use of the reactor to inspect intact F-111 wings is in itself noteworthy, there is another area in which the facility has applied new technology: the instrumentation and control system (ICS). The ICS developed by General Atomics (GA) contains several new and significant items: (a) the ability to servocontrol on three rods, (b) the ability to produce a square wave, and (c) the use of a software configurator to tune parameters affected by the actual reactor core dynamics. These items will probably be present in most, if not all, future research reactors. They were developed with increased control and overall usefulness of the reactor in mind

MAPLE-X10 reactor digital control system

International Nuclear Information System (INIS)

Deverno, M.T.; Hinds, H.W.

1991-10-01

The MAPLE-X10 reactor, currently under construction at the Chalk River Laboratories of Atomic Energy of Canada Limited, is a 10 MW t , pool-type, light-water reactor. It will be used for radioisotope production and silicon neutron transmutation doping. The reactor is controlled by a Digital Control System (DCS) and protected against abnormal process events by two independent safety systems. The DCS is an integrated control system used to regulate the reactor power and process systems. The safety philosophy for the control system is to minimize unsafe events arising from system failures and operational errors. this is achieved through redundancy, fail-safe design, automatic fault detection, and the selection of highly reliable components. The DCS provides both computer-controlled reactor regulation from the shutdown state to full power and automated reactor shutdown if safe limits are exceeded or critical sensors malfunction. The use of commercially available hardware with enhanced quality assurance makes the system cost effective while providing a high degree of reliability

Development of NPTC-11 intelligence control instrument with digital display

International Nuclear Information System (INIS)

Wang Chengming; Pu Li; Yu Jiang; Xue Yuping; Zhang Bo; Chen Yong

2007-01-01

The accurate of the process control gauge has direct influence on the safe operation of nuclear power plants. Therefore it is necessary to accumulate experiences for the domestic development of this Instrument. In this paper, NPTC-11 intelligence control Instrument with digital display is developed based on the design code for nuclear Instrument, considering the actual application requirements and technical redundancy. Its application in nuclear power plant for almost one year indicates that this Instrument satisfies the development purpose and requirements. (authors)

Portable Power And Digital-Communication Units

Science.gov (United States)

Levin, Richard R.; Henry, Paul K.; Rosenberg, Leigh S.

1992-01-01

Conceptual network of electronic-equipment modules provides electrical power and digital radio communications at multiple sites not served by cables. System includes central communication unit and portable units powered by solar photovoltaic arrays. Useful to serve equipment that must be set up quickly at remote sites or buildings that cannot be modified to provide cable connections.

Precision digital control systems

Science.gov (United States)

Vyskub, V. G.; Rozov, B. S.; Savelev, V. I.

This book is concerned with the characteristics of digital control systems of great accuracy. A classification of such systems is considered along with aspects of stabilization, programmable control applications, digital tracking systems and servomechanisms, and precision systems for the control of a scanning laser beam. Other topics explored are related to systems of proportional control, linear devices and methods for increasing precision, approaches for further decreasing the response time in the case of high-speed operation, possibilities for the implementation of a logical control law, and methods for the study of precision digital control systems. A description is presented of precision automatic control systems which make use of electronic computers, taking into account the existing possibilities for an employment of computers in automatic control systems, approaches and studies required for including a computer in such control systems, and an analysis of the structure of automatic control systems with computers. Attention is also given to functional blocks in the considered systems.

Design an optimal controller for nuclear reactor using a digital computer

International Nuclear Information System (INIS)

Saleh, F.M.A.

1986-01-01

An attempt is carried out to design an optimal controller, for a model nuclear reactor at one hand, and a model nuclear power plant at another hand using a digital computer. The design philosophy adopted was to specify the system dynamics in terms of a desired system transfer function, and realizing the design synthesis through state-variable feedback technique, thus ensuring both stability and optimization in the state space sense. The control design was also tested by carrying out digital simulation transient response runs (step, ramp, impulse, etc.) and agreement between the predicted desirable response and actual response of the overall design was achieved. Furthermore the performance of the controller is verified against a reference non-linear model for purposes of assessing the accuracy of the linearized approximation model. The results show that state-variable feedback policy can rank as an effective optimal technique for designing control algorithm for an on-line computer of a nuclear power plant. 41 figs. 43 refs

Event-driven control of a speed varying digital displacement machine

DEFF Research Database (Denmark)

Pedersen, Niels Henrik; Johansen, Per; Andersen, Torben O.

2017-01-01

. The controller synthesis is carried out as a discrete optimal deterministic problem with full state feedback. Based on a linear analysis of the feedback control system, stability is proven in a pre-specified operation region. Simulation of a non-linear evaluation model with the controller implemented shows great...... be treated as a Discrete Linear Time Invariant control problem with synchronous sampling rate. To make synchronous linear control theory applicable for a variable speed digital displacement machine, a method based on event-driven control is presented. Using this method, the time domain differential equations...... are converted into the spatial (position) domain to obtain a constant sampling rate and thus allowing for use of classical control theory. The method is applied to a down scaled digital fluid power motor, where the motor speed is controlled at varying references under varying pressure and load torque conditions...

A digital simulation of a pressurizer in a PWR nuclear power plant

International Nuclear Information System (INIS)

Sato, E.F.

1980-11-01

A model for pressurizer digital simulation of a PWR nuclear power plant during transients, considering all pressurizer control features, is presented. The pressurizer is divided into two regions separated by a water-vapor interface and non-equilibrium conditions are considered. The particular thermodynamic process followed during insurge and outsurges is determined at each instant of analysis without any previous assumption. The pressure behavior is defined by an explicit equation in any of four possible pressurizer thermodynamic conditions. Thermodynamic properties of steam and water are computed by ASME subroutines and the mathematical formulation presented in this study was programed in FORTRAN IV for a Burroughs-6700 digital computer system. This program was employed to simulate the Shippingport Atomic Power Station and Almirante Alvaro Alberto Nuclear Power Plant - Unit 1 pressurizers. The test results compared with experimental or vendor data show the validity of this analysis method. (Author) [pt

THE DEVELOPMENT OF DETAILED HUMAN FACTORS ENGINEERING GUIDELINES FOR DIGITAL CONTROL ROOM UPGRADES

International Nuclear Information System (INIS)

BROWN, W.; O'HARA, J.M.

2004-01-01

As part of the Department of Energy and Electric Power Research Institute's hybrid control room project, detailed human factors engineering guidance was developed for designing human-system interfaces that may be affected by introduction of additional digital technology during modernization of nuclear power plants. The guidance addresses several aspects of human-system interaction: information display, interface management, soft controls, alarms, computer-based procedures, computerized operator support systems, communications, and workstation/workplace design. In this paper, the ways in which digital upgrades might affect users' interaction with systems in each of these contexts are briefly described, and the contents of the guidance developed for each of the topics is also described

Digital I and C and Cyber Security for Nuclear Power Plants

International Nuclear Information System (INIS)

An, Yong Kyu; Chen, Daniel; Kalbarczyk, Zbigniew; Sollima, Calogero; Uddin, Rizwan

2014-01-01

Efforts are underway to switch existing nuclear power plants (NPPs) based on analog to digital control systems, while digital I and C systems are expected to be used in all new NPPs. Digital I and C is expected to solve obsolescence problem of analog components, and improve safety and performance. However, before analog systems can be switched to digital, much work needs to be done to ensure nuclear-grade safety and reliability of these completely new or hybrid systems. The goals of this research project are to identify possible faults and to evaluate resiliency of safety-critical digital I and C systems destined to be used in NPPs. A test bed is being developed for this purpose. This test bed consists of a model of a reactor, a digital controller, and associated communication links. The digital controller has a Triple-Modular Redundant (TMR) architecture to ensure continuous availability of the controller. A simple real time NPP simulator has been developed in LabVIEW using the point kinetics equation for the core, and models for a pressurizer, and a pump. The model for the primary loop is fairly complete, while that for the secondary loop is still in progress. The NPP simulator and the TMR controller, with its associated application program, have been assembled, and communications between them are established. The test bed also includes a set of specialized fault/error injectors to inject different types of faults/errors including both transients and permanents. A fault injection module is developed in LabVIEW in order to simulate hardware failures. The module contains a fault list manager (FLM), a fault injection manager (FIM), and a result analyzer. FLM picks a fault type and fault location at random from the pre-generated list of fault locations and types, and communicates this information to FIM, which injects faults into the system. The paper describes the details of the test bed, the associated fault injection system, and the results of the fault injection

Digital I and C and Cyber Security for Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

An, Yong Kyu; Chen, Daniel; Kalbarczyk, Zbigniew; Sollima, Calogero; Uddin, Rizwan [University of Illinois at Urbana-Champaign, Urbana (United States)

2014-08-15

Efforts are underway to switch existing nuclear power plants (NPPs) based on analog to digital control systems, while digital I and C systems are expected to be used in all new NPPs. Digital I and C is expected to solve obsolescence problem of analog components, and improve safety and performance. However, before analog systems can be switched to digital, much work needs to be done to ensure nuclear-grade safety and reliability of these completely new or hybrid systems. The goals of this research project are to identify possible faults and to evaluate resiliency of safety-critical digital I and C systems destined to be used in NPPs. A test bed is being developed for this purpose. This test bed consists of a model of a reactor, a digital controller, and associated communication links. The digital controller has a Triple-Modular Redundant (TMR) architecture to ensure continuous availability of the controller. A simple real time NPP simulator has been developed in LabVIEW using the point kinetics equation for the core, and models for a pressurizer, and a pump. The model for the primary loop is fairly complete, while that for the secondary loop is still in progress. The NPP simulator and the TMR controller, with its associated application program, have been assembled, and communications between them are established. The test bed also includes a set of specialized fault/error injectors to inject different types of faults/errors including both transients and permanents. A fault injection module is developed in LabVIEW in order to simulate hardware failures. The module contains a fault list manager (FLM), a fault injection manager (FIM), and a result analyzer. FLM picks a fault type and fault location at random from the pre-generated list of fault locations and types, and communicates this information to FIM, which injects faults into the system. The paper describes the details of the test bed, the associated fault injection system, and the results of the fault injection

Replacement of the complete control system of the NPP Oskarshamn 1 by digital distributed control system

International Nuclear Information System (INIS)

Berger, E.

1998-01-01

As part of an ongoing modernization program, Oskarshamn 1's I and C system and control room will be upgraded by ABB using its Advant Power range of digital, programmable process control system. Besides ensuring the higher level of safety that is demanded today, the new equipment provides the plant with an integrated system which will improve operator overview of operation and reduce risk of human error and serve as a platform for further improvements of the control room. This paper discusses in the example of Oskarshamn 1 how the complete control system of a nuclear power plant may be exchanged, the technical solution and the time schedule. Oskarshamn 1 is the first nuclear power plant in Sweden. It is a boiling water reactor built by ABB ATOM in Sweden between 1966 and 1971. According to this age the control system is semiconductor based and the reactor protection system is relays based. This makes the maintenance expensive and extensions nearly impossible. To extend the life period of this plant the owner has decided to improve the safety system and to replace the reactor protection system and safety related control and the non safety related control by a state of the art digital distributed control system of ABB. In March 1997 ABB got the order to replace the reactor protection system, the safety control system, to start the replacement of all control systems and to replace the old control room by a new ergonomically designed control room. Together with the exchange of the control system an enhancement of the safety system and of the emergency power supply will be implemented

Nanoelectromechanical Switches for Low-Power Digital Computing

Directory of Open Access Journals (Sweden)

Alexis Peschot

2015-08-01

Full Text Available The need for more energy-efficient solid-state switches beyond complementary metal-oxide-semiconductor (CMOS transistors has become a major concern as the power consumption of electronic integrated circuits (ICs steadily increases with technology scaling. Nano-Electro-Mechanical (NEM relays control current flow by nanometer-scale motion to make or break physical contact between electrodes, and offer advantages over transistors for low-power digital logic applications: virtually zero leakage current for negligible static power consumption; the ability to operate with very small voltage signals for low dynamic power consumption; and robustness against harsh environments such as extreme temperatures. Therefore, NEM logic switches (relays have been investigated by several research groups during the past decade. Circuit simulations calibrated to experimental data indicate that scaled relay technology can overcome the energy-efficiency limit of CMOS technology. This paper reviews recent progress toward this goal, providing an overview of the different relay designs and experimental results achieved by various research groups, as well as of relay-based IC design principles. Remaining challenges for realizing the promise of nano-mechanical computing, and ongoing efforts to address these, are discussed.

Digital lock-in techniques for adaptive power-line interference extraction.

Science.gov (United States)

Dobrev, Dobromir; Neycheva, Tatyana; Mudrov, Nikolay

2008-07-01

This paper presents a simple digital approach for adaptive power-line (PL) or other periodic interference extraction. By means of two digital square (or sine) wave mixers, the real and imaginary parts of the interference are found, and the interference waveform is synthesized and finally subtracted. The described technique can be implemented in an open-loop architecture where the interference is synthesized as a complex sinusoid or in a closed-loop architecture for automatic phase and gain control. The same approach can be used for removal of the fundamental frequency of the PL interference as well as its higher harmonics. It is suitable for real-time operation with popular low-cost microcontrollers.

ICC Experiment Performance Improvement through Advanced Feedback Controllers for High-Power Low-Cost Switching Power Amplifiers

International Nuclear Information System (INIS)

Nelson, Brian A.

2006-01-01

Limited resources force most smaller fusion energy research experiments to have little or no feedback control of their operational parameters, preventing achievement of their full operational potential. Recent breakthroughs in high-power switching technologies have greatly reduced feedback-controlled power supply costs, primarily those classified as switching power amplifiers. However, inexpensive and flexible controllers for these power supplies have not been developed. A uClinux-based micro-controller (Analog Devices Blackfin BF537) was identified as having the capabilities to form the base of a digital control system for switching power amplifiers. A control algorithm was created, and a Linux character device driver was written to realize the algorithm. The software and algorithm were successfully tested on a switching power amplifier and magnetic field coil using University of Washington (subcontractor) resources

Low Power Systolic Array Based Digital Filter for DSP Applications

Directory of Open Access Journals (Sweden)

S. Karthick

2015-01-01

Full Text Available Main concepts in DSP include filtering, averaging, modulating, and correlating the signals in digital form to estimate characteristic parameter of a signal into a desirable form. This paper presents a brief concept of low power datapath impact for Digital Signal Processing (DSP based biomedical application. Systolic array based digital filter used in signal processing of electrocardiogram analysis is presented with datapath architectural innovations in low power consumption perspective. Implementation was done with ASIC design methodology using TSMC 65 nm technological library node. The proposed systolic array filter has reduced leakage power up to 8.5% than the existing filter architectures.

Digital nuclear instrumentation application to nuclear power plant

International Nuclear Information System (INIS)

Burel, J.-P.; Fanet, H.

1993-01-01

The use of digital techniques for the control of nuclear reactors offers an interesting prospect in the improvement of the operation and safety of reactors. Thanks to close collaboration between Merlin Gerin and the French Atomic Energy Commission, a new piece of technology for nuclear instrumentation systems has been developed in order to meet the needs of different types of reactors. The principles of measurement are presented and the technology used is described. Other interesting points of this technology in addition to installation, operation and safety are examined. The digital neutron measurements are already operating in research reactors in France and will be installed in a different configuration in the new 1400 MW nuclear power plant. Integration into different designs is easily attainable by adapting the information transmission mode according to the technology present in the protection system and the treatment and visualization systems. (author)

Research on digital system design of nuclear power valve

Science.gov (United States)

Zhang, Xiaolong; Li, Yuan; Wang, Tao; Dai, Ye

2018-04-01

With the progress of China's nuclear power industry, nuclear power plant valve products is in a period of rapid development, high performance, low cost, short cycle of design requirements for nuclear power valve is proposed, so there is an urgent need for advanced digital design method and integrated design platform to provide technical support. Especially in the background of the nuclear power plant leakage in Japan, it is more practical to improve the design capability and product performance of the nuclear power valve. The finite element numerical analysis is a common and effective method for the development of nuclear power valves. Nuclear power valve has high safety, complexity of valve chamber and nonlinearity of seal joint surface. Therefore, it is urgent to establish accurate prediction models for earthquake prediction and seal failure to meet engineering accuracy and calculation conditions. In this paper, a general method of finite element modeling for nuclear power valve assembly and key components is presented, aiming at revealing the characteristics and rules of finite element modeling of nuclear power valves, and putting forward aprecision control strategy for finite element models for nuclear power valve characteristics analysis.

Digital Portfolios: Powerful Marketing Tool for Communications Students

Science.gov (United States)

Nikirk, Martin

2008-01-01

A digital portfolio is a powerful marketing tool for young people searching for employment in the communication or interactive media fields. With a digital portfolio, students can demonstrate their skills at working with software tools, demonstrate appropriate use of materials, explain technical procedures, show an understanding of processes and…

Reliability Estimation for Digital Instrument/Control System

Energy Technology Data Exchange (ETDEWEB)

Yang, Yaguang; Sydnor, Russell [U.S. Nuclear Regulatory Commission, Washington, D.C. (United States)

2011-08-15

Digital instrumentation and controls (DI and C) systems are widely adopted in various industries because of their flexibility and ability to implement various functions that can be used to automatically monitor, analyze, and control complicated systems. It is anticipated that the DI and C will replace the traditional analog instrumentation and controls (AI and C) systems in all future nuclear reactor designs. There is an increasing interest for reliability and risk analyses for safety critical DI and C systems in regulatory organizations, such as The United States Nuclear Regulatory Commission. Developing reliability models and reliability estimation methods for digital reactor control and protection systems will involve every part of the DI and C system, such as sensors, signal conditioning and processing components, transmission lines and digital communication systems, D/A and A/D converters, computer system, signal processing software, control and protection software, power supply system, and actuators. Some of these components are hardware, such as sensors and actuators, their failure mechanisms are well understood, and the traditional reliability model and estimation methods can be directly applied. But many of these components are firmware which has software embedded in the hardware, and software needs special consideration because its failure mechanism is unique, and the reliability estimation method for a software system will be different from the ones used for hardware systems. In this paper, we will propose a reliability estimation method for the entire DI and C system reliability using a recently developed software reliability estimation method and a traditional hardware reliability estimation method.

Reliability Estimation for Digital Instrument/Control System

International Nuclear Information System (INIS)

Yang, Yaguang; Sydnor, Russell

2011-01-01

Digital instrumentation and controls (DI and C) systems are widely adopted in various industries because of their flexibility and ability to implement various functions that can be used to automatically monitor, analyze, and control complicated systems. It is anticipated that the DI and C will replace the traditional analog instrumentation and controls (AI and C) systems in all future nuclear reactor designs. There is an increasing interest for reliability and risk analyses for safety critical DI and C systems in regulatory organizations, such as The United States Nuclear Regulatory Commission. Developing reliability models and reliability estimation methods for digital reactor control and protection systems will involve every part of the DI and C system, such as sensors, signal conditioning and processing components, transmission lines and digital communication systems, D/A and A/D converters, computer system, signal processing software, control and protection software, power supply system, and actuators. Some of these components are hardware, such as sensors and actuators, their failure mechanisms are well understood, and the traditional reliability model and estimation methods can be directly applied. But many of these components are firmware which has software embedded in the hardware, and software needs special consideration because its failure mechanism is unique, and the reliability estimation method for a software system will be different from the ones used for hardware systems. In this paper, we will propose a reliability estimation method for the entire DI and C system reliability using a recently developed software reliability estimation method and a traditional hardware reliability estimation method

Control strategy research of two stage topology for pulsed power supply

International Nuclear Information System (INIS)

Shi Chunfeng; Wang Rongkun; Huang Yuzhen; Chen Youxin; Yan Hongbin; Gao Daqing

2013-01-01

A kind of pulsed power supply of HIRFL-CSR was introduced, the ripple and the current error of the topological structure of the power in the operation process were analyzed, and two stage topology of pulsed power supply was given. The control strategy was simulated and the experiment was done in digital power platform. The results show that the main circuit structure and control method are feasible. (authors)

Attitude Control of a Satellite by using Digital Signal Processing

Directory of Open Access Journals (Sweden)

Adirelle C. Santana

2012-03-01

Full Text Available This article has discussed the development of a three-axis attitude digital controller for an artificial satellite using a digital signal processor. The main motivation of this study is the attitude control system of the satellite Multi-Mission Platform, developed by the Brazilian National Institute for Space Research for application in different sort of missions. The controller design was based on the theory of the Linear Quadratic Gaussian Regulator, synthesized from the linearized model of the motion of the satellite, i.e., the kinematics and dynamics of attitude. The attitude actuators considered in this study are pairs of cold gas jets powered by a pulse width/pulse frequency modulator. In the first stage of the project development, a system controller for continuous time was studied with the aim of testing the adequacy of the adopted control. The next steps had included an analysis of discretization techniques, the setting time of sampling rate, and the testing of the digital version of the Linear Quadratic Gaussian Regulator controller in the MATLAB/SIMULINK. To fulfill the study, the controller was implemented in a digital signal processor, specifically the Blackfin BF537 from Analog Devices, along with the pulse width/pulse frequency modulator. The validation tests used a scheme of co-simulation, where the model of the satellite was simulated in MATLAB/SIMULINK, while the controller and modulator were processed in the digital signal processor with a tool called Processor-In-the-Loop, which acted as a data communication link between both environments.function and required time to achieve a given mission accuracy are determined, and results are provided as illustration.

Research on real-time simulation test for upgrades of digital I and C system in nuclear power plant

International Nuclear Information System (INIS)

Shi Ji; Jiang Mingyu; Ma Yunqin

2005-01-01

The developing trend that digital instrument and control (I and C) system will supplant traditional analog I and C system in nuclear power plant is emphasized. This paper introduces mathematical model of steam generator of full scope simulator for nuclear power plant. The independent real-time simulation system, which forms the interactive closed loop together with the steam generator control system, can be applied to provide a simulation target for upgrades of instrument and control system and the research of control schemes. At the same time, a simulation method for this purpose is presented in this paper. In this method all of the hardware and software are composed of real distributed control system except the model of controlled object. This will not only create favorable conditions for commissioning on site in the future, but also give a theoretical analysis for upgrades of digital I and C system in nuclear power plant. (authors)

Replacement of the complete control system of the NPP Oskarshamn 1 by digital distributed control system

International Nuclear Information System (INIS)

Berger, E.

1998-01-01

As part of an ongoing modernization program, the I and C system and the control room of Oskarshamn 1 will be upgraded by ABB using its 'Advant Power' range of digital, programmable process control system. Besides ensuring the higher level of safety that is demanded today, the new equipment provides the plant with an integrated system which will improve operator interaction with the plant and reduce the risk of human error. The newly installed DCS system will serve also as a platform for further improvements of the control room. This paper discusses Oskarshamn 1 exchange of the complete control system of a nuclear power plant, the technical solution and the time schedule. Oskarshamn 1 is the first nuclear power plant in Sweden. It is a boiling water reactor built between 1966 and 1971 by ABB ATOM in Sweden. According to the plant age the control system is relay-based, while instrumentation and analogue control is semiconductor-based. This makes maintenance expensive and even worse, makes extensions nearly impossible. According to the safety standards of the 1960s, there is no separation between safety and non safety control and no seismic qualification. To extend the life of this plant the owner has decided to improve the safety system as well as to replace the reactor protection system, the safety related control and the non safety related control by a state-of-the-art digital distributed control system from ABB. In March 1997, ABB got the order to replace the reactor protection system, the safety control system and to start the replacement of all control systems. The old control room has to be replaced by a new ergonomically design. Together with the exchange of the control system the safety features of the plant and the emergency power supply has to be extended. (author)

Reactor instrumentation and control in nuclear power plants in Germany

International Nuclear Information System (INIS)

Aleite, W.

1993-01-01

The pertinent legislation, guidelines and standards of importance for nuclear power plant construction as well as the relevant committees in Germany are covered. The impact of international developments on the German regulatory scene is mentioned. A series of 15 data sheets on reactor control, followed by 5 data sheets on instrumentation and control in nuclear power plants, which were drawn up for German plants, are compared and commented in some detail. Digitalization of instrumentation and control systems continues apace. To illustrate the results that can be achieved with a digitalized information system, a picture series that documents a plant test of behavior on simulated steam generator tube rupture is elaborately commented. An outlook on backfitting and upgrading applications concludes this paper. (orig.) [de

Photovoltaic System Equipped with Digital Command Control and Acquisition

Directory of Open Access Journals (Sweden)

Khalil Kassmi

2013-07-01

Full Text Available In this paper, we present results concerning the design, the realization and the characterization of a photovoltaic system (PV, equipped with a digital controls: Power Point Tracking (MPPT, charge/discharge lead acid batteries, sun tracker and supervision. These different functions are performed with a microcontroller that has capabilities and functions to the reliability of PV systems (signal generation Pulses Width Modulation (PWM, speed etc.. Concerning the MPPT control operation, we improved the accuracy and reliability of research by improving the search algorithm “Hill Climbing” taking into account the optimal operation of PV panels depending on weather conditions (temperature and light.The experiment of each block shows that the MPPT control converges instantly the operating point of the PV panels around the maximum power point, independently of sudden changes of the illumination or the load. The control blocks charge/discharge battery and sun tracking show good control of charge/discharge lead acid batteries and the need of sun tracker to increase the power supplied by the PV panel. By using the improved MPPT control, loss of power supplied by the PV panels are very low (below 5%.

Function analysis of automatic power controller in Tianwan Nuclear Power Plant

International Nuclear Information System (INIS)

Zhou Haixiang

2006-01-01

The hardware and software design characters of the automatic power controller (APC) in Tianwan NPP are introduced. According to the analysis of the principle and function of the system, both availability and reliability of APC in Tianwan NPP are proved. The paper also supplies some methods on how to design the digital APC system. (authors)

An evaluation method of fault-tolerance for digital plant protection system in nuclear power plants

International Nuclear Information System (INIS)

Lee, Jun Seok; Kim, Man Cheol; Seong, Poong Hyun; Kang, Hyun Gook; Jang, Seung Cheol

2005-01-01

In recent years, analog based nuclear power plant (NPP) safety related instrumentation and control (I and C) systems have been replaced to modern digital based I and C systems. NPP safety related I and C systems require very high design reliability compare to the conventional digital systems so that reliability assessment is very important. In the reliability assessment of the digital system, fault tolerance evaluation is one of the crucial factors. However, the evaluation is very difficult because the digital system in NPP is very complex. In this paper, the simulation based fault injection technique on simplified processor is used to evaluate the fault-tolerance of the digital plant protection system (DPPS) with high efficiency with low cost

Power supply control system for experimental physical facilities

International Nuclear Information System (INIS)

Zelepukin, S.A.; Osipov, Eh.V.; Petrov, V.S.; Sergeev, V.A.; Uglekov, V.Ya.

1979-01-01

A multichannel (to 1024 channels) system for control of power supply voltage is descrited. The system consists of an analog commulator, a digital voltmeter and a special controller. The controller serves at the same time as an interface for connecting the system as a ''unit'' of the VECTOR and SUMMA unified electronic systems. The system has been realized for control of the photomultiplier power supply voltage of the MARK multipurpose experimental device (256 channels, the measurement accuracy is 0.2%, the measuring time is 500 ms per point). Software devised for the HP-2100 computer permits automatical comparison of photomultiplier power supply voltages with sample ones in the mode of continuous control of a single voltage or in the mode of programmed selection of voltages to provide the control in arbitrary order or automatic scanning

The Pastoral Power of Technology. Rethinking Alienation in Digital Culture

Directory of Open Access Journals (Sweden)

Katarina Giritli Nygren

2012-05-01

Full Text Available The purpose of this paper is to bring Foucault’s elaboration on ‘the pastoral modalities of power’ into play in order to rethink alienation in digital culture. Pastoral power is not displacing other conceptions of power, but provides another level of analysis involved in the forging of reasonable responsible subjects willing and able to sustain other conceptions of power. We will draw particularly on the early writings of Marx and the more recent poststructuralist developments concerning hegemony and superstructure in relation to technology. Technology as such is analysed in terms of repercussions of ‘design of the machine’ in industrial technological contexts and ‘design of digital culture’ in digital technological contexts. Pastoral power not only directs our focus to the making of technologies, but also to the making of individuals capable of taking on the responsibilities of technologies. This means that it is necessary to take on the notion of effective power of ideologies and their material reality.

47 CFR 74.795 - Digital low power TV and TV translator transmission system facilities.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 4 2010-10-01 2010-10-01 false Digital low power TV and TV translator... DISTRIBUTIONAL SERVICES Low Power TV, TV Translator, and TV Booster Stations § 74.795 Digital low power TV and TV translator transmission system facilities. (a) A digital low power TV or TV translator station shall operate...

47 CFR 74.792 - Digital low power TV and TV translator station protected contour.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 4 2010-10-01 2010-10-01 false Digital low power TV and TV translator station... SERVICES Low Power TV, TV Translator, and TV Booster Stations § 74.792 Digital low power TV and TV translator station protected contour. (a) A digital low power TV or TV translator will be protected from...

Digitizing Patterns of Power - Cartographic Communication for Digital Humanities

Science.gov (United States)

Kriz, Karel; Pucher, Alexander; Breier, Markus

2018-05-01

The representation of space in medieval texts, the appropriation of land and the subsequent installation of new structures of power are central research topics of the project "Digitizing Patterns of Power" (DPP). The project focuses on three regional case studies: the Eastern Alps and the Morava-Thaya region, the historical region of Macedonia, and historical Southern Armenia. DPP is a multidisciplinary project, conducted by the Austrian Academy of Sciences the Institute for Medieval Research (IMAFO) in cooperation with the University of Vienna, Department of Geography and Regional Research. It is part of an initiative to promote digital humanities research in Austria. DPP brings together expertise from historical and archaeological research as well as cartography and geocommunication to explore medieval geographies. The communication of space, time and spatial interconnectivity is an essential aspect of DPP. By incorporating digital cartographic expertise, relevant facts can be depicted in a more effective visual form. Optimal cartographic visualization of base data as well as the historical and archaeological information in an interactive map-based online platform are important features. However, the multidisciplinary of the project presents the participants with various challenges. The different involved disciplines, among them cartography, archaeology and history each have their own approaches to relevant aspects of geography and geocommunication. This paper treats geocommunication characteristics and approaches to interactive mapping in a historical and archaeological context within a multidisciplinary project environment. The fundamental challenges of cartographic communication within DPP will be presented. Furthermore, recent results on the communication of historical topographic, as well as uncertain thematic content will be demonstrated.

Implementation of digital control and protection systems of China advanced research reactor

International Nuclear Information System (INIS)

Zeng Hai; Jin Huajin; Xu Qiguo; Zhang Mingkui

2005-01-01

China Advanced Research Reactor (CARR), a reactor of the 21st century with high performance is being constructed in China. The requirements of reliability and stability on the control and protection (c and p) system are the main points raised. Especially, with the development of digital technology, the c and p system of CARR is demanded to match the trend of digitization in the field of reactor control. The c and p system, including reactor protection system, reactor monitoring and control system, reactor power regulating system, and the mitigation system for ATWS (Anticipate Transient Without Scram), adopts digital technology, and the digital display screen will replace the analog panels in the main control room. The c and p system of CARR adopts redundant technology with 2 or 3 redundant channels to improve the system reliability. The 10/100 Mbps self-adaptive redundant optic fiber industry Ethernet ring network is used to interlink operator workstations, supervisor workstation, and I/O control stations. Commercial grade equipment with mature experience in industrial application are applied to the c and p system of CARR, which have high reliability, good interchangeability, and is easily purchased, the software-developing tools fully match the international industry standards. The realization of digital c and p system of CARR will promote the progress of digital control technology for reactors in China, and certainly become a technical basic platform for developing informational and intelligent reactors in China. (authors)

Digital controls for plant control systems at the Ulchin 5 and 6 NPP: Lessons for the U.S. NPP retrofits?

International Nuclear Information System (INIS)

McCreary, T.; Stevens, J.

2006-01-01

South Korea, through its nuclear operating arm, Korea Hydro and Nuclear Power, Ltd. (KHNP), has been one of the leading countries in the routine construction and operation of nuclear power plants. While standardizing on certain design approaches in the plant, KHNP continues to stress the need for the most reliable and cutting edge I and C technologies available for safety and non safety related NSSS and BOP functions. Its specifications are among the most challenging in the world with regard to the system performance and reliability requirements that must be met for the systems to be supplied. The Ulchin Units 5 and 6 (1000 MW each) nuclear power plants have been recently commissioned (2004 and 2005 respectively) with advanced programmable digital control systems in the NSSS and BOP (which includes both safety and non-safety applications). The systems supplied met what the authors believe are the most rigorous performance and functional specification criteria in use today. The authors will highlight a number of the specification requirements, the rationale for same and the plant experiences in the resultant supplied systems. As the existing U.S. nuclear fleet is faced with the prospect of upgrading legacy controls with digital controls, there are valuable lessons to be learned in the Ulchin 5 and 6 experiences that can be applied to retrofits and even new U.S. plant designs. Ulchin 5 and 6 is one of the success stories in the application of advanced digital technology to nuclear power plants. The specification focus that guided the selection and project execution for the digital controls supplied for Ulchin was on several key areas: a) a high reliable fault tolerant system, b)functional segmentation to minimize the failure effects on operation, c) validation and verification of the owner's engineer's application design (for regulatory compliance) as well as validation and verification of the system architecture and operation (to assure system performance met

Application of embedded database to digital power supply system in HIRFL

International Nuclear Information System (INIS)

Wu Guanghua; Yan Huaihai; Chen Youxin; Huang Yuzhen; Zhou Zhongzu; Gao Daqing

2014-01-01

Background: This paper introduces the application of embedded MySQL database in the real-time monitoring system of the digital power supply system in Heavy Ion Research Facility in Lanzhou (HIRFL). Purpose: The aim is to optimize the real-time monitoring system of the digital power supply system for better performance. Methods: The MySQL database is designed and implemented under Linux operation system running on ARM processor, together with the related functions for real-time data monitoring, such as collection, storage and query. All status parameters of digital power supply system is collected and communicated with ARM by a FPGA, whilst the user interface is realized by Qt toolkits at ARM end. Results: The actual operation indicates that digital power supply can realize the function of real-time data monitoring, collection, storage and so on. Conclusion: Through practical application, we have found some aspects we can improve and we will try to optimize them in the future. (authors)

Power and reactive power simultaneous control by 0.5 MJ superconducting magnet energy storage

International Nuclear Information System (INIS)

Ise, Toshifumi; Tsuji, Kiichiro; Murakami, Yoshishige

1984-01-01

Superconducting magnet energy storage (SMES) is expected to be widely applied to the pulsed sources for fusion reactor research and to the energy storage substituting for pumping-up power stations, because of its fast energy storing and discharging and very high efficiency. Some results have been obtained so far. In this paper, however, the simultaneous control of power and reactive power is considered for an energy storage composed of two sets of thyristorized power conversion system and superconducting magnets in series connection, and a direct digital control system is described on the principle, design and configuration including the compensator, and on the experiment using the 0.5 MJ superconducting magnet energy storage installed in the Superconduction Engineering Experiment Center, Osaka University. The results obtained are as follows: (1) P control priority mode and Q control priority mode (in which power and reactive power control has priority, respectively) were proposed as the countermeasures when the simultaneous control of power and reactive power became impossible; (2) the design method was established, by which power and reactive power control loops can independently be designed as a result of simulation; (3) the achievement of the simultaneous control of power and reactive power was confirmed by using P-control priority mode and Q-control priority mode, in the experiment using the control system designed by simulation. The validity of simulation model was also confirmed by actual response waveforms. (Wakatsuki, Y.)

Design concepts for a nuclear digital instrumentation and control system platform

International Nuclear Information System (INIS)

Ou, T. C.; Chen, C. K.; Chen, P. J.; Shyu, S. S.; Lee, C. L.; Hsieh, S. F.

2010-10-01

The objective of this paper is to present the development results of the nuclear instrumentation and control system in Taiwan. As the Taiwan nuclear power plants age, the need to consider upgrading of both their safety and non-safety-related instrumentation and control systems becomes more urgent. Meanwhile, the digital instrumentation and control system that is based on current fast evolving electronic and information technologies are difficult to maintain effectively. Therefore, Institute of Nuclear Energy Research was made a decision to promote the Taiwan Nuclear Instrumentation and Control System project to collaborate with domestic electronic industry to establish self-reliant capabilities on the design, manufacturing, and application of nuclear instrumentation and control systems with newer technology. In the case of safety-related applications like nuclear instrumentation and control, safety-oriented quality control is required. In order to establish a generic qualified digital platform, the world-wide licensing experience should be considered in the licensing process. This paper describes the qualification and certification tools by IEC 61508 for design and development of safety related equipment and explains the basis for many decisions made while performing the digital upgrade. (Author)

Digital Processor Module Reliability Analysis of Nuclear Power Plant

International Nuclear Information System (INIS)

Lee, Sang Yong; Jung, Jae Hyun; Kim, Jae Ho; Kim, Sung Hun

2005-01-01

The system used in plant, military equipment, satellite, etc. consists of many electronic parts as control module, which requires relatively high reliability than other commercial electronic products. Specially, Nuclear power plant related to the radiation safety requires high safety and reliability, so most parts apply to Military-Standard level. Reliability prediction method provides the rational basis of system designs and also provides the safety significance of system operations. Thus various reliability prediction tools have been developed in recent decades, among of them, the MI-HDBK-217 method has been widely used as a powerful tool for the prediction. In this work, It is explained that reliability analysis work for Digital Processor Module (DPM, control module of SMART) is performed by Parts Stress Method based on MIL-HDBK-217F NOTICE2. We are using the Relex 7.6 of Relex software corporation, because reliability analysis process requires enormous part libraries and data for failure rate calculation

Combating obsolescence - ACR digital control systems design

International Nuclear Information System (INIS)

Tikku, S.; Raiskums, G.

2006-01-01

The ever increasing use of digital technologies and products to meet the control, automation and monitoring needs of the nuclear power plant - even though justified by the benefits it provides - comes with an increased risk of technological obsolescence happening through the course of the plant life. Some well considered strategies are being employed in the ACR design process to minimise this risk and alleviate the consequence if it happens. These include application of a modular overall architecture, adoption of international widely accepted standards to harmonise equipment qualification and software practices, production of control functional specifications that are not influenced by target platform, and careful selection of technologies and products. (author)

Analysis of Valve Requirements for High-Efficiency Digital Displacement Fluid Power Motors

DEFF Research Database (Denmark)

Rømer, Daniel; Johansen, Per; Pedersen, Henrik C.

2013-01-01

Digital displacement fluid power motors have been shown to enable high-efficiency operation in a wide operation range, including the part load range where conventional fluid power motors suffers from poor efficiencies. The use of these digital displacement motors set new requirements for the valve...... transition time and flow-pressure coefficient are normalized, leading to a presentation of the general efficiency map of the digital displacement motor. Finally the performance of existing commercial valves with respect to digital motors is commented....

Risk assessment of safety data link and network communication in digital safety feature control system of nuclear power plant

International Nuclear Information System (INIS)

Lee, Sang Hun; Son, Kwang Seop; Jung, Wondea; Kang, Hyun Gook

2017-01-01

Highlights: • Safety data communication risk assessment framework and quantitative scheme were proposed. • Fault-tree model of ESFAS unavailability due to safety data communication failure was developed. • Safety data link and network risk were assessed based on various ESF-CCS design specifications. • The effect of fault-tolerant algorithm reliability of safety data network on ESFAS unavailability was assessed. - Abstract: As one of the safety-critical systems in nuclear power plants (NPPs), the Engineered Safety Feature-Component Control System (ESF-CCS) employs safety data link and network communication for the transmission of safety component actuation signals from the group controllers to loop controllers to effectively accommodate various safety-critical field controllers. Since data communication failure risk in the ESF-CCS has yet to be fully quantified, the ESF-CCS employing data communication systems have not been applied in NPPs. This study therefore developed a fault tree model to assess the data link and data network failure-induced unavailability of a system function used to generate an automated control signal for accident mitigation equipment. The current aim is to provide risk information regarding data communication failure in a digital safety feature control system in consideration of interconnection between controllers and the fault-tolerant algorithm implemented in the target system. Based on the developed fault tree model, case studies were performed to quantitatively assess the unavailability of ESF-CCS signal generation due to data link and network failure and its risk effect on safety signal generation failure. This study is expected to provide insight into the risk assessment of safety-critical data communication in a digitalized NPP instrumentation and control system.

Use of digital photography for power plant retrofits

International Nuclear Information System (INIS)

Kamba, J.J.

1995-01-01

One of the latest advancements in electronic tools for reducing engineering and drafting effort is the use of digital photography (DP) for retrofit and betterment projects at fossil and nuclear power plants. Sargent and Lundy (S and L) has effectively used digital photography for condition assessments, minor backfit repairs, thermo-lag fire wrap assessments and repairs, and other applications. Digital photography offers several benefits on these types of projects including eliminating the need for official repair drawings and providing station maintenance with a true 3-D visualization of the repair

CANDU Digital Control Computer upgrade options

International Nuclear Information System (INIS)

De Jong, M.S.; De Grosbois, J.; Qian, T.

1997-01-01

This paper reviews the evolution of Digital Control Computers (DCC) in CANDU power plants to the present day. Much of this evolution has been to meeting changing control or display requirements as well as the replacement of obsolete, or old and less reliable technology with better equipment that is now available. The current work at AECL and Canadian utilities to investigate DCC upgrade options, alternatives, and strategies are examined. The dependence of a particular upgrade strategy on the overall plant refurbishment plans are also discussed. Presently, the upgrade options range from replacement of individual obsolete system components, to replacement of the entire DCC hardware without changing the software, to complete replacement of the DCCs with a functionally equivalent system using new control computer equipment and software. Key issues, constraints and objectives associated with these DCC upgrade options are highlighted. (author)

Experience of digital control systems in Scandinavian BWRs

International Nuclear Information System (INIS)

Rydahl, I.

1989-01-01

Since 1984 digital control systems have been in operation in various Scandinavian BWRs. Examples of such digital control systems are: dual microprocessor based system for complete control of radwaste plant, three channel recirculation control system, and three channel feedwater control system. This paper describes Swedish development from one channel through three channel analog control systems to digital systems. The author describes experience of digital control systems during design, testing, commissioning and operation. The main benefits of digital compared with analog technology are discussed. Especially the outstanding facility of using a built-in process simulator for commissioning and tuning. The use of digital technology in nuclear safety system and future plans are dealt with

Probabilistic safety assessment for instrumentation and control systems in nuclear power plants: an overview

International Nuclear Information System (INIS)

Lu, Lixuan; Jiang, Jin

2004-01-01

Deregulation in the electricity market has resulted in a number of challenges in the nuclear power industry. Nuclear power plants must find innovative ways to remain competitive by reducing operating costs without jeopardizing safety. Instrumentation and Control (I and C) systems not only play important roles in plant operation, but also in reducing the cost of power generation while maintaining and/or enhancing safety. Therefore, it is extremely important that I and C systems are managed efficiently and economically. With the increasing use of digital technologies, new methods are needed to solve problems associated with various aspects of digital I and C systems. Probabilistic Safety Assessment (PSA) has proved to be an effective method for safety analysis and risk-based decisions, even though challenges are still present. This paper provides an overview of PSA applications in three areas of digital I and C systems in nuclear power plants. These areas are Graded Quality Assurance, Surveillance Testing, and Instrumentation and Control System Design. In addition, PSA application in the regulation of nuclear power plants that adopt digital I and C systems is also investigated. (author)

Control circuits in power electronics practical issues in design and implementation

CERN Document Server

Castilla, Miguel

2016-01-01

Control circuits are a key element in the operation and performance of power electronics converters. This book describes practical issues related to the design and implementation of these control circuits, and is divided into three parts - analogue control circuits, digital control circuits, and new trends in control circuits.

Regulatory issues of digital instrumentation and control system in Lungmen project

International Nuclear Information System (INIS)

Chuang, C.F.; Chou, H.P.

2004-01-01

The Lungmen Nuclear Power Station (LNPS) is currently under construction in Taiwan, which consists of 2 advanced boiling water reactor (ABWR) units. The instrumentation and control (IC) systems of the LNPS are based on the state-of-the-art modernized fully integrated digital design. These IC systems possess many advantages and distinguished features comparing to traditional analog IC systems, they enjoy set-point stability, self-diagnostic and automatic testing ability, fault tolerance and avoidance, low power requirements, data handling and storage capability, as well as enhanced human-machine interfaces. This paper presents regulatory overviews, regulatory requirements, current major regulatory issues, as well as the areas of regulatory concerns and the lessons learned on the digital IC systems in the Lungmen Project

Trends in digital I and C for nuclear power plants

International Nuclear Information System (INIS)

Cook, B.M.

2000-01-01

Over the past decade, large-scale digital I and C systems have been installed on nuclear power plants as the original systems for plant operations. Examples of these include Sizewell B in the United Kingdom and Temelin NPP in the Czech Republic. Now, this digital technology is being used for replacement and upgrade systems such as those for Ringhals Unit 2 in Sweden and the Kewaunee plant in the United States. Such a digital upgrade is being planned for the Dukovany NPP in the Czech Republic. As the experience base grows with this digital technology on nuclear power plants, certain trends are developing in the application practices and licensing of these systems. This paper discusses these trends and suggests adaptations that may become necessary in the classical roles of vendors, regulators and plant operators. (author)

Building a new control system for the cyclotron power supplies

International Nuclear Information System (INIS)

Kormany, Z.; Lakatos, T.; Kovacs, P.; Szuecs, I.; Ander, I.

2000-01-01

Complete text of publication follows. The MGC cyclotron of the ATOMKI is a multi-particle and variable-energy machine with a rather complicated beam transport system. As a consequence, the current or voltage value of numerous power supplies should be set and adjusted by the operators during a typical run. The original control system of the cyclotron provides a traditional control desk for this purpose where the requested values can be set by using selector switches and up/down tumblers. The adjustment process with this system is completely manual and rather slow - every power supply unit gets its starting value one after the other and it typically takes 10 to 20 minutes to change the whole setting. Another disadvantage of the present system is the poor reproducibility / the analogue panel meters of the control desk cannot provide the required precision to exactly repeat a former setting. To overcome the above difficulties and speed up the adjustment process of the cyclotron and the beam transport lines, a new control system for the power supplies has been designed and is under implementation within the framework of our modernization project. Supported by the International Atomic Energy Agency, Technical Assistance Program - Project Code Number: HUN/4/013. The control of the power supplies will be changed to digital - the analogue control signals of the power stages will be produced by the D/A, the current and voltage values will be read by the A/D conversion modules of a programmable logic controller (PLC). The transition to digital control requires the development of special interface units. To separate completely the control and measuring channels from each other, they are isolated from the PLC-ground by applying opto-isolators. A two-channel (control and measurement) linear interface circuit built around the TIL 300 optical isolators has been designed, assembled and tested. It has been verified that the linearity and the precision of this circuit fulfills the

Development of digital power measuring and protecting equipment for SPRR-300 reactor

International Nuclear Information System (INIS)

Wang Xuejie; Li Xi'an; Zhu Shilei

2005-01-01

A measuring and protecting equipment of reactor power based on Single-Chip Microcomputer is introduced in this paper. The composition of hardware and the major control idea about the software for the equipment are presented. Digitizing the measuring data from nuclear instruments is precondition of reactor control and protection system which would be computerizing, and it is also an application of redundancy and variety of reactor protection system in nuclear measuring instruments. At last the working state is described. (authors)

Technical study of real-time simulation system for digital I and C system of steam generator in nuclear power plant

International Nuclear Information System (INIS)

Shi Ji; Jiang Mingyu; Ma Yunqin

2004-01-01

The real-time simulation system, which forms a interactive closed circle together with the steam generator control system, has been developed using a dynamic mathematical model of steam generator in this paper. It can provide a simulation target for upgrades of digital Instrument and Control system in Nuclear Power Plant (NPP) and is applicable for further research of control schemes. With this program, the authors have studied and analyzed the response of transient parameters to some different disturbance, the calculated results are in good agreement with those calculated by NPP simulator program. This will give a theoretical analysis for upgrades of digital I and C system in nuclear power plant

47 CFR 74.710 - Digital low power TV and TV translator station protection.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 4 2010-10-01 2010-10-01 false Digital low power TV and TV translator station... SERVICES Low Power TV, TV Translator, and TV Booster Stations § 74.710 Digital low power TV and TV translator station protection. (a) An application to construct a new low power TV, TV translator, or TV...

Accelerator-control-system interface for intelligent power supplies

International Nuclear Information System (INIS)

Cohen, S.

1992-01-01

A number of high-current high-precision magnet power supplies have been installed at the proton storage ring at the Los Alamos National Laboratory Accelerator Complex. The units replace existing supplies, powering large dipole magnets in the ring. These bending magnets require a high-current supply that is precise and stable. The control and interface design for these power supplies represents a departure from all others on-site. The supplies have sophisticated microprocessor control on-board and communicate with the accelerator control system via RS-422 (serial communications). The units, built by Alpha Scientific Electronics, Hayward, CA use a high-level ASCII control protocol. The low-level ''front-end'' software used by the accelerator control system has been written to accommodate these new devices. They communicate with the control system through a terminal server port connected to the site-wide ethernet backbone. Details of the software implementation for the analog and digital control of the supplies through the accelerator control system will be presented

Development of a microprocessor controller for stand-alone photovoltaic power systems

Science.gov (United States)

Millner, A. R.; Kaufman, D. L.

1984-01-01

A controller for stand-alone photovoltaic systems has been developed using a low power CMOS microprocessor. It performs battery state of charge estimation, array control, load management, instrumentation, automatic testing, and communications functions. Array control options are sequential subarray switching and maximum power control. A calculator keypad and LCD display provides manual control, fault diagnosis and digital multimeter functions. An RS-232 port provides data logging or remote control capability. A prototype 5 kW unit has been built and tested successfully. The controller is expected to be useful in village photovoltaic power systems, large solar water pumping installations, and other battery management applications.

Digital control computer upgrade at the Cernavoda NPP simulator

International Nuclear Information System (INIS)

Ionescu, T.

2006-01-01

The Plant Process Computer equips some Nuclear Power Plants, like CANDU-600, with Centralized Control performed by an assembly of two computers known as Digital Control Computers (DCC) and working in parallel for safely driving of the plan at steady state and during normal maneuvers but also during abnormal transients when the plant is automatically steered to a safe state. The Centralized Control means both hardware and software with obligatory presence in the frame of the Full Scope Simulator and subject to changing its configuration with specific requirements during the plant and simulator life and covered by this subsection

Reliability study: digital engineered safety feature actuation system of Korean Standard Nuclear Power Plant

International Nuclear Information System (INIS)

Sudarno; Kang, H. G.; Jang, S. C.; Eom, H. S.; Ha, J. J.

2003-04-01

The usage of digital Instrumentation and Control (I and C) in a nuclear power plant becomes more extensive, including safety related systems. The PSA application of these new designs are very important in order to evaluate their reliability. In particular, Korean Standard Nuclear Power Plants (KSNPPs), typically Ulchin 5 and 6 (UCN 5 and 6) reactor units, adopted the digital safety-critical systems such as Digital Plant Protection System (DPPS) and Digital Engineered Safety Feature Actuation System (DESFAS). In this research, we developed fault tree models for assessing the unavailability of the DESFAS functions. We also performed an analysis of the quantification results. The unavailability results of different DESFAS functions showed that their values are comprised from 5.461E-5 to 3.14E-4. The system unavailability of DESFAS AFAS-1 is estimated as 5.461E-5, which is about 27% less than that of analog system if we consider the difference of human failure probability estimation between both analyses. The results of this study could be utilized in risk-effect analysis of KSNPP. We expect that the safety analysis result will contribute to design feedback

A REVIEW OF HUMAN-SYSTEM INTERFACE DESIGN ISSUES OBSERVED DURING ANALOG-TO-DIGITAL AND DIGITAL-TO-DIGITAL MIGRATIONS IN U.S. NUCLEAR POWER PLANTS

Energy Technology Data Exchange (ETDEWEB)

Kovesdi, C.; Joe, J.

2017-05-01

The United States (U.S.) Department of Energy (DOE) Light Water Reactor Sustainability (LWRS) program is developing a scientific basis through targeted research and development (R&D) to support the U.S. nuclear power plant (NPP) fleet in extending their existing licensing period and ensuring their long-term reliability, productivity, safety, and security. Over the last several years, human factors engineering (HFE) professionals at the Idaho National Laboratory (INL) have supported the LWRS Advanced Instrumentation, Information, and Control (II&C) System Technologies pathway across several U.S. commercial NPPs in analog-to-digital migrations (i.e., turbine control systems) and digital-to-digital migrations (i.e., Safety Parameter Display System). These efforts have included in-depth human factors evaluation of proposed human-system interface (HSI) design concepts against established U.S. Nuclear Regulatory Commission (NRC) design guidelines from NUREG-0700, Rev 2 to inform subsequent HSI design prior to transitioning into Verification and Validation. This paper discusses some of the overarching design issues observed from these past HFE evaluations. In addition, this work presents some observed challenges such as common tradeoffs utilities are likely to face when introducing new HSI technologies into NPP hybrid control rooms. The primary purpose of this work is to distill these observed design issues into general HSI design guidance that industry can use in early stages of HSI design.

POSITION CONTROL OF BRUSHLESS DC MOTOR BASED ON DIGITAL SIGNAL PROCESSING

Directory of Open Access Journals (Sweden)

Çetin GENÇER

2006-01-01

Full Text Available Brushless DC Motors (BLDC have been used widely high performance control systems which are depended on to development of power electronic and control technology. In these motors to fed commutated supply, the control of position without oscilation has been required. In this study, position control of BLDC with digital signal processing has been implemented by a proportional-derivative (PD controller because of its simple structure. It has been seen that the controller which is proposed from simulation and experimental studies, has a quick dynamic responce with nonoscillation.

Ultra-Low-Power Analog-to-Digital Converters for Medical Applications

OpenAIRE

Zhang, Dai

2014-01-01

Biomedical systems are commonly attached to or implanted into human bodies, and powered by harvested energy or small batteries. In these systems, analog-to-digital converters (ADCs) are key components as the interface between the analog world and the digital domain. Conversion of the low frequency bioelectric signals does not require high speed, but ultralow- power operation. This combined with the required conversion accuracy makes the design of such ADCs a major challenge. Among prevalent A...

A multinode digital control system for 500 MWe PHWR

Energy Technology Data Exchange (ETDEWEB)

Patil, G N; Suresh Babu, R M; Jangra, L R; Das, Shantanu; Mallik, S B [Bhabha Atomic Research Centre, Bombay (India). Reactor Control Div.

1994-12-31

A fault tolerant distributed digital computer system for 500 MWe reactor power regulation is configured around standard microcomputer boards designed indigenously. The system is configured as functionally partitioned distributed control system having 8 nodes linked by high-speed dual redundant high-way. The paper gives the details of the configuration of system and how the features of fault-tolerance and fail-safeness are achieved through design. (author). 1 fig.

A dependability modeling of software under hardware faults digitized system in nuclear power plants

International Nuclear Information System (INIS)

Choi, Jong Gyun

1996-02-01

An analytic approach to the dependability evaluation of software in the operational phase is suggested in this work with special attention to the physical fault effects on the software dependability : The physical faults considered are memory faults and the dependability measure in question is the reliability. The model is based on the simple reliability theory and the graph theory with the path decomposition micro model. The model represents an application software with a graph consisting of nodes and arcs that probabilistic ally determine the flow from node to node. Through proper transformation of nodes and arcs, the graph can be reduced to a simple two-node graph and the software failure probability is derived from this graph. This model can be extended to the software system which consists of several complete modules without modification. The derived model is validated by the computer simulation, where the software is transformed to a probabilistic control flow graph. Simulation also shows a different viewpoint of software failure behavior. Using this model, we predict the reliability of an application software and a software system in a digitized system(ILS system) in the nuclear power plant and show the sensitivity of the software reliability to the major physical parameters which affect the software failure in the normal operation phase. The derived model is validated by the computer simulation, where the software is transformed to a probabilistic control flow graph. Simulation also shows a different viewpoint of software failure behavior. Using this model, we predict the reliability of an application software and a software system in a digitized system (ILS system) is the nuclear power plant and show the sensitivity of the software reliability to the major physical parameters which affect the software failure in the normal operation phase. This modeling method is particularly attractive for medium size programs such as software used in digitized systems of

Robust digital controllers for uncertain chaotic systems: A digital redesign approach

Energy Technology Data Exchange (ETDEWEB)

Ababneh, Mohammad [Department of Controls, FMC Kongsberg Subsea, FMC Energy Systems, Houston, TX 77067 (United States); Barajas-Ramirez, Juan-Gonzalo [CICESE, Depto. De Electronica y Telecomunicaciones, Ensenada, BC, 22860 (Mexico); Chen Guanrong [Centre for Chaos Control and Synchronization, Department of Electronic Engineering, City University of Hong Kong (China); Shieh, Leang S. [Department of Electrical and Computer Engineering, University of Houston, Houston, TX 77204-4005 (United States)

2007-03-15

In this paper, a new and systematic method for designing robust digital controllers for uncertain nonlinear systems with structured uncertainties is presented. In the proposed method, a controller is designed in terms of the optimal linear model representation of the nominal system around each operating point of the trajectory, while the uncertainties are decomposed such that the uncertain nonlinear system can be rewritten as a set of local linear models with disturbed inputs. Applying conventional robust control techniques, continuous-time robust controllers are first designed to eliminate the effects of the uncertainties on the underlying system. Then, a robust digital controller is obtained as the result of a digital redesign of the designed continuous-time robust controller using the state-matching technique. The effectiveness of the proposed controller design method is illustrated through some numerical examples on complex nonlinear systems--chaotic systems.

Digital control of grid connected converters for distributed power generation

Energy Technology Data Exchange (ETDEWEB)

Skjellnes, Tore

2008-07-01

Pulse width modulated converters are becoming increasingly popular as their cost decreases and power rating increases. The new trend of small scale power producers, often using renewable energy sources, has created new demands for delivery of energy to the grid. A major advantage of the pulse width modulated converter is the ability to control the output voltage at any point in the voltage period. This enables rapid response to load changes and non-linear loads. In addition it can shape the voltage in response to the output current to create an outward appearance of a source impedance. This is called a virtual impedance. This thesis presents a controller for a voltage controlled three phase pulse width modulated converter. This controller enables operation in standalone mode, in parallel with other converters in a micro grid, and in parallel with a strong main grid. A time varying virtual impedance is presented which mainly attenuates reactive currents. A method of investigating the overall impedance including the virtual impedance is presented. New net standards have been introduced, requiring the converter to operate even during severe dips in the grid voltage. Experiments are presented verifying the operation of the controller during voltage dips. (Author). 37 refs., 65 figs., 10 tabs

Local digital control of power electronic converters in a dc microgrid based on a-priori derivation of switching surfaces

Science.gov (United States)

Banerjee, Bibaswan

In power electronic basedmicrogrids, the computational requirements needed to implement an optimized online control strategy can be prohibitive. The work presented in this dissertation proposes a generalized method of derivation of geometric manifolds in a dc microgrid that is based on the a-priori computation of the optimal reactions and trajectories for classes of events in a dc microgrid. The proposed states are the stored energies in all the energy storage elements of the dc microgrid and power flowing into them. It is anticipated that calculating a large enough set of dissimilar transient scenarios will also span many scenarios not specifically used to develop the surface. These geometric manifolds will then be used as reference surfaces in any type of controller, such as a sliding mode hysteretic controller. The presence of switched power converters in microgrids involve different control actions for different system events. The control of the switch states of the converters is essential for steady state and transient operations. A digital memory look-up based controller that uses a hysteretic sliding mode control strategy is an effective technique to generate the proper switch states for the converters. An example dcmicrogrid with three dc-dc boost converters and resistive loads is considered for this work. The geometric manifolds are successfully generated for transient events, such as step changes in the loads and the sources. The surfaces corresponding to a specific case of step change in the loads are then used as reference surfaces in an EEPROM for experimentally validating the control strategy. The required switch states corresponding to this specific transient scenario are programmed in the EEPROM as a memory table. This controls the switching of the dc-dc boost converters and drives the system states to the reference manifold. In this work, it is shown that this strategy effectively controls the system for a transient condition such as step changes

A Low Power Digital Accumulation Technique for Digital-Domain CMOS TDI Image Sensor.

Science.gov (United States)

Yu, Changwei; Nie, Kaiming; Xu, Jiangtao; Gao, Jing

2016-09-23

In this paper, an accumulation technique suitable for digital domain CMOS time delay integration (TDI) image sensors is proposed to reduce power consumption without degrading the rate of imaging. In terms of the slight variations of quantization codes among different pixel exposures towards the same object, the pixel array is divided into two groups: one is for coarse quantization of high bits only, and the other one is for fine quantization of low bits. Then, the complete quantization codes are composed of both results from the coarse-and-fine quantization. The equivalent operation comparably reduces the total required bit numbers of the quantization. In the 0.18 µm CMOS process, two versions of 16-stage digital domain CMOS TDI image sensor chains based on a 10-bit successive approximate register (SAR) analog-to-digital converter (ADC), with and without the proposed technique, are designed. The simulation results show that the average power consumption of slices of the two versions are 6 . 47 × 10 - 8 J/line and 7 . 4 × 10 - 8 J/line, respectively. Meanwhile, the linearity of the two versions are 99.74% and 99.99%, respectively.

Single event upset mitigation techniques for FPGAs utilized in nuclear power plant digital instrumentation and control

International Nuclear Information System (INIS)

Wang Xin; Holbert, Keith E.; Clark, Lawrence T.

2011-01-01

Highlights: → Triple modular redundancy (TMR) implementation is the best solution for digital I and C. → Maximal probability of two simultaneous errors with TMR maximum partition is 4.44%. → Dual modular redundancy minimum logic partitioning design is an additional option. - Abstract: Field programmable gate arrays (FPGAs) are integrated circuits being increasingly used for digital instrumentation and control (I and C) in nuclear power plants (NPPs) because of low cost, re-configurability and low design turn-around time. However, to ensure reliability, proper design techniques must be employed since the memory and logic in FPGAs are susceptible to single event upsets (SEUs). Triple modular redundancy (TMR) has become a common SEU mitigation design technique because of its straightforward implementation and reliable results. Partitioned TMR approaches are introduced in this paper, and formulae derived indicate that the maximum probability of two simultaneous errors [P E ] max is inversely proportional to the number of logic partitions in a TMR design, when each redundant logic block in every logic partition has the same number of sensitive nodes. However, the maximum logic partitioning design cannot completely eliminate the possibility of two simultaneous upsets. For the example test circuit it is found that [P E ] max is reduced dramatically from 66.67% for minimum logic partitioning to 4.44% for maximum logic partitioning. Because TMR introduces significant overhead due to its full hardware redundancy, a dual modular redundancy approach is also examined for application to less demanding situations. By comparative analysis this study reaches the conclusion that the maximum logic partitioning TMR implementation is the best solution for digital I and C applications in NPPs where obtaining robustness is of the highest importance, despite its higher area overhead.

A New Real Time Lyapunov Based Controller for Power Quality Improvement in Unified Power Flow Controllers Using Direct Matrix Converters

Directory of Open Access Journals (Sweden)

Joaquim Monteiro

2017-06-01

Full Text Available This paper proposes a Direct Matrix Converter operating as a Unified Power Flow Controller (DMC-UPFC with an advanced control method for UPFC, based on the Lyapunov direct method, presenting good results in power quality assessment. This control method is used for real-time calculation of the appropriate matrix switching state, determining which switching state should be applied in the following sampling period. The control strategy takes into account active and reactive power flow references to choose the vector converter closest to the optimum. Theoretical principles for this new real-time vector modulation and control applied to the DMC-UPFC with input filter are established. The method needs DMC-UPFC dynamic equations to be solved just once in each control cycle, to find the required optimum vector, in contrast to similar control methods that need 27 vector estimations per control cycle. The designed controller’s performance was evaluated using Matlab/Simulink software. Controllers were also implemented using a digital signal processing (DSP system and matrix hardware. Simulation and experimental results show decoupled transmission line active (P and reactive (Q power control with zero theoretical error tracking and fast response. Output currents and voltages show small ripple and low harmonic content.

Evaluation of fault coverage for digitalized system in nuclear power plants using VHDL

International Nuclear Information System (INIS)

Kim, Suk Joon; Lee, Jun Suk; Seong, Poong Hyun

2003-01-01

Fault coverage of digital systems is found to be one of the most important factors in the safety analysis of nuclear power plants. Several axiomatic models for the estimation of fault coverage of digital systems have been proposed, but to apply those axiomatic models to real digital systems, parameters that the axiomatic models require should be approximated using analytic methods, empirical methods or expert opinions. In this paper, we apply the fault injection method to VHDL computer simulation model of a real digital system which provides the protection function to nuclear power plants, for the approximation of fault detection coverage of the digital system. As a result, the fault detection coverage of the digital system could be obtained

A dynamic failure evaluation of a simplified digital control system of a nuclear power plant pressurizer

International Nuclear Information System (INIS)

Pinto, J.M.O.; Melo, P.F. Frutuoso e; Saldanha, P.L.C.

2010-01-01

Given the increasing use of digital systems in nuclear power plants, a specific approach to reliability and risk analysis has been required. The digital system reflects many interactions between hardware, software, process variables, and human actions. At the same time, the software, does not have a reliability approach as well-defined as the one existing for the other physical components of the system. Then, its reliability analysis is still under development due to difficulties arising from the complexity, flexibility and interactions present in such systems.The traditional approach of using fault trees is static and does not approach the dynamic interactions in such systems, such as delays in capture and processing information, memory, logic loops, system states, etc. It is necessary to find a reliability methodology that takes into account these issues without violating the existing requirements concerning safety analysis, such as: ability to distinguish between common-cause failures, availability of relevant information to users, like minimal cut sets, and failure probabilities as long as the possibility of incorporating the results into existing probabilistic safety assessments (PSA).One approach is to trace all the possible errors of the digital system through dynamic methodologies. The DFM (Dynamic Flow-graph Methodology) is one of the methodologies that better meets the requirements for modeling dynamic systems. It discretizes the most relevant variables of the analyzed system in states that reflect their behavior, sets the logic that connects them through decision tables and finally performs a system analysis, aiming, for example, the root causes (prime implicants) of a given top event of failure. Three aspects have been addressed, the modeling of the system itself, the incorporation of results to probabilistic safety analyses and identification of software failures.To illustrate the DFM, a simplified digital control system of a typical PWR pressurizer

Virtual instrumention-based linearity test platform for DCCT of digital power supply at SSRF

International Nuclear Information System (INIS)

Tang Junlong; Li Deming; Shen Tianjian; Liu Hong

2008-01-01

Based on virtual instrumentation, a reliable and effective test platform, performing instrument control, data acquisition and data recording, has been established to evaluate linearity of high performance DCCT (DC current transducer) for digital power supply at Shanghai Synchrotron Radiation Facility (SSRF). The software in LabVIEW language was developed to perform computer communication via serial communication (RS232) and GPIB, providing a friendly user interface to the linearity test platform. This makes it easy to test the linearity and control power on or off and current output of high-precision and high-current DC constant current output power supply. The experimental data, stored in an EXCEL file, can be processed to obtain DCCT linearity, and provide basis to further analyze DCCT performance in the future. (authors)

Development, structure and qualification of a new digital instrumentation and control system

International Nuclear Information System (INIS)

Hofmann, H.; Sauer, H.J.

1991-01-01

Introduction of digital instrumentation and control in nuclear power plants is characterized by the need to meet numerous requirements concerning reliability, ergonomic design of the main control room and comprehensive qualification. The system described here is distinguished by a hierarchical and modular structure, being redundant throughout. Ergonomic considerations dominate the layout of the screen-based main control room. Powerful computer-aided engineering tools are employed for planning of the entire system and for generation of the user software. Qualification is performed in step with the development of the system, based on the applicable national and international rules and regulations and in close cooperation with an independent expert. (orig.) [de

Advanced instrumentation and control techniques for nuclear power plants

International Nuclear Information System (INIS)

Hayakawa, Hiroyasu; Makino, Maomi

1989-01-01

Toshiba has been promoting the development and improvement of control and instrumentation (C and I) systems employing the latest technologies, to fulfill the requirements of nuclear power plants for increased reliability, the upgrading of functions, improved maintainability, and reasonable cost. Such development has been systematically performed based on a schematic view of integrated digital control and instrumentation systems, actively adopting state-of-the-art techniques such as the latest man-machine interfaces, digital and optical multiplexing techniques, and artificial intelligence. In addition, comprehensive feedback has been obtained from the accumulation of operating experience. This paper describes the purpose, contents and status of applications of representative newly-developed systems. (author)

47 CFR 74.793 - Digital low power TV and TV translator station protection of broadcast stations.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 4 2010-10-01 2010-10-01 false Digital low power TV and TV translator station... DISTRIBUTIONAL SERVICES Low Power TV, TV Translator, and TV Booster Stations § 74.793 Digital low power TV and TV translator station protection of broadcast stations. (a) An application to construct a new digital low power...

Survey and analysis on environmental and electromagnetic effect on instrumentation and control equipment of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Hwang, In Koo; Lee, Dong Young; Cha, Kyung Ho

2001-03-01

As the instrumentation and control (I and C) equipment suppliers tend to provide digital components rather than conventional analog type components for instrumentation and control systems of nuclear power plants(NPPs), it is unavoidable to adopt digital equipment for safety I and C systems as well as non-safety systems. However, the full introduction of digital equipment for I and C systems of nuclear power plants raises several concerns which have not been considered in conventional analog I and C equipment. The two major examples of the issues of digital systems are environmental/electromagnetic compatibility (EMC) and software reliability. This report presents the survey and research results on environmental and electromagnetic effect on I and C equipment of nuclear power plants to give a guideline for aging management and design process. Electromagnetic site surveys were conducted to be used as a part of technical basis to demonstrate that I and C systems are compatible with the ambient electromagnetic noise in Korean nuclear power plants.

Real-time digital simulation of power electronics systems with Neutral Point Piloted multilevel inverter using FPGA

Energy Technology Data Exchange (ETDEWEB)

Rakotozafy, Mamianja [Groupe de Recherches en Electrotechnique et Electronique de Nancy (GREEN), Faculte des Sciences et Techniques, BP 70239, 54506 Vandoeuvre Cedex (France); CONVERTEAM SAS, Parc d' activites Techn' hom, 24 avenue du Marechal Juin, BP 40437, 90008 Belfort Cedex (France); Poure, Philippe [Laboratoire d' Instrumentation Electronique de Nancy (LIEN), Faculte des Sciences et Techniques, BP 70239, 54506 Vandoeuvre Cedex (France); Saadate, Shahrokh [Groupe de Recherches en Electrotechnique et Electronique de Nancy (GREEN), Faculte des Sciences et Techniques, BP 70239, 54506 Vandoeuvre Cedex (France); Bordas, Cedric; Leclere, Loic [CONVERTEAM SAS, Parc d' activites Techn' hom, 24 avenue du Marechal Juin, BP 40437, 90008 Belfort Cedex (France)

2011-02-15

Most of actual real time simulation platforms have practically about ten microseconds as minimum calculation time step, mainly due to computation limits such as processing speed, architecture adequacy and modeling complexities. Therefore, simulation of fast switching converters' instantaneous models requires smaller computing time step. The approach presented in this paper proposes an answer to such limited modeling accuracies and computational bandwidth of the currently available digital simulators.As an example, the authors present a low cost, flexible and high performance FPGA-based real-time digital simulator for a complete complex power system with Neutral Point Piloted (NPP) three-level inverter. The proposed real-time simulator can model accurately and efficiently the complete power system, reducing costs, physical space and avoiding any damage to the actual equipment in the case of any dysfunction of the digital controller prototype. The converter model is computed at a small fixed time step as low as 100 ns. Such a computation time step allows high precision account of the gating signals and thus avoids averaging methods and event compensations. Moreover, a novel high performance model of the NPP three-level inverter has also been proposed for FPGA implementation. The proposed FPGA-based simulator models the environment of the NPP converter: the dc link, the RLE load and the digital controller and gating signals. FPGA-based real time simulation results are presented and compared with offline results obtained using PLECS software. They validate the efficiency and accuracy of the modeling for the proposed high performance FPGA-based real-time simulation approach. This paper also introduces new potential FPGA-based applications such as low cost real time simulator for power systems by developing a library of flexible and portable models for power converters, electrical machines and drives. (author)

Design and Implement a Digital H∞ Robust Controller for a MW-Class PMSG-Based Grid-Interactive Wind Energy Conversion System

Directory of Open Access Journals (Sweden)

Tomonobu Senjyu

2013-04-01

Full Text Available A digital H∞ controller for a permanent magnet synchronous generator (PMSG based wind energy conversion system (WECS is presented. Wind energy is an uncertain fluctuating resource which requires a tight control management. So, it is still an exigent task for the control design engineers. The conventional proportional-integral (PI control is not ideal during high turbulence wind velocities, and the nonlinear behavior of the power converters. These are raising interest towards the robust control concepts. The robust design is to find a controller, for a given system, such that the closed-loop system becomes robust that assurance high-integrity and fault tolerant control system, robust H∞ control theory has befallen a standard design method of choice over the past two decades in industrial control applications. The robust H∞ control theory is also gaining eminence in the WECS. Due to the implementation complexity for the continuous H∞ controller, and availability of the high speedy micro-controllers, the design of a sample-data or a digital H∞ controller is very important for the realistic implementation. But there isn’t a single research to evaluate the performance of the digital H∞ controller for the WECS. In this paper, the proposed digital H∞ controller schemes comprise for the both generator and grid interactive power converters, and the control performances are compared with the conventional PI controller and the fuzzy controller. Simulation results confirm the efficacy of the proposed method Energies 2013, 6 2085 which are ensured the WECS stabilities, mitigate shaft stress, and improving the DC-link voltage and output power qualities.

Control Board Digital Interface Input Devices – Touchscreen, Trackpad, or Mouse?

Energy Technology Data Exchange (ETDEWEB)

Thomas A. Ulrich; Ronald L. Boring; Roger Lew

2015-08-01

The authors collaborated with a power utility to evaluate input devices for use in the human system interface (HSI) for a new digital Turbine Control System (TCS) at a nuclear power plant (NPP) undergoing a TCS upgrade. A standalone dynamic software simulation of the new digital TCS and a mobile kiosk were developed to conduct an input device study to evaluate operator preference and input device effectiveness. The TCS software presented the anticipated HSI for the TCS and mimicked (i.e., simulated) the turbine systems’ responses to operator commands. Twenty-four licensed operators from the two nuclear power units participated in the study. Three input devices were tested: a trackpad, mouse, and touchscreen. The subjective feedback from the survey indicates the operators preferred the touchscreen interface. The operators subjectively rated the touchscreen as the fastest and most comfortable input device given the range of tasks they performed during the study, but also noted a lack of accuracy for selecting small targets. The empirical data suggest the mouse input device provides the most consistent performance for screen navigation and manipulating on screen controls. The trackpad input device was both empirically and subjectively found to be the least effective and least desired input device.

Digital control for turbogas units; Control digital para unidades turbogas

Energy Technology Data Exchange (ETDEWEB)

Garcia Beltran, Carlos Daniel

1997-02-01

The present thesis deals with the rehabilitation of the control system for the gas turbines W501 of the Gomez Palacio Combined Cycle Power Station in the state of Durango, Mexico. The first part of the development deals with a re-engineering process of software applied to the digital control system of the gas turbines of the Gomez Palacio Combined Cycle Power Station. This process was developed using concepts of several branches of engineering: a) involved the knowledge of the software engineering, using formal methods for the analysis of the original system and the redesign of the new system; b) The control engineering was used in the analysis of diverse control and automation strategies employed for gas turbines control, with the objective of verifying the type of instructions and existing routines within the software. The final product of this stage is a modulated programmatic system, based on structured design that is functionally a mirror image of the original system. The system obtained conformed by five main modules which are based on a model proposed originally for control by batch: i) Man Machine Interface, ii) Regulatory Control, iii) Protections, iv) Logic sequences and v) Supervision. The second stage of development was the improvement of the speed control of the turbine. When a turbogas unit is controlled, it must be taken into account several operation stages such as the starting, the control in stable state and the shut down. The real behavior of the turbine during the starting, and mainly the great number of backward movements produced, proposed by itself the search of a new controller who more closely maintained the acceleration specifications whereupon the turbine was designed. The development of a new control algorithm began with the analysis of the process, trying to identify which are the critical stages of this one and be able to evaluate in an objective form the advantages of an algorithm upon the other. It was continued with the

Analyzing the decision making process of certifying digital control systems of nuclear power plants

International Nuclear Information System (INIS)

Yih, Swu; Fan, Chin-Feng

2012-01-01

Highlights: ► We have performed basic research in analyzing certification process and developed a regulatory decision making model for nuclear digital control system certification. The model views certification as an evidence–confidence conversion process. ► We have applied this model to analyze previous nuclear digital I and C certification experiences and obtained valuable insights. ► Furthermore, a prototype of a computer-aided licensing support system based on the model has been developed to enhance regulatory review efficiency. - Abstract: Safety-critical computing systems need regulators’ approval before operation. Such a permit issue process is called “certification”. Digital instrumentation and Control (I and C) certification in the nuclear domain has always been problematic and lengthy. Thus, the certification efficiency has always been a crucial concern to the applicant whose business depends on the regulatory decision. However, to our knowledge, there is little basic research on this topic. This study presents a Regulatory Decision-Making Model aiming at analyzing the characteristics and efficiency influence factors in a generic certification process. This model is developed from a dynamic operational perspective by viewing the certification process as an evidence–confidence conversion process. The proposed model is then applied to previous nuclear digital I and C certification experiences to successfully explain why some cases were successful and some were troublesome. Lessons learned from these cases provide invaluable insights regarding to the regulatory review activity. Furthermore, to utilize the insights obtained from the model, a prototype of a computer-aided licensing support system has been developed to speed up review evidence preparation and manipulation; thus, regulatory review efficiency can be further improved.

The modular design method for digital control systems in Japanese BWRs

International Nuclear Information System (INIS)

Kondoh, Y.; Motomura, A.

1998-01-01

Digital technology is being applied to control systems in nuclear power plants. Especially in Japanese BWRs, control systems are being digitized both in constructing plant and in retrofit of operating plants. Digital technology has many advantages compared with analog technology. However, its high performance and flexibility may result in too complicated software structure, which will cause long design time and long testing time and increase cost. In introduction of digital technology, it is most important to restrict unnecessary flexibility of software. The function of control systems can be divided in standard part and variable part. Standard function may be common to every plant while variable function should be designed for each plant. Even in current design, standard design is preserved to be reused in next application. However, this design approach is not always effective because standard function may be changed by customer and nothing is considered for variable part even if it is large. To keep reliability and reduce cost by software reuse, Toshiba adopts modular design of control software, where standard part is designed as a set of standard functional modules and variable function is designed as a complex of standard functional modules and plant unique modules. Toshiba firstly applied modular design method to fuel handling machine control system. In this application the design work has been reduced to 30 percent by reusing of functional module which was first developed in former applications. This remarkable reduction of design work has enhanced reliability with less cost. In addition, software, has been produced and tested according to the functional module. These qualified software modules will be applied to next system and will realize highest reliability and least cost. Toshiba is now planning the application of this modular design method for every digital control system. (author)

Expert systems in power substation operation and control

Energy Technology Data Exchange (ETDEWEB)

Ribeiro, Guilherme Moutinho; Lambert-Torres, Germano; Silva, Alexandre P. Alves da [Escola Federal de Engenharia de Itajuba, MG (Brazil)

1994-12-31

With digital technology being increasingly adopted in power substations (SE), perspectives are created for integration of supervision, control and protection systems in addition to making its process automation feasible. Once a SE is digitalized, the systems which previously were implemented physically will be able to be implemented by means of computer programs (software), allowing the expansion of its scope of operation. Studies and research performed at the international level have pointed to the utilization of Expert Systems (ES) as a more suitable alternative for representation and solution of the operation and control problems, especially those which do not have an established theory, which are provided with diagnosis characteristics and that associate themselves with fuzzy data and information. (author) 4 refs., 3 figs.

Digitized self-oscillating loop for piezoelectric transformer-based power converters

DEFF Research Database (Denmark)

Ekhtiari, Marzieh; Andersen, Thomas; Zhang, Zhe

2016-01-01

A new method is implemented in designing of self-oscillating loop for driving piezoelectric transformers. The implemented method is based on combining both analog and digital control systems. Digitized delay, or digitized phase shift through the self-oscillating loop results in a very precise...... frequency control and ensures an optimum operation of the piezoelectric transformer in terms of voltage gain and efficiency. In this work, additional time delay is implemented digitally for the first time through 16 bit digital-to-analog converter to the self-oscillating loop. Delay control setpoints...... updates at a rate of 417 kHz. This allows the control loop to dynamically follow frequency changes of the transformer in each resonant cycle. The operation principle behind self-oscillating is discussed in this paper. Moreover, experimental results are reported....

Real time Intelligent Control Laboratory (RT-ICL) of PowerLabDK for smart grid technology development

DEFF Research Database (Denmark)

Ostergaard, Jacob; Wu, Qiuwei; Garcia-Valle, Rodrigo

2012-01-01

This paper presents the Intelligent Control Laboratory (ICL) of the PowerLabDK and describes examples of ongoing research work utilizing the ICL. The ICL is comprised of a real time digital simulator (RTDS) with 5 racks, a full scale SCADA system and experimental control room with a link to the B......This paper presents the Intelligent Control Laboratory (ICL) of the PowerLabDK and describes examples of ongoing research work utilizing the ICL. The ICL is comprised of a real time digital simulator (RTDS) with 5 racks, a full scale SCADA system and experimental control room with a link...

Application of digital control in Japanese PWR Plants

International Nuclear Information System (INIS)

Taguchi, S.; Kondo, Y.; Teranishi, S.; Matsumiya, M.; Takashima, M.; Nagai, T.

1986-01-01

More reliable and flexible control system to improve the plant availability and operability is constantly demanded. In order to answer the demands, digital control systems are being applied to Japanese PWR plants. Microprocessor-based digital control systems are widely used in other industries and show good performance. The digital control system has been already applied to the chemical and volume control system and the radioactive waste disposal system in the operating plants. These systems have been working as expected and demonstrating good performances. The digital control system for the reactor control system, which is the main control system of the PWR plants, is being developed. The design of the system has been already finished and the verification/validation process is now in progress

Integrated power electronic converters and digital control

CERN Document Server

Emadi, Ali; Nie, Zhong

2009-01-01

Non-isolated DC-DC ConvertersBuck ConverterBoost ConverterBuck-Boost ConverterIsolated DC-DC ConvertersFlyback ConverterForward ConverterPush-Pull ConverterFull-Bridge ConverterHalf-Bridge ConverterPower Factor CorrectionConcept of PFCGeneral Classification of PFC CircuitsHigh Switching Frequency Topologies for PFCApplication of PFC in Advanced Motor DrivesIntegrated Switched-Mode Power ConvertersSwitched-Mode Power SuppliesThe Concept of Integrated ConverterDefinition of Integrated Switched-Mode Power Supplies (ISMPS)Boost-Type Integrated TopologiesGeneral Structure of Boost-Type Integrated T

An Embedded Based Digital Controller for Thermal Process

Directory of Open Access Journals (Sweden)

A. Lakshmi Sangeetha

2008-01-01

Full Text Available This paper describes a low cost virtual instrumentation (VI system to monitor and control the electrically heated water bath temperature. The PIC16F877 based digital microcontroller is used as thermostat which controls and monitors the temperature. The digital controller also allows the user to modify the sensor (PT100 calibration data values if necessary. The developed programmable on/off control function provides on-line display of measuring temperature, set point as well as the control function output plots through the parallel port. This bus interaction is realized in Visual Basic/Assembly Language and uses a 16 bit, 10 ms sampling analog-to-digital converter (ADS 7805 for monitoring and controlling the parameters of the temperature local digital controller.

Application of discrete function and software control flow to dependability assessment of embedded digital system

International Nuclear Information System (INIS)

Choi, Jong Gyun; Seong, Poong Hyun

2001-01-01

This article describes a combinatorial model for estimating the reliability of the embedded digital system by means of discrete function theory and software control flow. This model includes a coverage model for fault processing mechanisms implemented in digital system. Furthermore, the model considers the interaction between hardware and software. The fault processing mechanisms make it difficult for many types of components in digital system to be treated as binary state, good or bad. The discrete function theory provides a complete analysis of multi-state system as which the digital system can be regarded Through adaptation software control flow to discrete function theory, the HW/SW interaction is considered for estimation of the reliability of digital system. Using this model, we predict the reliability of one board controller in a digital system, Interposing Logic System(ILS), which is installed in YGN nuclear power units 3 and 4. Since the proposed model is general combinatinal model, the simplification of this model becomes a conservative model that treats the system as binary state. Moreover, if information for coverage factor of fault tolerance mechanisms implemented in system through fault injection experiment is obtained, this model can consider detailed interaction of system components

Addressing Obsolescence in Operating Power Stations by Implementation of Safety Related Digital Upgrades Paper for Spanish Nuclear Society

Energy Technology Data Exchange (ETDEWEB)

Legrand, R.

2014-07-01

Obsolescence of Instrumentation and Controls is a major problem facing operating Nuclear Power Stations globally. AREVA is the only supplier that has supported the successful licensing, engineering, procurement, installation and commissioning of a full-scope digital Instrumentation and Control (I and C) Protection System in the United States. (Author)

Advanced Instrumentation and control techniques for nuclear power plants

International Nuclear Information System (INIS)

Mori, Nobuyuki; Makino, Maomi; Naito, Norio

1992-01-01

Toshiba has been promoting the development of an advanced instrumentation and control system for nuclear power plants to fulfill the requirements for increased reliability, improved functionality and maintainability, and more competitive economic performance. This system integrates state-of-the-art technologies such as those for the latest man-machine interface, digital processing, optical multiplexing signal transmission, human engineering, and artificial intelligence. Such development has been systematically accomplished based on a schematic view of integrated digital control and instrumentation systems, and the development of whole systems has now been completed. This paper describes the purpose, design philosophy, and contents of newly developed systems, then considers the future trends of advanced man-machine systems. (author)

Control and data processing systems in UK nuclear power plant and nuclear facilities

International Nuclear Information System (INIS)

Baldwin, J.A.; Wall, D.N.

1997-01-01

This note identifies some of the data processing and control systems in UK nuclear power plant, with emphasis on direct digital control systems and sequence control. A brief indication is also given of some of the associated research activities on control systems and software. (author). 2 figs

Control and data processing systems in UK nuclear power plant and nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Baldwin, J A; Wall, D N [AEA Technology, Winfrith, Dorchester (United Kingdom)

1997-07-01

This note identifies some of the data processing and control systems in UK nuclear power plant, with emphasis on direct digital control systems and sequence control. A brief indication is also given of some of the associated research activities on control systems and software. (author). 2 figs.

A basic design of microcontroller based data processor and local display for digital logarithmic power channel

International Nuclear Information System (INIS)

Nur Khasan; Syahrudin Yusuf

2009-01-01

A data processor and its local display for a digital logarithmic power channel, which will be used as a complement and diversification of nuclear reactor instrument, has been designed using micro controller base circuit. This power channel has been designed using TTL device and microcontroller. The roll of the microcontroller will be as data acquisition, data processing for the measurement of percentage reactor power, period and the trip decision. In this design has beer; created display of numerical value will be display on the local display in on-line mode for 1 nV to 10 10 nV neutron flux measurement range. This logarithmic power channel is expected to support the existing instrument which uses analog system in Instrumentation and Control System of nuclear reactor. (author)

Digital intelligent booster for DCC miniature train networks

Science.gov (United States)

Ursu, M. P.; Condruz, D. A.

2017-08-01

Modern miniature trains are now driven by means of the DCC (Digital Command and Control) system, which allows the human operator or a personal computer to launch commands to each individual train or even to control different features of the same train. The digital command station encodes these commands and sends them to the trains by means of electrical pulses via the rails of the railway network. Due to the development of the miniature railway network, it may happen that the power requirement of the increasing number of digital locomotives, carriages and accessories exceeds the nominal output power of the digital command station. This digital intelligent booster relieves the digital command station from powering the entire railway network all by itself, and it automatically handles the multiple powered sections of the network. This electronic device is also able to detect and process short-circuits and overload conditions, without the intervention of the digital command station.

Probabilistic safety assessment for digital instrumentation and control systems in nuclear power plants - a review

International Nuclear Information System (INIS)

Lu, L.; Jiang, J.

2003-01-01

Deregulation in electricity market has created a great deal of challenges for nuclear power industries [1]. To stay competitive, Nuclear Power Plants (NPPs) will have to find ways to reduce their operational costs and to improve the plant safety. Instrumentation and Control (I and C) systems play an important role in this regard. Thus, new methodologies need to be developed to manage the operation of I and C systems more economically without jeopardizing the overall plant safety. Probabilistic Safety Assessment (PSA) technique is one of the promising methods to deal with such an issue, because PSA analyzes various system operational issues from a probabilistic sense, rather than a worst-case approach. However, there are several limitations when PSA is applied to I and C systems directly. A possible solution to this problem can be found by incorporating PSA with several other approaches. To better understand the issues involved, an attempt has been made in this paper to carry out a literature survey on this and related subject, particularly the effort will be made on: 1) the development of digital I and C systems in NPP, 2) PSA and its potential benefits and limitations, and 3) applications of PSA in various aspects of I and C systems including the resource allocation, the determination of surveillance testing strategies and the design of I and C systems. Finally, some solutions to overcome the aforementioned obstacles when applying PSA in I and C systems are also examined critically. (author)

Training simulator for nuclear power plant reactor control model and method

International Nuclear Information System (INIS)

Czerbuejewski, F.R.

1975-01-01

A description is given of a method and system for the real-time dynamic simulation of a nuclear power plant for training purposes, wherein a control console has a plurality of manual and automatic remote control devices for operating simulated control rods and has indicating devices for monitoring the physical operation of a simulated reactor. Digital computer means are connected to the control console to calculate data values for operating the monitoring devices in accordance with the control devices. The simulation of the reactor control rod mechanism is disclosed whereby the digital computer means operates the rod position monitoring devices in a real-time that is a fraction of the computer time steps and simulates the quick response of a control rod remote control lever together with the delayed response upon a change of direction

Implementation of Power Efficient Flash Analogue-to-Digital Converter

Directory of Open Access Journals (Sweden)

Taninki Sai Lakshmi

2014-01-01

Full Text Available An efficient low power high speed 5-bit 5-GS/s flash analogue-to-digital converter (ADC is proposed in this paper. The designing of a thermometer code to binary code is one of the exacting issues of low power flash ADC. The embodiment consists of two main blocks, a comparator and a digital encoder. To reduce the metastability and the effect of bubble errors, the thermometer code is converted into the gray code and there after translated to binary code through encoder. The proposed encoder is thus implemented by using differential cascade voltage switch logic (DCVSL to maintain high speed and low power dissipation. The proposed 5-bit flash ADC is designed using Cadence 180 nm CMOS technology with a supply rail voltage typically ±0.85 V. The simulation results include a total power dissipation of 46.69 mW, integral nonlinearity (INL value of −0.30 LSB and differential nonlinearity (DNL value of −0.24 LSB, of the flash ADC.

Distributed digital real-time control system for TCV tokamak

Energy Technology Data Exchange (ETDEWEB)

Le, H.B. [École Polytechnique Fédérale de Lausanne (EPFL), Centre de Recherches en Physique des Plasmas (CRPP), Association EURATOM-Confédération Suisse, CH-1015 Lausanne (Switzerland); Felici, F. [Eindhoven University of Technology, P.O. Box 513, 5600 MB Eindhoven (Netherlands); Paley, J.I.; Duval, B.P.; Moret, J.-M.; Coda, S.; Sauter, O.; Fasel, D.; Marmillod, P. [École Polytechnique Fédérale de Lausanne (EPFL), Centre de Recherches en Physique des Plasmas (CRPP), Association EURATOM-Confédération Suisse, CH-1015 Lausanne (Switzerland)

2014-03-15

Highlights: • A new distributed digital control system for the TCV tokamak has been commissioned. • Data is shared in real-time between all nodes using the reflective memory. • The customised Linux OS allows achieving deterministic and low latency behaviour. • The control algorithm design in Simulink together with the automatic code generation using Embedded Coder allow rapid algorithm development. • Controllers designed outside the TCV environment can be ported easily. • The previous control system functions have been emulated and improved. • New capabilities include MHD control, profile control, equilibrium reconstruction. - Abstract: A new digital feedback control system (named the SCD “Système de Contrôle Distribué”) has been developed, integrated and used successfully to control TCV (Tokamak à Configuration Variable) plasmas. The system is designed to be modular, distributed, and scalable, accommodating hundreds of diagnostic inputs and actuator outputs. With many more inputs and outputs available than previously possible, it offers the possibility to design advanced control algorithms with better knowledge of the plasma state and to coherently control all TCV actuators, including poloidal field (PF) coils, gas valves, the gyrotron powers and launcher angles of the electron cyclotron heating and current drive system (ECRH/ECCD) together with diagnostic triggering signals. The system consists of multiple nodes; each is a customised Linux desktop or embedded PC which may have local ADC and DAC cards. Each node is also connected to a memory network (reflective memory) providing a reliable, deterministic method of sharing memory between all nodes. Control algorithms are programmed as block diagrams in Matlab-Simulink providing a powerful environment for modelling and control design. The C code is generated automatically from the Simulink block diagram and compiled, with the Simulink Embedded Coder (SEC, formerly Real-Time Workshop Embedded

Modernization of control system using the digital control system; Modernizacion de sistemas de control usando la simulacion como herramiento de ingenieria

Energy Technology Data Exchange (ETDEWEB)

Carrasco, J. A.; Fernandez, L.; Jimenez, A.

2002-07-01

Nowadays, all plant automation tendencies are based on the use of Digital Control System. In big industrial plants the control systems employed are Distributed Control Systems (DCS). The addition of these systems in nuclear power plants,implies an important adaptation process, because most of them were installed using analog control systems. This paper presents the objectives and the first results obtained, in a modernization project, focused in obtaining an engineering platform for making test and analysis of changes prior to their implementation in a nuclear plant. Modernization, Upgrade, DCS, Automation, Simulation, Training. (Author)

Abnormal condition and events analysis for instrumentation and control systems. Volume 1: Methodology for nuclear power plant digital upgrades. Final report

International Nuclear Information System (INIS)

McKemy, S.; Marcelli, M.; Boehmer, N.; Crandall, D.

1996-01-01

The ACES project was initiated to identify a cost-effective methodology for addressing abnormal conditions and events (ACES) in digital upgrades to nuclear power plant systems, as introduced by IEEE Standard 7-4.3.2-1993. Several methodologies and techniques currently in use in the defense, aerospace, and other communities for the assurance of digital safety systems were surveyed, and although several were shown to possess desirable qualities, non sufficiently met the needs of the nuclear power industry. This report describes a tailorable methodology for performing ACES analysis that is based on the more desirable aspects of the reviewed methodologies and techniques. The methodology is applicable to both safety- and non-safety-grade systems, addresses hardware, software, and system-level concerns, and can be applied in either a lifecycle or post-design timeframe. Employing this methodology for safety systems should facilitate the digital upgrade licensing process

The instrument control unit of SPICA SAFARI: a macro-unit to host all the digital control functionalities of the spectrometer

Science.gov (United States)

Di Giorgio, Anna Maria; Biondi, David; Saggin, Bortolino; Shatalina, Irina; Viterbini, Maurizio; Giusi, Giovanni; Liu, Scige J.; Cerulli-Irelli, Paquale; Van Loon, Dennis; Cara, Christophe

2012-09-01

We present the preliminary design of the Instrument Control Unit (ICU) of the SpicA FAR infrared Instrument (SAFARI), an imaging Fourier Transform Spectrometer (FTS) designed to give continuous wavelength coverage in both photometric and spectroscopic modes from around 34 to 210 µm. Due to the stringent requirements in terms of mass and volume, the overall SAFARI warm electronics will be composed by only two main units: Detector Control Unit and ICU. ICU is therefore a macro-unit incorporating the four digital sub-units dedicated to the control of the overall instrument functionalities: the Cooler Control Unit, the Mechanism Control Unit, the Digital processing Unit and the Power Supply Unit. Both the mechanical solution adopted to host the four sub-units and the internal electrical architecture are presented as well as the adopted redundancy approach.

A Novel Sliding Mode Control Technique for Indirect Current Controlled Active Power Filter

Directory of Open Access Journals (Sweden)

Juntao Fei

2012-01-01

Full Text Available A novel sliding mode control (SMC method for indirect current controlled three-phase parallel active power filter is presented in this paper. There are two designed closed loops in the system: one is the DC voltage controlling loop and the other is the reference current tracking loop. The first loop with a PI regulator is used to control the DC voltage approximating to the given voltage of capacitor, and the output of PI regulator through a low-pass filter is applied as the input of the power supply reference currents. The second loop implements the tracking of the reference currents using integral sliding mode controller, which can improve the harmonic treating performance. Compared with the direct current control technique, it is convenient to be implemented with digital signal processing system because of simpler system structure and better harmonic treating property. Simulation results verify that the generated reference currents have the same amplitude with the load currents, demonstrating the superior harmonic compensating effects with the proposed shunt active power filter compared with the hysteresis method.

Power and Aging Characterization of Digital FIR Filters Architectures

DEFF Research Database (Denmark)

Calimera, Andrea; Liu, Wei; Macii, Enrico

2012-01-01

-variation, temperature and aging induced variations pose new challenges in the fabrication of the next generation of ICs. This work presents a detailed power and aging characterization of digital FIR filters in an industrial 45nm CMOS technology, and a design space exploration of different filter architectures...... with respect to throughput, area, power dissipation and aging. The exploration is intended to provide new design guidelines when considering aging of components in power/performance tradeoffs....

Review report: safety and reliability issues on digital instrumentation and control systems in nuclear power plants and United States Nuclear Regulatory Commission's dispositions

International Nuclear Information System (INIS)

Watanabe, Norio; Suzudo, Tomoaki

1998-09-01

Recently, digital instrumentation and control (I and C) systems have been applied to nuclear power plants (NPPs) in various countries. Introduction of digital I and C systems, however, raises special issues on design, implementation, safety and licensing. Since FY 1997, the Japan Atomic Energy Research Institute (JAERI) has been carrying out a project, Study on Reliability of Digital I and C Systems, which includes extensive reviews of design approaches, technical standards, regulatory processes, especially, in the United States. This report summarizes the results from the study of National Research Council (NRC) and the U.S. Nuclear Regulatory Commission's (USNRC's) responses to the recommendations made by the NRC's study. That study identified six technical key issues (system aspects of digital I and C technology, software quality assurance, common-mode software failure potential, safety and reliability assessment methods, human factors and man-machine interface, dedication of commercial off-the-shelf hardware and software) and two strategic key issues (case-by-case licensing process, adequacy of technical infrastructure) that arise from the introduction of digital I and C technology and then, made recommendations to the USNRC for coping with digital I and C applications. The USNRC responded to each recommendation and showed their own dispositions in which the USNRC agreed with most of the recommendations. In Japan, it is expected that introduction of digital I and C technology is inevitable in NPPs because the vendors are gradually discontinuing support and stocking of analog components. To cope with such situations, there is a need to develop and update the standards and guidelines applicable to digital I and C technology. The key issues and the USNRC's dispositions provided in this report is believed to be useful for developing and updating them. (J.P.N.)

A Classification Method of Technical Security Controls for Digital I and C Systems in NPPs

International Nuclear Information System (INIS)

Song, J. G.; Lee, J. W.; Park, G. Y.; Kwon, K. C.; Lee, D. Y.; Lee, C. K.

2012-01-01

The instrumentation and control (I and C) systems in nuclear power plants (NPPs) are a key facility to monitor plant state, control plant devices, and prevent accidents. Recent I and C systems have been composed of digital systems in order to enhance the effectiveness of operation and maintenance of NPPs. An assessment method for the analysis of security controls is needed to respond to potential cyber attacks against digital I and C systems. RG 5.71 'Cyber Security Programs for Nuclear Facilities' published by U.S.NRC in 2010 presents a comprehensive set of security controls for NPPs. Although this document provides the requirements of security controls, a guidance describing which security controls should be applied to specific digital assets and how to implement them is still needed for the I and C system design and development. In this paper, a classification method of the technical security controls listed in RG 5.71 is proposed to provide a guide useful for the application of the controls during the design and implementation phases of I and C systems

A Classification Method of Technical Security Controls for Digital I and C Systems in NPPs

Energy Technology Data Exchange (ETDEWEB)

Song, J. G.; Lee, J. W.; Park, G. Y.; Kwon, K. C.; Lee, D. Y.; Lee, C. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-05-15

The instrumentation and control (I and C) systems in nuclear power plants (NPPs) are a key facility to monitor plant state, control plant devices, and prevent accidents. Recent I and C systems have been composed of digital systems in order to enhance the effectiveness of operation and maintenance of NPPs. An assessment method for the analysis of security controls is needed to respond to potential cyber attacks against digital I and C systems. RG 5.71 'Cyber Security Programs for Nuclear Facilities' published by U.S.NRC in 2010 presents a comprehensive set of security controls for NPPs. Although this document provides the requirements of security controls, a guidance describing which security controls should be applied to specific digital assets and how to implement them is still needed for the I and C system design and development. In this paper, a classification method of the technical security controls listed in RG 5.71 is proposed to provide a guide useful for the application of the controls during the design and implementation phases of I and C systems

A new control strategy for nuclear power reactors

International Nuclear Information System (INIS)

Wakabayashi, H.; Sasaki, K.; Takegaki, M.

1990-01-01

A new automatic direct digital control strategy for nuclear power reactors is presented. It is based on a simple control logic of comparison between the available time (the time for the error signal to disappear) and the required time (the time for the time derivative to match that of the target trend). The method aims to control the system to an acceptable state within a minimum time under a number of restraints. The control capability of the method is shown for two typical transients. This method is generally applicable to process control in which time-optimal control based on the maximum principle is sought

A novel analog/digital reconfigurable automatic gain control with a novel DC offset cancellation circuit

Energy Technology Data Exchange (ETDEWEB)

He Xiaofeng; Ye Tianchun [Institute of Microelectronics, Chinese Academy of Science, Beijing 100029 (China); Mo Taishan; Ma Chengyan, E-mail: hexiaofeng@casic.ac.cn [Hangzhou Zhongke Microelectronics Co, Ltd, Hangzhou 310053 (China)

2011-02-15

An analog/digital reconfigurable automatic gain control (AGC) circuit with a novel DC offset cancellation circuit for a direct-conversion receiver is presented. The AGC is analog/digital reconfigurable in order to be compatible with different baseband chips. What's more, a novel DC offset cancellation (DCOC) circuit with an HPCF (high pass cutoff frequency) less than 10 kHz is proposed. The AGC is fabricated by a 0.18 {mu}m CMOS process. Under analog control mode, the AGC achieves a 70 dB dynamic range with a 3 dB-bandwidth larger than 60 MHz. Under digital control mode, through a 5-bit digital control word, the AGC shows a 64 dB gain control range by 2 dB each step with a gain error of less than 0.3 dB. The DC offset cancellation circuits can suppress the output DC offset voltage to be less than 1.5 mV, while the offset voltage of 40 mV is introduced into the input. The overall power consumption is less than 3.5 mA, and the die area is 800 x 300 {mu}m{sup 2}. (semiconductor integrated circuits)

Development of digital safety system logic and control

International Nuclear Information System (INIS)

Nishikawa, H.; Sakamoto, H.

1995-01-01

Advanced-BWR (ABWR) uses total digital control and instrumentation (C and I) system. In particular, ABWR adopts a newly developed safety system using advanced digital technology. In the presentation the digital safety system design, manufacturing and factory validation test method are shortly overviewed. The digital safety system consists of micro-processor based digital controllers, data and information transmission by optical fibers and human-machine interface using color flat displays. This new developed safety system meet the nuclear safety requirements such as high reliability, independence of divisions, operability and maintainability. (2 refs., 4 figs., 1 tab.)

Evaluation of mental workload on digital maintenance systems in nuclear power plants

International Nuclear Information System (INIS)

Hwang, S. L.; Huang, F. H.; Lin, J. C.; Liang, G. F.; Yenn, T. C.; Hsu, C. C.

2006-01-01

The purpose of this study is to evaluate operators' mental workload dealing with digital maintenance systems in Nuclear Power Plants. First of all, according to the factors affected the mental workload, a questionnaire was designed to evaluate the mental workload of maintenance operators at the second Nuclear Power (NPP) in Taiwan. Then, sixteen maintenance engineers of the Second NPP participated in the questionnaire survey. The results indicated that the mental workload was lower in digital systems than that in analog systems. Finally, a mental workload model based on Neural Network technique was developed to predict the workload of maintenance operators in digital maintenance systems. (authors)

Compact lidar system using laser diode, binary continuous wave power modulation, and an avalanche photodiode-based receiver controlled by a digital signal processor

Science.gov (United States)

Ardanuy, Antoni; Comerón, Adolfo

2018-04-01

We analyze the practical limits of a lidar system based on the use of a laser diode, random binary continuous wave power modulation, and an avalanche photodiode (APD)-based photereceiver, combined with the control and computing power of the digital signal processors (DSP) currently available. The target is to design a compact portable lidar system made all in semiconductor technology, with a low-power demand and an easy configuration of the system, allowing change in some of its features through software. Unlike many prior works, we emphasize the use of APDs instead of photomultiplier tubes to detect the return signal and the application of the system to measure not only hard targets, but also medium-range aerosols and clouds. We have developed an experimental prototype to evaluate the behavior of the system under different environmental conditions. Experimental results provided by the prototype are presented and discussed.

Optimized control strategy for crowbarless solid state modular power supply

International Nuclear Information System (INIS)

Upadhyay, R.; Badapanda, M.K.; Tripathi, A.; Hannurkar, P.R.; Pithawa, C.K.

2009-01-01

Solid state modular power supply with series connected IGBT based power modules have been employed as high voltage bias power supply of klystron amplifier. Auxiliary compensation of full wave inverter bridge with ZVS/ZCS operations of all IGBTs over entire operating range is incorporated. An optimized control strategy has been adopted for this power supply needing no output filter, making this scheme crowbarless and is presented in this paper. DSP based fully digital control with same duty cycle for all power modules, have been incorporated for regulating this power supply along with adequate protection features. Input to this power supply is taken directly from 11 kV line and the input system is intentionally made 24 pulsed to reduce the input harmonics, improve the input power factor significantly, there by requiring no line filters. Various steps have been taken to increase the efficiency of major subsystems, so as to improve the overall efficiency of this power supply significantly. (author)

Malaysian Preparation for Nuclear Power Plant Instrumentation and Control System

International Nuclear Information System (INIS)

Mohd Idris Taib; Nurfarhana Ayuni Joha; Kamarudin Sulaiman; Izhar Abu Hussin

2011-01-01

Instrumentation and Control System is required in Nuclear Power Plant for their safe and effective operation. The system is combination and integrated from detectors, actuators, analog system as well as digital system. Current design of system definitely follows of electronic as well as computer technology, with strictly follow regulation and guideline from local regulator as well as International Atomic Energy Agency. Commercial Off-The-Shelf products are extensively used with specific nucleonic instrumentation. Malaysian experiences depend on Reactor TRIGA PUSPATI Instrumentation and Control, Power Plant Instrumentation and Control as well as Process Control System. However Malaysians have capabilities to upgrade themself from Electronics, Computers, Electrical and Mechanical based. Proposal is presented for Malaysian preparation. (author)

Digital viscosity controller for fossil power plants; Controlador digital de viscosidad para plantas termoelectricas

Energy Technology Data Exchange (ETDEWEB)

Bautista B, Amberto; Ocampo P, Carlos; Gutierrez A, Ruben; Madinaveitia V, Miguel [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1990-12-31

Upon the need of increasing the efficiency of the existing fossil power plants in Mexico, the Instrumentation and Control Department of the Instituto de Investigaciones Electricas (IIE) designed and built a viscosity controller to enhance the fuel oil heating process. The system strategy, that allows the control either by temperature or viscosity considers, as an important element, the changing characteristics of the supplied fuels. The equipment that is utilized forms apart of the line Acquisition and Control System (ACS) developed at the same Institute, that has been successfully applied in other systems. [Espanol] Ante la necesidad de aumentar la eficiencia de las plantas termoelectricas existentes en Mexico, el Departamento de Instrumentacion y Control, del Instituto de Investigaciones Electricas (IIE), diseno y construyo un controlador de viscosidad para mejorar el proceso de calentamiento del aceite combustible. La estrategia del sistema, que permite controlar ya sea por viscosidad o por temperatura, considera como elemento importante las caracteristicas cambiantes de los combustibles suministrados. El equipo que se utiliza forma parte de la linea SAC (sistema de adquisicion y control), desarrollada en el mismo Instituto, que se ha aplicado satisfactoriamente en otros sistemas.

Digital viscosity controller for fossil power plants; Controlador digital de viscosidad para plantas termoelectricas

Energy Technology Data Exchange (ETDEWEB)

Bautista B, Amberto; Ocampo P, Carlos; Gutierrez A, Ruben; Madinaveitia V, Miguel [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

1989-12-31

Upon the need of increasing the efficiency of the existing fossil power plants in Mexico, the Instrumentation and Control Department of the Instituto de Investigaciones Electricas (IIE) designed and built a viscosity controller to enhance the fuel oil heating process. The system strategy, that allows the control either by temperature or viscosity considers, as an important element, the changing characteristics of the supplied fuels. The equipment that is utilized forms apart of the line Acquisition and Control System (ACS) developed at the same Institute, that has been successfully applied in other systems. [Espanol] Ante la necesidad de aumentar la eficiencia de las plantas termoelectricas existentes en Mexico, el Departamento de Instrumentacion y Control, del Instituto de Investigaciones Electricas (IIE), diseno y construyo un controlador de viscosidad para mejorar el proceso de calentamiento del aceite combustible. La estrategia del sistema, que permite controlar ya sea por viscosidad o por temperatura, considera como elemento importante las caracteristicas cambiantes de los combustibles suministrados. El equipo que se utiliza forma parte de la linea SAC (sistema de adquisicion y control), desarrollada en el mismo Instituto, que se ha aplicado satisfactoriamente en otros sistemas.

Design of monitoring and control system of digital power supply for HIMM based on microcontroller

International Nuclear Information System (INIS)

Yu Chunlei; Wu Fengjun; Gao Daqing; Yan Huaihai; Chen Youxin; Guo Yuxin; Huang Yuzhen; Zhang Huajian

2013-01-01

The touch screen control system is under development in Heavy Ion Medical Machine (HIMM) project. In this paper, the touch screen control system is studied in detail, which is driven by PIC24 microcontroller. According to the internal protocol of power system , control of power switch , waveform and state display, parameter setting are all implemented in this control system. The communication among microcontroller, FPGA board for power supply and state board is normal and stable during the test. Compared to analog switch control system, the local control system for HIMM is much more convenient and aesthetic, additionally the control accuracy is even higher. (authors)

Evaluation of digital fault-tolerant architectures for nuclear power plant control systems

International Nuclear Information System (INIS)

Battle, R.E.

1990-01-01

Four fault tolerant architectures were evaluated for their potential reliability in service as control systems of nuclear power plants. The reliability analyses showed that human- and software-related common cause failures and single points of failure in the output modules are dominant contributors to system unreliability. The four architectures are triple-modular-redundant (TMR), both synchronous and asynchronous, and also dual synchronous and asynchronous. The evaluation includes a review of design features, an analysis of the importance of coverage, and reliability analyses of fault tolerant systems. An advantage of fault-tolerant controllers over those not fault tolerant, is that fault-tolerant controllers continue to function after the occurrence of most single hardware faults. However, most fault-tolerant controllers have single hardware components that will cause system failure, almost all controllers have single points of failure in software, and all are subject to common cause failures. Reliability analyses based on data from several industries that have fault-tolerant controllers were used to estimate the mean-time-between-failures of fault-tolerant controllers and to predict those failures modes that may be important in nuclear power plants. 7 refs., 4 tabs

High speed and high functional inverter power supplies for plasma generation and control, and their performance

International Nuclear Information System (INIS)

Uesugi, Yoshihiko; Razzak, Mohammad A.; Kondo, Kenji; Kikuchi, Yusuke; Takamura, Shuichi; Imai, Takahiro; Toyoda, Mitsuhiro

2003-01-01

The Rapid development of high power and high speed semiconductor switching devices has led to their various applications in related plasma fields. Especially, a high speed inverter power supply can be used as an RF power source instead of conventional linear amplifiers and a power supply to control the magnetic field in a fusion plasma device. In this paper, RF thermal plasma production and plasma heating experiments are described emphasis placed on using a static induction transistor inverter at a frequency range between 200 kHz and 2.5 MHz as an RF power supply. Efficient thermal plasma production is achieved experimentally by using a flexible and easily operated high power semiconductor inverter power supply. Insulated gate bipolar transistor (IGBT) inverter power supplies driven by a high speed digital signal processor are applied as tokamak joule coil and vertical coil power supplies to control plasma current waveform and plasma equilibrium. Output characteristics, such as the arbitrary bipolar waveform generation of a pulse width modulation (PWM) inverter using digital signal processor (DSP) can be successfully applied to tokamak power supplies for flexible plasma current operation and fast position control of a small tokamak. (author)

Digital control systems. Verteilte Prozessleitsysteme

Energy Technology Data Exchange (ETDEWEB)

1984-01-01

With a distinct description of the systems properties thin regulation shall provide a latter transparency for the use of digital control systems. The application of the new technique shall be facilitated, incitations for the further development shall be given and the compatibility of the systems shall be advanced. Moreover, the regulation can be used as criteria catalogue for the evaluation of digital systems.

Licensing of digital Instrumentation and Control in Radioisotope Production Facility

International Nuclear Information System (INIS)

Abdel-Aziz, L.Kh.; Lashin, R.; Mostafa, W.

2012-01-01

In spite of the rapid development of digital I and C systems in all major industries, it has for several reasons been slower in nuclear power plants. The most important reason is that only a few new plants have been ordered worldwide during the last ten years. A second reason is connected to the efforts needed in providing adequate evidence that the digital I and C system can be used in safety and safety related applications. This issue is connected to the effort needed in obtaining adequate assurance that the digital I and C will fulfill its intended function and contain no unintended function in all possible operational states during its entire life cycle. This paper presents an acceptance criteria for licensing a digital instrumentation and control system in a Radioisotope Production Facility(1), which is under commissioning. The acceptance criteria ensure that the I and C systems are designed to reach the highest degree of reliability with respect to the function they perform, operators will have clear and accessible availability to data on every plant parameter, and also ensure that the safety objectives have been covered

Cyber Threat and vulnerability Analysis for Digital Assets of NPPs

International Nuclear Information System (INIS)

Oh, Eun Se; Seo, In Yong; Kim, See Hong

2009-01-01

Today's computer and communication technology breakthrough make increase plant floor replacement from analog instrumentation and control systems of nuclear power plants to a full-fledged digital system . The rich functionality and crisp accuracy are one of big advantages of digital technology adaptation, but use of open networks and inherited shared system resources (memory, network, etc.) are well known weak points of digital system. Intended or un-intended cyber attack throughout power plant digital control system's weak point may result to wide area of system failures and that easily defeats system operation and multiple protection safeguards. Well organized cyber security analysis for nuclear plant digital control systems (digital assets) are required

Evaluation of digital fault-tolerant architectures for nuclear power plant control systems

International Nuclear Information System (INIS)

Battle, R.E.

1990-01-01

This paper reports on four fault-tolerant architectures that were evaluated for their potential reliability in service as control systems of nuclear power plants. The reliability analyses showed that human- and software-related common cause failures and single points of failure in the output modules are dominant contributors to system unreliability. The four architectures are triple-modular-redundant, both synchronous and asynchronous, and also dual synchronous and asynchronous. The evaluation includes a review of design features, an analysis of the importance of coverage, and reliability analyses of fault-tolerant systems. Reliability analyses based on data from several industries that have fault-tolerant controllers were used to estimate the mean-time-between-failures of fault-tolerant controllers and to predict those failure modes that may be important in nuclear power plants

Digital image processing for radiography in nuclear power plants

International Nuclear Information System (INIS)

Heidt, H.; Rose, P.; Raabe, P.; Daum, W.

1985-01-01

With the help of digital processing of radiographic images from reactor-components it is possible to increase the security and objectiveness of the evaluation. Several examples of image processing procedures (contrast enhancement, density profiles, shading correction, digital filtering, superposition of images etc.) show the advantages for the visualization and evaluation of radiographs. Digital image processing can reduce some of the restrictions of radiography in nuclear power plants. In addition a higher degree of automation can be cost-saving and increase the quality of radiographic evaluation. The aim of the work performed was to to improve the readability of radiographs for the human observer. The main problem is lack of contrast and the presence of disturbing structures like weld seams. Digital image processing of film radiographs starts with the digitization of the image. Conventional systems use TV-cameras or scanners and provide a dynamic range of 1.5. to 3 density units, which are digitized to 256 grey levels. For the enhancement process it is necessary that the grey level range covers the density range of the important regions of the presented film. On the other hand the grey level coverage should not be wider than necessary to minimize the width of digitization steps. Poor digitization makes flaws and cracks invisible and spoils all further image processing

Digital redesign of anti-wind-up controller for cascaded analog system.

Science.gov (United States)

Chen, Y S; Tsai, J S H; Shieh, L S; Moussighi, M M

2003-01-01

The cascaded conventional anti-wind-up (CAW) design method for integral controller is discussed. Then, the prediction-based digital redesign methodology is utilized to find the new pulse amplitude modulated (PAM) digital controller for effective digital control of the analog plant with input saturation constraint. The desired digital controller is determined from existing or pre-designed CAW analog controller. The proposed method provides a novel methodology for indirect digital design of a continuous-time unity output-feedback system with a cascaded analog controller as in the case of PID controllers for industrial control processes with the presence of actuator saturations. It enables us to implement an existing or pre-designed cascaded CAW analog controller via a digital controller effectively.

Review report: safety and reliability issues on digital instrumentation and control systems in nuclear power plants and United States Nuclear Regulatory Commission`s dispositions

Energy Technology Data Exchange (ETDEWEB)

Watanabe, Norio; Suzudo, Tomoaki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1998-09-01

Recently, digital instrumentation and control (I and C) systems have been applied to nuclear power plants (NPPs) in various countries. Introduction of digital I and C systems, however, raises special issues on design, implementation, safety and licensing. Since FY 1997, the Japan Atomic Energy Research Institute (JAERI) has been carrying out a project, Study on Reliability of Digital I and C Systems, which includes extensive reviews of design approaches, technical standards, regulatory processes, especially, in the United States. This report summarizes the results from the study of National Research Council (NRC) and the U.S. Nuclear Regulatory Commission`s (USNRC`s) responses to the recommendations made by the NRC`s study. That study identified six technical key issues (system aspects of digital I and C technology, software quality assurance, common-mode software failure potential, safety and reliability assessment methods, human factors and man-machine interface, dedication of commercial off-the-shelf hardware and software) and two strategic key issues (case-by-case licensing process, adequacy of technical infrastructure) that arise from the introduction of digital I and C technology and then, made recommendations to the USNRC for coping with digital I and C applications. The USNRC responded to each recommendation and showed their own dispositions in which the USNRC agreed with most of the recommendations. In Japan, it is expected that introduction of digital I and C technology is inevitable in NPPs because the vendors are gradually discontinuing support and stocking of analog components. To cope with such situations, there is a need to develop and update the standards and guidelines applicable to digital I and C technology. The key issues and the USNRC`s dispositions provided in this report is believed to be useful for developing and updating them. (J.P.N.)

Digital control of the superconducting cavities for the LEP energy upgrade

International Nuclear Information System (INIS)

Gavallari, G.; Ciapala, E.

1992-01-01

The superconducting (SC) cavities for the LEP200 energy upgrade will be installed in units of 16 as for the present copper cavity system. Similar equipment will be used for RF power generation and distribution, for the low-level RF system and for digital control. The SC cavities and their associated equipment however require different interface hardware and new control software. To simplify routine operation control of the SC cavity units is made to resemble as closely as possible that of the existing units. Specific controls for the SC cavities at the equipment level, the facilities available and the integration of the SC cavity units into the LEP RF control system are described. (author)

Design and Implement a Digital H{sub {infinity}}Robust Controller for a MW-Class PMSG-Based Grid-Interactive Wind Energy Conversion System

Energy Technology Data Exchange (ETDEWEB)

Howlander, Abdul Motin [Faculty of Engineering, Univ. of the Ryukyus, Okinawa (Japan); Urasaki, Naomitsu [Faculty of Engineering, Univ. of the Ryukyus, Okinawa (Japan); Yona, Atsushi [Faculty of Engineering, Univ. of the Ryukyus, Okinawa (Japan); Senjyu, Tomonobu [Faculty of Engineering, Univ. of the Ryukyus, Okinawa (Japan); Saber, Ahmed Yousuf [Operation Technology, Irvine, CA (United States)

2013-04-15

A digital H{sub {infinity}}controller for a permanent magnet synchronous generator (PMSG) based wind energy conversion system (WECS) is presented. Wind energy is an uncertain fluctuating resource which requires a tight control management. So, it is still an exigent task for the control design engineers. The conventional proportional-integral (PI) control is not ideal during high turbulence wind velocities, and the nonlinear behavior of the power converters. These are raising interest towards the robust control concepts. The robust design is to find a controller, for a given system, such that the closed-loop system becomes robust that assurance high-integrity and fault tolerant control system, robust H{sub {infinity}}control theory has befallen a standard design method of choice over the past two decades in industrial control applications. The robust H{sub {infinity}}control theory is also gaining eminence in the WECS. Due to the implementation complexity for the continuous H{sub {infinity}}controller, and availability of the high speedy micro-controllers, the design of a sample-data or a digital H{sub {infinity}}controller is very important for the realistic implementation. But there isn’t a single research to evaluate the performance of the digital H{sub {infinity}}controller for the WECS. In this paper, the proposed digital H{sub {infinity}}controller schemes comprise for the both generator and grid interactive power converters, and the control performances are compared with the conventional PI controller and the fuzzy controller. Simulation results confirm the efficacy of the proposed method Energies 2013, 6 2085 which are ensured the WECS stabilities, mitigate shaft stress, and improving the DC-link voltage and output power qualities.

Finnish experiences on licensing and using of programmable digital systems in nuclear power plants

International Nuclear Information System (INIS)

Haapanen, P.; Maskuniitty, M.; Heimburger, H.; Hall, L.E.; Manninen, T.

1993-01-01

Finnish utility companies, Imatran Voima Oy (IVO) and Teollisuuden Voima (TVO), and the licensing authority, the Finnish Centre for Radiation and Nuclear Safety (STUK), are preparing for a new nuclear power plant in Finland. Plant vendors are proposing programmable digital automation systems for both the safety-related and the operational I and C (instrumentation and control) systems in this new unit. Also in existing plant units the replacement of certain old analog systems with state-of-the-art digital ones will become necessary in the years to come. Licensing of programmable systems for safety critical applications requires a new approach due to the special properties and failure modes of these systems. The major difficulties seem to be in the assessment and quantification of software reliability. The Technical Research Centre of Finland has in co-operation with the authority and the utilities conducted a project (AJA) to develop domestically applicable licensing requirements, guidelines and practices. International standards, guidelines and licensing practices have been analyzed in order to specify national licensing requirements. The paper describes and discusses the findings and experiences of the AJA project so far. The experience in introducing advanced programmable digital control and computer systems in the operating nuclear power plants will be covered briefly. Although these systems are not safety-related but systems of more general interest regarding nuclear safety, some routines regarding the licensing of safety- related systems have been followed. In these backfitting and replacement projects some experience have been gained in how to license safety-related programmable systems. (Author) 31 refs., 2 figs

A digital controlled negative high voltage power source for LINAC of HLS

International Nuclear Information System (INIS)

Gao Hui; Chen Jun; Hong Jun; Wang Weibing

2005-01-01

This paper introduces the working principle of a 10-80 kV negative high voltage power source for the electronic gun of the 200 MeV LINAC of NSRL, especially how to realize the switch power, voltage/current sampling, feedback control and microcontroller module. The firmware design for the SOC microcontroller of ADuC8xx and the application software design for PC are also presented. (authors)

Optimal pole shifting controller for interconnected power system

International Nuclear Information System (INIS)

Yousef, Ali M.; Kassem, Ahmed M.

2011-01-01

Research highlights: → Mathematical model represents a power system which consists of synchronous machine connected to infinite bus through transmission line. → Power system stabilizer was designed based on optimal pole shifting controller. → The system performances was tested through load disturbances at different operating conditions. → The system performance with the proposed optimal pole shifting controller is compared with the conventional pole placement controller. → The digital simulation results indicated that the proposed controller has a superior performance. -- Abstract: Power system stabilizer based on optimal pole shifting is proposed. An approach for shifting the real parts of the open-loop poles to any desired positions while preserving the imaginary parts is presented. In each step of this approach, it is required to solve a first-order or a second-order linear matrix Lyapunov equation for shifting one real pole or two complex conjugate poles, respectively. This presented method yields a solution, which is optimal with respect to a quadratic performance index. The attractive feature of this method is that it enables solutions of the complex problem to be easily found without solving any non-linear algebraic Riccati equation. The present power system stabilizer is based on Riccati equation approach. The control law depends on finding the feedback gain matrix, and then the control signal is synthesized by multiplying the state variables of the power system with determined gain matrix. The gain matrix is calculated one time only, and it works over wide range of operating conditions. To validate the power of the proposed PSS, a linearized model of a simple power system consisted of a single synchronous machine connected to infinite bus bar through transmission line is simulated. The studied power system is subjected to various operating points and power system parameters changes.

Optimal pole shifting controller for interconnected power system

Energy Technology Data Exchange (ETDEWEB)

Yousef, Ali M., E-mail: drali_yousef@yahoo.co [Electrical Eng. Dept., Faculty of Engineering, Assiut University (Egypt); Kassem, Ahmed M., E-mail: kassem_ahmed53@hotmail.co [Control Technology Dep., Industrial Education College, Beni-Suef University (Egypt)

2011-05-15

Research highlights: {yields} Mathematical model represents a power system which consists of synchronous machine connected to infinite bus through transmission line. {yields} Power system stabilizer was designed based on optimal pole shifting controller. {yields} The system performances was tested through load disturbances at different operating conditions. {yields} The system performance with the proposed optimal pole shifting controller is compared with the conventional pole placement controller. {yields} The digital simulation results indicated that the proposed controller has a superior performance. -- Abstract: Power system stabilizer based on optimal pole shifting is proposed. An approach for shifting the real parts of the open-loop poles to any desired positions while preserving the imaginary parts is presented. In each step of this approach, it is required to solve a first-order or a second-order linear matrix Lyapunov equation for shifting one real pole or two complex conjugate poles, respectively. This presented method yields a solution, which is optimal with respect to a quadratic performance index. The attractive feature of this method is that it enables solutions of the complex problem to be easily found without solving any non-linear algebraic Riccati equation. The present power system stabilizer is based on Riccati equation approach. The control law depends on finding the feedback gain matrix, and then the control signal is synthesized by multiplying the state variables of the power system with determined gain matrix. The gain matrix is calculated one time only, and it works over wide range of operating conditions. To validate the power of the proposed PSS, a linearized model of a simple power system consisted of a single synchronous machine connected to infinite bus bar through transmission line is simulated. The studied power system is subjected to various operating points and power system parameters changes.

Implementation of Adaptive Digital Controllers on Programmable Logic Devices

Science.gov (United States)

Gwaltney, David A.; King, Kenneth D.; Smith, Keary J.; Monenegro, Justino (Technical Monitor)

2002-01-01

Much has been made of the capabilities of FPGA's (Field Programmable Gate Arrays) in the hardware implementation of fast digital signal processing. Such capability also makes an FPGA a suitable platform for the digital implementation of closed loop controllers. Other researchers have implemented a variety of closed-loop digital controllers on FPGA's. Some of these controllers include the widely used proportional-integral-derivative (PID) controller, state space controllers, neural network and fuzzy logic based controllers. There are myriad advantages to utilizing an FPGA for discrete-time control functions which include the capability for reconfiguration when SRAM-based FPGA's are employed, fast parallel implementation of multiple control loops and implementations that can meet space level radiation tolerance requirements in a compact form-factor. Generally, a software implementation on a DSP (Digital Signal Processor) or microcontroller is used to implement digital controllers. At Marshall Space Flight Center, the Control Electronics Group has been studying adaptive discrete-time control of motor driven actuator systems using digital signal processor (DSP) devices. While small form factor, commercial DSP devices are now available with event capture, data conversion, pulse width modulated (PWM) outputs and communication peripherals, these devices are not currently available in designs and packages which meet space level radiation requirements. In general, very few DSP devices are produced that are designed to meet any level of radiation tolerance or hardness. The goal of this effort is to create a fully digital, flight ready controller design that utilizes an FPGA for implementation of signal conditioning for control feedback signals, generation of commands to the controlled system, and hardware insertion of adaptive control algorithm approaches. An alternative is required for compact implementation of such functionality to withstand the harsh environment

Advanced stability control of multi-machine power system by vips apparatus

Energy Technology Data Exchange (ETDEWEB)

Yokoyama, A [Tokyo Univ., Tokyo (Japan). Dept. of Electrical Engineering; Sekine, Y [Science Univ. of Tokyo, Tokyo (Japan). Dept. of Electrical Engineering

1994-12-31

New technology such as synchronized switching and power electronics will make it possible to change the configuration of transmission network, the impedances of transmission lines and the phase angles of voltage in the future power systems. This paper presents a comprehensive power system damping control by power electronics based variable impedance apparatus such as variable series capacitor and high speed phase shifter and also shows a novel switching-over control of transmission lines by synchronized switching for the first awing stability and damping enhancement. The control scheme discussed in this paper is based on an energy function of multi-machine power system and its time derivative. Its effectiveness is demonstrated by digital simulations and eigenvalue analysis in multi-machine test systems. It is demonstrated that multiple switching of transmission lines improves damping in the post-fault conditions. (author) 13 refs., 24 figs., 5 tabs.

Software environment and configuration for the DSP controlled NSLS booster power supplies

International Nuclear Information System (INIS)

Olsen, R.; Dabrowski, J.; Murray, J.

1993-01-01

The booster at the NSLS is being upgraded from 0.75 to 2 pulses per second by means of the installation of new dipole, quadrupole, and sextupole power supplies. The control system of these power supplies employs general purpose digital signal processing modules, and therefore, software support is required. This paper outlines the development system configuration, and the software environment

Cyber Threat and vulnerability Analysis for Digital Assets of NPPs

Energy Technology Data Exchange (ETDEWEB)

Oh, Eun Se; Seo, In Yong [Korea Electric Power research Institute, Daejeon (Korea, Republic of); Kim, See Hong [Korea Hydro and Nuclear Power Co., Seoul (Korea, Republic of)

2009-10-15

Today's computer and communication technology breakthrough make increase plant floor replacement from analog instrumentation and control systems of nuclear power plants to a full-fledged digital system . The rich functionality and crisp accuracy are one of big advantages of digital technology adaptation, but use of open networks and inherited shared system resources (memory, network, etc.) are well known weak points of digital system. Intended or un-intended cyber attack throughout power plant digital control system's weak point may result to wide area of system failures and that easily defeats system operation and multiple protection safeguards. Well organized cyber security analysis for nuclear plant digital control systems (digital assets) are required.

Results and Insights on the Impact of Smoke on Digital Instrumentation and Control

Energy Technology Data Exchange (ETDEWEB)

Tanaka, T. J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Nowlen, S. P. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2001-01-31

Smoke can cause interruptions and upsets in active electronics. Because nuclear power plants are replacing analog with digital instrumentation and control systems, qualification guidelines for new systems are being reviewed for severe environments such as smoke and electromagnetic interference. Active digital systems, individual components, and active circuits have been exposed to smoke in a program sponsored by the U.S. Nuclear Regulatory Commission. The circuits and systems were all monitored during the smoke exposure, indicating any immediate effects of the smoke. The major effect of smoke has been to increase leakage currents (through circuit bridging across contacts and leads) and to cause momentary upsets and failures in digital systems. This report summarizes two previous reports and presents new results from conformal coating, memory chip, and hard drive tests. The report describes practices for mitigation of smoke damage through digital system design, fire barriers, ventilation, fire suppressants, and post fire procedures.

Aircraft digital flight control technical review

Science.gov (United States)

Davenport, Otha B.; Leggett, David B.

1993-01-01

The Aircraft Digital Flight Control Technical Review was initiated by two pilot induced oscillation (PIO) incidents in the spring and summer of 1992. Maj. Gen. Franklin (PEO) wondered why the Air Force development process for digital flight control systems was not preventing PIO problems. Consequently, a technical review team was formed to examine the development process and determine why PIO problems continued to occur. The team was also to identify the 'best practices' used in the various programs. The charter of the team was to focus on the PIO problem, assess the current development process, and document the 'best practices.' The team reviewed all major USAF aircraft programs with digital flight controls, specifically, the F-15E, F-16C/D, F-22, F-111, C-17, and B-2. The team interviewed contractor, System Program Office (SPO), and Combined Test Force (CTF) personnel on these programs. The team also went to NAS Patuxent River to interview USN personnel about the F/A-18 program. The team also reviewed experimental USAF and NASA systems with digital flight control systems: X-29, X-31, F-15 STOL and Maneuver Technology Demonstrator (SMTD), and the Variable In-Flight Stability Test Aircraft (VISTA). The team also discussed the problem with other experts in the field including Ralph Smith and personnel from Calspan. The major conclusions and recommendations from the review are presented.

Flexible Microgrid Power Quality Enhancement Using Adaptive Hybrid Voltage and Current Controller

DEFF Research Database (Denmark)

He, Jinwei; Li, Yun Wei; Blaabjerg, Frede

2014-01-01

-pass/bandpass filters in the DG unit digital controller. Moreover, phase-locked loops are not necessary as the microgrid frequency deviation can be automatically identified by the power control loop. Consequently, the proposed control method provides opportunities to reduce DG control complexity, without affecting......To accomplish superior harmonic compensation performance using distributed generation (DG) unit power electronics interfaces, an adaptive hybrid voltage and current controlled method (HCM) is proposed in this paper. It shows that the proposed adaptive HCM can reduce the numbers of low...... the harmonic compensation performance. Comprehensive simulated and experimental results from a single-phase microgrid are provided to verify the feasibility of the proposed adaptive HCM approach....

Concept and design of a fully computerized control room for future nuclear power plant

International Nuclear Information System (INIS)

Hinz, W.; Kollmannsberger, J.

1991-01-01

The development of digital process control equipment and of safety engineering equipment together with the CRT - based information visualization systems is advanced to a state allowing process control of nuclear power plant to be done by these equipments. The systems have been tested in the control room of the fossil-fuel Staudinger reactor station, unit 5, and the computer-assisted PRISCA process information system has been tested in the Konvoi-type nuclear reactor series. These tests serve as a basis for further process control system development by Siemens KWU, to be used in their future nuclear power plants. The advantages of digital process control and CRT-based information display are intended to be used for further optimization of the man-machine interface in nuclear power plant. One important aspect is to give the control room personnel complete insight into the operational processes of the entire plant, and to establish for detail recognition for process monitoring a very close mental link between operators and the system processes. In addition, the control room operator has to be given appropriate means and tools for process monitoring and control, fulfilling the requirements of guaranteeing the plant's availability and safety. These requirements put very high demands on the process monitoring and control equipment. (orig.) [de

Specification of requirements for upgrades using digital instrument and control systems. Report prepared within the framework of the international working group on nuclear power plant control and instrumentation

International Nuclear Information System (INIS)

1999-01-01

The need to develop good specifications of requirements for instrument and control (I and C) systems applies throughout the world and is becoming more and more important as more upgrades are planned. Better guidance on how to develop good requirements specifications would support safer, more effective and more economical refits and upgrades. The need for this was pointed out by the IAEA International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI). This report is the result of a series of advisory and consultants meetings held by the IAEA in 1997 and 1998 in Vienna. The scope of the activities described covers a methodology for the determination of requirements and the development of the necessary specifications and plans needed through the life-cycle of digital instrumentation and control systems. It is restricted to technical aspects and indicates subjects which should be included in specifications and plans at different phases

Digital Control Techniques Based on Voltage Source Inverters in Renewable Energy Applications: A Review

Directory of Open Access Journals (Sweden)

Sohaib Tahir

2018-02-01

Full Text Available In the modern era, distributed generation is considered as an alternative source for power generation. Especially, need of the time is to provide the three-phase loads with smooth sinusoidal voltages having fixed frequency and amplitude. A common solution is the integration of power electronics converters in the systems for connecting distributed generation systems to the stand-alone loads. Thus, the presence of suitable control techniques, in the power electronic converters, for robust stability, abrupt response, optimal tracking ability and error eradication are inevitable. A comprehensive review based on design, analysis, validation of the most suitable digital control techniques and the options available for the researchers for improving the power quality is presented in this paper with their pros and cons. Comparisons based on the cost, schemes, performance, modulation techniques and coordinates system are also presented. Finally, the paper describes the performance evaluation of the control schemes on a voltage source inverter (VSI and proposes the different aspects to be considered for selecting a power electronics inverter topology, reference frames, filters, as well as control strategy.

Digital low level RF control system for the DESY TTF VUV-FEL Linac

International Nuclear Information System (INIS)

Ayvazyan, V.; Choroba, S.; Matyushin, A.; Moeller, G.; Petrosyan, G.; Rehlich, K.; Simrock, S.N.; Vetrov, P.

2005-01-01

In the RF system for the Vacuum Ultraviolet Free Electron Laser (VUV-FEL) Linac each klystron supplies RF power to up to 32 cavities. The superconducting cavities are operated in pulsed mode and high accelerating gradients close to the performance limit. The RF control of the cavity fields to the level of 10 -4 for amplitude and 0.1 degree for phase however presents a significant technical challenge due to the narrow bandwidth of the cavities which results in high sensitivity to perturbations of the resonance frequency by mechanical vibrations (microphonics) and Lorenz force detuning. The VUV-FEL Linac RF control system employs a completely digital feedback system to provide flexibility in the control algorithms, precise calibration of the accelerating field vector-sum, and extensive diagnostics and exception handling capabilities. The RF control algorithm is implemented in DSP (Digital Signal Processor) firmware and DOOCS (Distributed Object Oriented Control System) servers. The RF control system design objectives are discussed. Hardware and software design of the DSP based RF control are presented. (orig.)

Digital low level RF control system for the DESY TTF VUV-FEL Linac

Energy Technology Data Exchange (ETDEWEB)

Ayvazyan, V.; Choroba, S.; Matyushin, A.; Moeller, G.; Petrosyan, G.; Rehlich, K.; Simrock, S.N.; Vetrov, P.

2005-07-01

In the RF system for the Vacuum Ultraviolet Free Electron Laser (VUV-FEL) Linac each klystron supplies RF power to up to 32 cavities. The superconducting cavities are operated in pulsed mode and high accelerating gradients close to the performance limit. The RF control of the cavity fields to the level of 10{sup -4} for amplitude and 0.1 degree for phase however presents a significant technical challenge due to the narrow bandwidth of the cavities which results in high sensitivity to perturbations of the resonance frequency by mechanical vibrations (microphonics) and Lorenz force detuning. The VUV-FEL Linac RF control system employs a completely digital feedback system to provide flexibility in the control algorithms, precise calibration of the accelerating field vector-sum, and extensive diagnostics and exception handling capabilities. The RF control algorithm is implemented in DSP (Digital Signal Processor) firmware and DOOCS (Distributed Object Oriented Control System) servers. The RF control system design objectives are discussed. Hardware and software design of the DSP based RF control are presented. (orig.)

High-Speed, Low-Power ADC for Digital Beam Forming (DBF) Systems, Phase I

Data.gov (United States)

National Aeronautics and Space Administration — Ridgetop Group will design a high-speed, low-power silicon germanium (SiGe)-based, analog-to-digital converter (ADC) to be a key element for digital beam forming...

Device and Circuit Design Challenges in the Digital Subthreshold Region for Ultralow-Power Applications

Directory of Open Access Journals (Sweden)

Ramesh Vaddi

2009-01-01

Full Text Available In recent years, subthreshold operation has gained a lot of attention due to ultra low-power consumption in applications requiring low to medium performance. It has also been shown that by optimizing the device structure, power consumption of digital subthreshold logic can be further minimized while improving its performance. Therefore, subthreshold circuit design is very promising for future ultra low-energy sensor applications as well as high-performance parallel processing. This paper deals with various device and circuit design challenges associated with the state of the art in optimal digital subthreshold circuit design and reviews device design methodologies and circuit topologies for optimal digital subthreshold operation. This paper identifies the suitable candidates for subthreshold operation at device and circuit levels for optimal subthreshold circuit design and provides an effective roadmap for digital designers interested to work with ultra low-power applications.

Model for impact assessment in human factors engineering project of PWR plants with digital control

International Nuclear Information System (INIS)

Roedel, Frederico G.; Schirru, Roberto

2017-01-01

New nuclear power plants are being designed with the digital Instrumentation and Control (I and C) as the backbone for the functions of protection, control, monitoring and display and with digital Human-System Interface (HSI). In this new environment, rather than play physical control actions, the operators begin to act as decision makers and, within this context, the Human Factors Engineering (HFE) has become an integral part of the projects. As the operational experience with the use of digital I and C systems and HSI is limited since, besides the small number of applications, it is proprietary, the objective of this work is to carry out an assessment in order to identify the most relevant aspects of a digital HSI project. The proposed model is based on concepts of fuzzy logic, uses MATLAB for data processing, defines criteria for evaluation and quantification of impacts in the project and has been applied to the General Principles and the Guidelines presented in the NUREG-0700. The assessment indicated that the Guidelines for User-Interface Interaction and Management, for Information Display and for Computer-Based Procedures System should be carefully evaluated in the design of a digital HSI considering the new Users Tasks Demand, the Organization of HSI Elements and the Work Environment. (author)

Model for impact assessment in human factors engineering project of PWR plants with digital control

Energy Technology Data Exchange (ETDEWEB)

Roedel, Frederico G.; Schirru, Roberto, E-mail: froedel@nuclear.ufrj.br, E-mail: schirru@lmp.ufrj.br [Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Departamento de Engenharia Nuclear

2017-07-01

New nuclear power plants are being designed with the digital Instrumentation and Control (I and C) as the backbone for the functions of protection, control, monitoring and display and with digital Human-System Interface (HSI). In this new environment, rather than play physical control actions, the operators begin to act as decision makers and, within this context, the Human Factors Engineering (HFE) has become an integral part of the projects. As the operational experience with the use of digital I and C systems and HSI is limited since, besides the small number of applications, it is proprietary, the objective of this work is to carry out an assessment in order to identify the most relevant aspects of a digital HSI project. The proposed model is based on concepts of fuzzy logic, uses MATLAB for data processing, defines criteria for evaluation and quantification of impacts in the project and has been applied to the General Principles and the Guidelines presented in the NUREG-0700. The assessment indicated that the Guidelines for User-Interface Interaction and Management, for Information Display and for Computer-Based Procedures System should be carefully evaluated in the design of a digital HSI considering the new Users Tasks Demand, the Organization of HSI Elements and the Work Environment. (author)

Communications and control for electric power systems: Final report

Energy Technology Data Exchange (ETDEWEB)

Kirkham, H.

1998-04-01

This report is a summary of some of the work done on the Communications and Control project, with particular emphasis on the achievements during the years 1986--1996. During those years, the project moved away from concern with dispersed storage and generation and its impact on power system operation (the team was responsible for studies in this area, and for making a power system simulator that included DSG), and became involved in more concrete work aimed at applying high-tech solutions to problems of power system communications and control. This report covers work done at JPL on the following topics: (1) the measurement of electric and magnetic fields, both ac and dc; (2) the use of optical power to supply low-power electronics; (3) the design of a fault-tolerant communication system designed for distribution automation; and (4) a digital phase locked loop that allows the use of low-power transmitting electronics to recreate a good-quality signal at the receiver. In a report of this kind, only the results and highlights of the work are described.

47 CFR 73.9001 - Redistribution control of digital television broadcasts.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 4 2010-10-01 2010-10-01 false Redistribution control of digital television... RADIO SERVICES RADIO BROADCAST SERVICES Digital Broadcast Television Redistribution Control § 73.9001 Redistribution control of digital television broadcasts. Licensees of TV broadcast stations may utilize the...

How does a change in the control room design affect diagnostic strategies in nuclear power plants?

International Nuclear Information System (INIS)

Kim, Dong Young; Kim, Jonghyun

2014-01-01

Recently, main control rooms have been considerably changed by modern computer techniques. Some of the features that distinguish digital control rooms from conventional, analog rooms in nuclear power plants include advanced alarm systems, graphic information display systems, computerized procedure systems, and soft control. These features can bring changes in operator tasks, changing the characteristics of tasks or creating new tasks for operators. It is especially expected that these features may bring out changes in the operator's diagnostic tasks and strategies in a digital control room as compared with an analog control room. This study investigates the differences in the operator's diagnostic tasks and strategies in analog and digital control rooms. This study also attempts to evaluate how new systems in a digital control room affect diagnostic strategies. Three different approaches, which are complementary, are used to identify diagnostic strategies in the digital control room and in the analog control room: (1) observation in the simulator, (2) interview with operators, and (3) a literature review. The results show that the digital control room introduces new diagnosis strategies compared with the analog control room while also changing the characteristics of the strategies, mostly by gaining more support from the computerized system. (author)

Hardware replacements and software tools for digital control computers

International Nuclear Information System (INIS)

Walker, R.A.P.; Wang, B-C.; Fung, J.

1996-01-01

Technological obsolescence is an on-going challenge for all computer use. By design, and to some extent good fortune, AECL has had a good track record with respect to the march of obsolescence in CANDU digital control computer technology. Recognizing obsolescence as a fact of life, AECL has undertaken a program of supporting the digital control technology of existing CANDU plants. Other AECL groups are developing complete replacement systems for the digital control computers, and more advanced systems for the digital control computers of the future CANDU reactors. This paper presents the results of the efforts of AECL's DCC service support group to replace obsolete digital control computer and related components and to provide friendlier software technology related to the maintenance and use of digital control computers in CANDU. These efforts are expected to extend the current lifespan of existing digital control computers through their mandated life. This group applied two simple rules; the product, whether new or replacement should have a generic basis, and the products should be applicable to both existing CANDU plants and to 'repeat' plant designs built using current design guidelines. While some exceptions do apply, the rules have been met. The generic requirement dictates that the product should not be dependent on any brand technology, and should back-fit to and interface with any such technology which remains in the control design. The application requirement dictates that the product should have universal use and be user friendly to the greatest extent possible. Furthermore, both requirements were designed to anticipate user involvement, modifications and alternate user defined applications. The replacements for hardware components such as paper tape reader/punch, moving arm disk, contact scanner and Ramtek are discussed. The development of these hardware replacements coincide with the development of a gateway system for selected CANDU digital control

High-Speed, Low-Power ADC for Digital Beam Forming (DBF) Systems, Phase II

Data.gov (United States)

National Aeronautics and Space Administration — In Phase 1, Ridgetop Group designed a high-speed, yet low-power silicon germanium (SiGe)-based, analog-to-digital converter (ADC) to be a key element for digital...

Low-Cost Digital Implementation of Proportional-Resonant Current Controllers for PV Inverter Applications Using Delta Operator

DEFF Research Database (Denmark)

Sera, Dezso; Kerekes, Tamas; Lungeanu, Marian

2005-01-01

the possibility of selective harmonic compensation. However, in case of digital implementation on a low-cost fixedpoint DSP, the limited computational power and the limited numerical representation precision can restrict the utilization of it. The present paper proposes a different way of digital implementation...... of the P+Resonant controller with selective harmonic compensation on a low-cost fixed-point DSP. The resonant part of the P+R has been implemented as a second order filter based on Delta operator. The current controller, together with harmonic compensation for the 3rd, 5th, and 7th harmonics has been...

Cardinal principle and application practice of 3D digital model design for nuclear power plant

International Nuclear Information System (INIS)

Wang Ruobing; Wu Yan

2005-01-01

The practical application of 3D digital model design at nuclear power plants was introduced in detail in the paper. The whole process for system choice, program constitution, model design and project practice were also summarized. By demonstrating the cardinal principal and application practice of 3D digital model design as an important sub-project of CGNPC Digital Plant, the paper validates the rationality and validity of the major architecture system and program configuration of the digital plant, carries out beneficial attempt and study in the overall power plant life engineering management and site practice, and has achieved significant engineering and social benefits. The success of practices in the project accelerates the extended and extensive application of Digital Plant in the operation and maintenance simulation of Daya Bay and Ling'ao Nuclear Power Plants, and the engineering design management for Ling'ao II and III of CGNPC on a consolidated basis. (authors)

New technology for BWR power plant control and instrumentation

International Nuclear Information System (INIS)

Takano, Yoshiyuki; Nakamura, Makoto; Murata, Fumio.

1992-01-01

Nuclear power plants are facing strong demands for higher reliability and cost-performance in their control and instrumentation systems. To meet these needs, Hitachi is developing advanced control and instrumentation technology by rationalizing the conventional technology in that field. The rationalization is done through the utilization of reliable digital technology and optical transmission technology, and others, which are now commonly used in computer applications. The goal of the development work is to ensure safe, stable operation of the plant facilities and to secure harmony between man and machine. To alleviate the burdens of the operators, the latest electronic devices are being employed to create an advanced man-machine interface, and to promote automatic operation of the plant based upon the automatic operation of individual systems. In addition, the control and instrumentation system, including the safety system, incorporates more and more digital components in order to further enhance the reliability and maintainability of the plant. (author)

Centralized digital control of accelerators

International Nuclear Information System (INIS)

Melen, R.E.

1984-01-01

Upon careful examination of the architecture of SLAC's computer control systems, it becomes evident that the distribution of the systems' intelligence generally falls into tree-like layers. The first layer typically consists of a central computer complex incorporating one or more relatively large and powerful processors. The more modern systems use state-of-the-art 32-bit processors with several megabytes of RAM and several hundreds of megabytes of disk memory. Further, they support extensive user-friendly operating systems and program development facilities. The second layer typically consists of several smaller processors which are downloaded from the central complex and whose primary task is to provide data acquisition and distribution. The more modern systems are 16-bit processors with several hundred kilobytes of RAM and no disk memory. The third layer typically consists of several tens or hundreds of micro-processors, each dedicated to a single device. The micro-processors for these ''dedicated intelligent controllers'' are small and inexpensive and typically require less than 32 kilobytes of RAM or EPROM memory. Their hardware may be general purpose in nature or may be built into the architecture of the device itself. Figure 5 illustrates several of the relevant features of each of these layers. This paper serves to illustrate that SLAC is commited to the centralized digital control of its accelerators

Direct drive digital servo press with high parallel control

Science.gov (United States)

Murata, Chikara; Yabe, Jun; Endou, Junichi; Hasegawa, Kiyoshi

2013-12-01

Direct drive digital servo press has been developed as the university-industry joint research and development since 1998. On the basis of this result, 4-axes direct drive digital servo press has been developed and in the market on April of 2002. This servo press is composed of 1 slide supported by 4 ball screws and each axis has linearscale measuring the position of each axis with high accuracy less than μm order level. Each axis is controlled independently by servo motor and feedback system. This system can keep high level parallelism and high accuracy even with high eccentric load. Furthermore the 'full stroke full power' is obtained by using ball screws. Using these features, new various types of press forming and stamping have been obtained by development and production. The new stamping and forming methods are introduced and 'manufacturing' need strategy of press forming with high added value and also the future direction of press forming are also introduced.

Distortions in power spectra of digitized signals - II: Suggested solution

International Nuclear Information System (INIS)

Njau, E.C.

1982-04-01

In Part I of this report we developed analytical expressions which represent exactly the energy density spectra of ''digitization processes'' that are essentially involved in spectral analysis of continuous signals. Besides, we related the spectral energy density of each digitization process to the parameters of the exact spectral energy density of the corresponding signal. On this basis, we briefly discussed the forms of distortions (or false structures) which are present in normally computed power spectra when the corresponding spectra of the digitization processes are not sufficiently decoupled from or nullified in the computed spectra. The biggest worry with regard to these distortions is not only that they may mask the actual information contained in the original signal, but also they may tempt the researcher to establish false characteristics about the signal involved. It is, in this context, that any reasonable method that could be used (even conditionally) to pinpoint false structures in computed power spectra would be both timely and useful. A simple, handy guidance through which some portions of computed energy density spectra which are dominated by the false structures mentioned above, can be located is presented herein. Equations are presented which give the various frequencies at which false peaks may be located in such ''contaminated'' portions of computed energy density spectra. The occurrence of frequency shifts in computed power spectra is also briefly discussed. (author)

An approach based on defense-in-depth and diversity (3D) for the reliability assessment of digital instrument and control systems of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Silva, Paulo Adriano da; Saldanha, Pedro L.C., E-mail: pasilva@cnen.gov.b, E-mail: Saldanha@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Coord. Geral de Reatores Nucleares; Melo, Paulo F. Frutuoso e, E-mail: frutuoso@nuclear.ufrj.b [Universidade Federal do Rio de Janeiro (PEN/COPPE/UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-Graduacao em Engenharia. Programa de Engenharia Nuclear; Araujo, Ademir L. de [Associacao Brasileira de Ensino Universitario (UNIABEU), Angra dos Reis, RJ (Brazil)

2011-07-01

The adoption of instrumentation and control (I and C) digital technology has been slower in nuclear power plants. The reason has been unfruitful efforts to obtain evidence in order to prove that I and C systems can be used in nuclear safety systems, for example, the Reactor Protection System (RPS), ensuring the proper operation of all its functions. This technology offers a potential improvement for safety and reliability. However, there still no consensus about the model to be adopted for digital systems software to be used in reliability studies. This paper presents the 3D methodology approach to assess digital I and C reliability. It is based on the study of operational events occurring in NPPs. It is easy to identify, in general, the level of I and C system reliability, showing its key vulnerabilities, enabling to trace regulatory actions to minimize or avoid them. This approach makes it possible to identify the main types of digital I and C system failure, with the potential for common cause failures as well as evaluating the dominant failure modes. The MAFIC-D software was developed to assist the implementation of the relationships between the reliability criteria, the analysis of relationships and data collection. The results obtained through this tool proved to be satisfactory and complete the process of regulatory decision-making from licensing I and C digital of NPPs and call still be used to monitor the performance of I and C digital post-licensing during the lifetime of the system, providing the basis for the elaboration of checklists of regulatory inspections. (author)

An approach based on defense-in-depth and diversity (3D) for the reliability assessment of digital instrument and control systems of nuclear power plants

International Nuclear Information System (INIS)

Silva, Paulo Adriano da; Saldanha, Pedro L.C.

2011-01-01

The adoption of instrumentation and control (I and C) digital technology has been slower in nuclear power plants. The reason has been unfruitful efforts to obtain evidence in order to prove that I and C systems can be used in nuclear safety systems, for example, the Reactor Protection System (RPS), ensuring the proper operation of all its functions. This technology offers a potential improvement for safety and reliability. However, there still no consensus about the model to be adopted for digital systems software to be used in reliability studies. This paper presents the 3D methodology approach to assess digital I and C reliability. It is based on the study of operational events occurring in NPPs. It is easy to identify, in general, the level of I and C system reliability, showing its key vulnerabilities, enabling to trace regulatory actions to minimize or avoid them. This approach makes it possible to identify the main types of digital I and C system failure, with the potential for common cause failures as well as evaluating the dominant failure modes. The MAFIC-D software was developed to assist the implementation of the relationships between the reliability criteria, the analysis of relationships and data collection. The results obtained through this tool proved to be satisfactory and complete the process of regulatory decision-making from licensing I and C digital of NPPs and call still be used to monitor the performance of I and C digital post-licensing during the lifetime of the system, providing the basis for the elaboration of checklists of regulatory inspections. (author)

A Digital Motion Control System for Large Telescopes

Science.gov (United States)

Hunter, T. R.; Wilson, R. W.; Kimberk, R.; Leiker, P. S.

2001-05-01

We have designed and programmed a digital motion control system for large telescopes, in particular, the 6-meter antennas of the Submillimeter Array on Mauna Kea. The system consists of a single robust, high-reliability microcontroller board which implements a two-axis velocity servo while monitoring and responding to critical safety parameters. Excellent tracking performance has been achieved with this system (0.3 arcsecond RMS at sidereal rate). The 24x24 centimeter four-layer printed circuit board contains a multitude of hardware devices: 40 digital inputs (for limit switches and fault indicators), 32 digital outputs (to enable/disable motor amplifiers and brakes), a quad 22-bit ADC (to read the motor tachometers), four 16-bit DACs (that provide torque signals to the motor amplifiers), a 32-LED status panel, a serial port to the LynxOS PowerPC antenna computer (RS422/460kbps), a serial port to the Palm Vx handpaddle (RS232/115kbps), and serial links to the low-resolution absolute encoders on the azimuth and elevation axes. Each section of the board employs independent ground planes and power supplies, with optical isolation on all I/O channels. The processor is an Intel 80C196KC 16-bit microcontroller running at 20MHz on an 8-bit bus. This processor executes an interrupt-driven, scheduler-based software system written in C and assembled into an EPROM with user-accessible variables stored in NVSRAM. Under normal operation, velocity update requests arrive at 100Hz from the position-loop servo process running independently on the antenna computer. A variety of telescope safety checks are performed at 279Hz including routine servicing of a 6 millisecond watchdog timer. Additional ADCs onboard the microcontroller monitor the winding temperature and current in the brushless three-phase drive motors. The PID servo gains can be dynamically changed in software. Calibration factors and software filters can be applied to the tachometer readings prior to the application of

Digital Sliding Mode Control of Anti-Lock Braking System

Directory of Open Access Journals (Sweden)

MITIC, D. B.

2013-02-01

Full Text Available The control of anti-lock braking system is a great challenge, because of the nonlinear and complex characteristics of braking dynamics, unknown parameters of vehicle environment and system parameter variations. Using some of robust control methods, such as sliding mode control, can be a right solution for these problems. In this paper, we introduce a novel approach to design of ABS controllers, which is based on digital sliding mode control with only input/output measurements. The relay term of the proposed digital sliding mode control is filtered through digital integrator, reducing the chattering phenomenon in that way, and the additional signal of estimated modelling error is introduced into control algorithm to enhance the system steady-state accuracy. The given solution was verified in real experimental framework and the obtained results were compared with the results of implementation of two other digital sliding mode control algorithms. It is shown that it gives better system response, higher steady-state accuracy and smaller chattering.

Digital compensation of receiver clipping for DVB reception on low-power mobile

NARCIS (Netherlands)

Linnartz, J.P.M.G.; Rietman, R.

2007-01-01

Battery life-time is a critical issue for digital television (DVB) viewing on mobile phones. The number of quantization steps used in the analog-to-digital converter (ADC) is an important factor in the total power consumption of a DVB receiver. The OFDM signals require a large resolution of the ADC.

Reliability Analysis Study of Digital Reactor Protection System in Nuclear Power Plant

International Nuclear Information System (INIS)

Guo, Xiao Ming; Liu, Tao; Tong, Jie Juan; Zhao, Jun

2011-01-01

The Digital I and C systems are believed to improve a plants safety and reliability generally. The reliability analysis of digital I and C system has become one research hotspot. Traditional fault tree method is one of means to quantify the digital I and C system reliability. Review of advanced nuclear power plant AP1000 digital protection system evaluation makes clear both the fault tree application and analysis process to the digital system reliability. One typical digital protection system special for advanced reactor has been developed, which reliability evaluation is necessary for design demonstration. The typical digital protection system construction is introduced in the paper, and the process of FMEA and fault tree application to the digital protection system reliability evaluation are described. Reliability data and bypass logic modeling are two points giving special attention in the paper. Because the factors about time sequence and feedback not exist in reactor protection system obviously, the dynamic feature of digital system is not discussed

Using the digital reactor control systems at NPP

International Nuclear Information System (INIS)

Schirl, G.; Hertel, J.

2006-01-01

A conception of application of the digital reactor control systems (RCS) at NPP is presented. The digital RCS architecture and safety ensuring are considered. The strategy and algorithm of the operating NPP equipping with the new digital RCS are given too [ru

Realization of manchester encoding and decoding and fast-speed communication for digital power supply based on FPGA

International Nuclear Information System (INIS)

Chen Huanguang; Xu Ruinian; Shen Tianjian; Li Deming

2008-01-01

A design and simulation to realize the process of Manchester encoding and decoding, to realize the process of SPI communication between FPGA and DSP, using Altera company's Quartus II IDE on FPGA is presented in this paper. And the application on the digital power supply controller with Manchester communication by optical fiber is introduced. (authors)

Development of Risk Assessment Technology for Low Power, Shutdown and Digital I and C Systems

Energy Technology Data Exchange (ETDEWEB)

Jang, Seung Cheol; Kang, Hyung Gook; Lim, Ho Gon; Park, Jin Hee; Eom, Heung Sub; Kim, Tae Woon; Ha, Jae Joo

2005-04-15

There are two technical areas to deal with in the project; the low power and shutdown probabilistic safety assessment (PSA), and the digital I and C PSA. The scope and contents of each area could be summarized as follows: Quality assessment of a LPSD PSA model for a Korean Standard Nuclear Power Plant (KSNP), Quality improvement of the KSNP LPSD PSA model in the following four technical areas; plant operating status (POS), initiating event analysis, determination of success criteria, accident sequence analysis, Development of the LPSD risk management technologies, Unavailability analysis of Digital safety systems such as Digital Plant Protection System (DPPS) and Digital Engineered Safety Feature Actuation System (DESFAS), Impact analysis of the digital safety systems on plant risks throughout of the digital plant risk models for evaluating core damage frequency (CDF) and large early release frequency (LERF), Study on the methodologies for treating digital-specific problems in the digital I and C PSA such as reliability of safety-critical software, common cause failure (CCF) of digital components, fault coverage, etc.

Development of Risk Assessment Technology for Low Power, Shutdown and Digital I and C Systems

International Nuclear Information System (INIS)

Jang, Seung Cheol; Kang, Hyung Gook; Lim, Ho Gon; Park, Jin Hee; Eom, Heung Sub; Kim, Tae Woon; Ha, Jae Joo

2005-04-01

There are two technical areas to deal with in the project; the low power and shutdown probabilistic safety assessment (PSA), and the digital I and C PSA. The scope and contents of each area could be summarized as follows: Quality assessment of a LPSD PSA model for a Korean Standard Nuclear Power Plant (KSNP), Quality improvement of the KSNP LPSD PSA model in the following four technical areas; plant operating status (POS), initiating event analysis, determination of success criteria, accident sequence analysis, Development of the LPSD risk management technologies, Unavailability analysis of Digital safety systems such as Digital Plant Protection System (DPPS) and Digital Engineered Safety Feature Actuation System (DESFAS), Impact analysis of the digital safety systems on plant risks throughout of the digital plant risk models for evaluating core damage frequency (CDF) and large early release frequency (LERF), Study on the methodologies for treating digital-specific problems in the digital I and C PSA such as reliability of safety-critical software, common cause failure (CCF) of digital components, fault coverage, etc

Performance analysis of the closed digital control circuit of reactor A-1

International Nuclear Information System (INIS)

Karpeta, C.; Volf, K.; Stirsky, P.; Roubal, S.; Muellerova, H.

A computer-aided analysis is presented of the optimum digital control of the A-1 nuclear power plant reactor. The effect of index weighting matrices on the quality of control processes was studied for a deterministic case using the Separation Theorem for a linear time-discrete regulator problem with a quadratic performance index. Some properties were also investigated of the Kalman filter serving the process state estimation. An analysis is reported for a stochastic case, this for both time-invariant and time-variant Kalman filter gain matrix. (author)

Audio power amplifier techniques with energy efficient power conversion. Vol. 1

Energy Technology Data Exchange (ETDEWEB)

Nielsen, Karsten

1998-04-01

A fundamental study of both analog and digital pulse modulation methods is carried out. A novel class of multi-level pulse modulation methods - Phase Shifted Carrier Pulse Width Modulation (PSCPWM) - is introduced and show to have several advantageous features, primarily caused by the much improved synthesis of the modulating signal. Enhanced digital pulse modulation methods for digital Pulse Modulation Amplifier (PMA) systems are investigated, and a simple methodology for digital PWM modulator synthesis is devised. It is concluded, that the modulator performance is not a limitation in the system, regardless of the domain of modulator implementation. Power conversion in PMA systems is adressed from the perspective of both linearity and efficienty optimization. Based on detailed studies of the distortion mechanisms in the power conversion stage it is concluded, that this is the fundamental limitation on system performance due to several physical limitations. The analysis of general power stage efficiency concludes that dramatic improvements in energy efficiency are possible with PMA systems that are optimized for efficiency. A control system design methodology is devised as a platform for synthesis of robust control systems. Investigations of three fundamental control structures show that even simple control systems offer a remarkable value, although the considered topologies also have their limitations which is verified by practical evaluation in hardware. A novel control method is introduced - Multivariable Enhanced Cascade Control (MECC). MECC provides flexible control over all essential system parameters and is furthermore simple in realization. Practical evaluation of a MECC based PMA shows state-of-the-art performance. The application of non-linear control methods is investigated with the introduction of an enhanced non-linear control/modulator topology. Although the non-linear controller is theoretically interesting, the method proves to suffer from various

Advanced control and instrumentation systems in nuclear power plants. Design, verification and validation

International Nuclear Information System (INIS)

Haapanen, P.

1995-01-01

The Technical Committee Meeting on design, verification and validation of advanced control and instrumentation systems in nuclear power plants was held in Espoo, Finland on 20 - 23 June 1994. The meeting was organized by the International Atomic Energy Agency's (IAEA) International Working Group's (IWG) on Nuclear Power Plant Control and Instrumentation (NPPCI) and on Advanced Technologies for Water Cooled Reactors (ATWR). VTT Automation together with Imatran Voima Oy and Teollisuuden Voima Oy responded about the practical arrangements of the meeting. In total 96 participants from 21 countries and the Agency took part in the meeting and 34 full papers and 8 posters were presented. Following topics were covered in the papers: (1) experience with advanced and digital systems, (2) safety and reliability analysis, (3) advanced digital systems under development and implementation, (4) verification and validation methods and practices, (5) future development trends. (orig.)

Adoption of digital safety protection system in Japan

International Nuclear Information System (INIS)

Ogiso, Z.

1998-01-01

The application of micro-processor-based digital controllers has been widely propagated among various industries in recent years. While in the nuclear power plant industry, the application of them has also been expanding gradually starting from non-safety related systems, taking advantage of their reliability and maintainability over the conventional analog devices. Based on the careful study of the feasibility of digital controllers to the safety protection system, the Tokyo Electric Power Company proposed on May 1989 the adoption of digital controllers to the safety protection system in the Application for Permission of Establishment of Kashiwazaki-Kariwa units 6 and 7 (ABWR-1350Mwe each). MITI, Ministry of International Trade and Industry, the Japanese regulatory body for electric power generating facilities, had approved this application after careful review. This paper describes a series of supporting activities leading to the MITI's approval of the digital safety protection system and the MITI's licensing activities. (author)

76 FR 44821 - Digital Low Power Television, Television Translator, and Television Booster Stations and To Amend...

Science.gov (United States)

2011-07-27

...] Digital Low Power Television, Television Translator, and Television Booster Stations and To Amend Rules... Digital Low Power Television, Television Translator, and Television Booster Stations and to Amend Rules... translator facilities in the 700 MHz band. These provisions provide procedures for a primary wireless...

76 FR 72849 - Digital Low Power Television, Television Translator, and Television Booster Stations and To Amend...

Science.gov (United States)

2011-11-28

...] Digital Low Power Television, Television Translator, and Television Booster Stations and To Amend Rules... for Digital Low Power Television, Television Translator, and Television Booster Stations and to Amend... television, TV translator, and Class A television station DTV licensees''). The Commission has also revised...

Development of digital device based work verification system for cooperation between main control room operators and field workers in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Lee, Seung Min, E-mail: jewellee@kaeri.re.kr [Korea Atomic Energy Research Institute, 305-353, 989-111 Daedeok-daero, Yuseong-gu, Daejeon (Korea, Republic of); Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1, Guseong-dong, Yuseong-gu, Daejeon 305-701 (Korea, Republic of); Lee, Hyun Chul, E-mail: leehc@kaeri.re.kr [Korea Atomic Energy Research Institute, 305-353, 989-111 Daedeok-daero, Yuseong-gu, Daejeon (Korea, Republic of); Ha, Jun Su, E-mail: junsu.ha@kustar.ac.ae [Department of Nuclear Engineering, Khalifa University of Science Technology and Research, Abu Dhabi P.O. Box 127788 (United Arab Emirates); Seong, Poong Hyun, E-mail: phseong@kaist.ac.kr [Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1, Guseong-dong, Yuseong-gu, Daejeon 305-701 (Korea, Republic of)

2016-10-15

Highlights: • A digital device-based work verification and cooperation support system was developed. • Requirements were derived by interviewing field operators having experiences with mobile-based work support systems. • The usability of the proposed system was validated by conducting questionnaire surveys. • The proposed system will be useful if the manual or the set of guidelines is well constructed. - Abstract: Digital technologies have been applied in the nuclear field to check task results, monitor events and accidents, and transmit/receive data. The results of using digital devices have proven that these devices can provide high accuracy and convenience for workers, allowing them to obtain obvious positive effects by reducing their workloads. In this study, as one step forward, a digital device-based cooperation support system, the nuclear cooperation support and mobile documentation system (Nu-COSMOS), is proposed to support communication between main control room (MCR) operators and field workers by verifying field workers’ work results in nuclear power plants (NPPs). The proposed system consists of a mobile based information storage system to support field workers by providing various functions to make workers more trusted by MCR operators; also to improve the efficiency of meeting, and a large screen based information sharing system supports meetings by allowing both sides to share one medium. The usability of this system was estimated by interviewing field operators working in nuclear power plants and experts who have experience working as operators. A survey to estimate the usability of the suggested system and the suitability of the functions of the system for field working was conducted for 35 subjects who have experience in field works or with support system development-related research. The usability test was conducted using the system usability scale (SUS), which is widely used in industrial usability evaluation. Using questionnaires

Development of digital device based work verification system for cooperation between main control room operators and field workers in nuclear power plants

International Nuclear Information System (INIS)

Lee, Seung Min; Lee, Hyun Chul; Ha, Jun Su; Seong, Poong Hyun

2016-01-01

Highlights: • A digital device-based work verification and cooperation support system was developed. • Requirements were derived by interviewing field operators having experiences with mobile-based work support systems. • The usability of the proposed system was validated by conducting questionnaire surveys. • The proposed system will be useful if the manual or the set of guidelines is well constructed. - Abstract: Digital technologies have been applied in the nuclear field to check task results, monitor events and accidents, and transmit/receive data. The results of using digital devices have proven that these devices can provide high accuracy and convenience for workers, allowing them to obtain obvious positive effects by reducing their workloads. In this study, as one step forward, a digital device-based cooperation support system, the nuclear cooperation support and mobile documentation system (Nu-COSMOS), is proposed to support communication between main control room (MCR) operators and field workers by verifying field workers’ work results in nuclear power plants (NPPs). The proposed system consists of a mobile based information storage system to support field workers by providing various functions to make workers more trusted by MCR operators; also to improve the efficiency of meeting, and a large screen based information sharing system supports meetings by allowing both sides to share one medium. The usability of this system was estimated by interviewing field operators working in nuclear power plants and experts who have experience working as operators. A survey to estimate the usability of the suggested system and the suitability of the functions of the system for field working was conducted for 35 subjects who have experience in field works or with support system development-related research. The usability test was conducted using the system usability scale (SUS), which is widely used in industrial usability evaluation. Using questionnaires

Optimized linear motor and digital PID controller setup used in Mössbauer spectrometer

Science.gov (United States)

Kohout, Pavel; Kouřil, Lukáš; Navařík, Jakub; Novák, Petr; Pechoušek, Jiří

2014-10-01

Optimization of a linear motor and digital PID controller setup used in a Mössbauer spectrometer is presented. Velocity driving system with a digital PID feedback subsystem was developed in the LabVIEW graphical environment and deployed on the sbRIO real-time hardware device (National Instruments). The most important data acquisition processes are performed as real-time deterministic tasks on an FPGA chip. Velocity transducer of a double loudspeaker type with a power amplifier circuit is driven by the system. Series of calibration measurements were proceeded to find the optimal setup of the P, I, D parameters together with velocity error signal analysis. The shape and given signal characteristics of the velocity error signal are analyzed in details. Remote applications for controlling and monitoring the PID system from computer or smart phone, respectively, were also developed. The best setup and P, I, D parameters were set and calibration spectrum of α-Fe sample with an average nonlinearity of the velocity scale below 0.08% was collected. Furthermore, the width of the spectral line below 0.30 mm/s was observed. Powerful and complex velocity driving system was designed.

Digitization and simulation realization of full range control system for steam generator water level

International Nuclear Information System (INIS)

Qian Hong; Ye Jianhua; Qian Fei; Li Chao

2010-01-01

In this paper, a full range digital control system for the steam generator water level is designed by a control scheme of single element control and three-element cascade feed-forward control, and the method to use the software module configuration is proposed to realize the water level control strategy. This control strategy is then applied in the operation of the nuclear power simulation machine. The simulation result curves indicate that the steam generator water level maintains constant at the stable operation condition, and when the load changes, the water level changes but finally maintains the constant. (authors)

Design of an ultra-low-power digital processor for passive UHF RFID tags

Energy Technology Data Exchange (ETDEWEB)

Shi Wanggen; Zhuang Yiqi; Li Xiaoming; Wang Xianghua; Jin Zhao; Wang Dan, E-mail: wanggen_shi@163.co [Key Laboratory of the Ministry of Education for Wide Band-Gap Semiconductor Materials and Devices, Institute of Microelectronics, Xidian University, Xi' an 710071 (China)

2009-04-15

A new architecture of digital processors for passive UHF radio-frequency identification tags is proposed. This architecture is based on ISO/IEC 18000-6C and targeted at ultra-low power consumption. By applying methods like system-level power management, global clock gating and low voltage implementation, the total power of the design is reduced to a few microwatts. In addition, an innovative way for the design of a true RNG is presented, which contributes to both low power and secure data transaction. The digital processor is verified by an integrated FPGA platform and implemented by the Synopsys design kit for ASIC flows. The design fits different CMOS technologies and has been taped out using the 2P4M 0.35 mum process of Chartered Semiconductor.

The analysis and realization of state-matrix parameters of a digital adjuster used for accelerator power system

International Nuclear Information System (INIS)

Long Yindong; Zhao Long; Chinese Academy of Sciences, Beijing; Qiao Weimin; Jing Lan

2008-01-01

The power-control system of synchronized accelerator must be a high definition and real time system. In this paper we introduced a platform for parameter analysis and realization. As a necessary part of the digital adjustor, it is achieved by the method of state-space equation based on the Cyclone II for improving performance of the accelerator power-control system. With the platform, the object control in a precision range of up to 10 64 can be realized, depending on the optimum arithmetic and the MATLAB functions. In addition, considering the actual environment, the parameters the actual demands can be better met by choosing the parameters, providing a necessary support to achieve the higher definition and better real time adjustor. (authors)

A distributed control approach for power and energy management in a notional shipboard power system

Science.gov (United States)

Shen, Qunying

The main goal of this thesis is to present a power control module (PCON) based approach for power and energy management and to examine its control capability in shipboard power system (SPS). The proposed control scheme is implemented in a notional medium voltage direct current (MVDC) integrated power system (IPS) for electric ship. To realize the control functions such as ship mode selection, generator launch schedule, blackout monitoring, and fault ride-through, a PCON based distributed power and energy management system (PEMS) is developed. The control scheme is proposed as two-layer hierarchical architecture with system level on the top as the supervisory control and zonal level on the bottom as the decentralized control, which is based on the zonal distribution characteristic of the notional MVDC IPS that was proposed as one of the approaches for Next Generation Integrated Power System (NGIPS) by Norbert Doerry. Several types of modules with different functionalities are used to derive the control scheme in detail for the notional MVDC IPS. Those modules include the power generation module (PGM) that controls the function of generators, the power conversion module (PCM) that controls the functions of DC/DC or DC/AC converters, etc. Among them, the power control module (PCON) plays a critical role in the PEMS. It is the core of the control process. PCONs in the PEMS interact with all the other modules, such as power propulsion module (PPM), energy storage module (ESM), load shedding module (LSHED), and human machine interface (HMI) to realize the control algorithm in PEMS. The proposed control scheme is implemented in real time using the real time digital simulator (RTDS) to verify its validity. To achieve this, a system level energy storage module (SESM) and a zonal level energy storage module (ZESM) are developed in RTDS to cooperate with PCONs to realize the control functionalities. In addition, a load shedding module which takes into account the reliability

Research on digital PID control algorithm for HPCT

International Nuclear Information System (INIS)

Zeng Yi; Li Rui; Shen Tianjian; Ke Xinhua

2009-01-01

Digital PID applied in high-precision HPCT (High-precision current transducer) based on Digital Signal Processor (DSP) TMS320F2812 and special D/A converter was researched. By using increment style PID Control algorithm, the stability and precision of high-precision HPCT output voltage is improved. On basis of deeply analysing incremental digital PID, the scheme model of HPCT is proposed, the feasibility simulation using Matlab is given. Practical hardware circuit verified the incremental PID has closed-loop control process in tracking HPCT output voltage. (authors)

Computationally efficient methods for digital control

NARCIS (Netherlands)

Guerreiro Tome Antunes, D.J.; Hespanha, J.P.; Silvestre, C.J.; Kataria, N.; Brewer, F.

2008-01-01

The problem of designing a digital controller is considered with the novelty of explicitly taking into account the computation cost of the controller implementation. A class of controller emulation methods inspired by numerical analysis is proposed. Through various examples it is shown that these

DESIGN AND TESTING OF A DIGITAL REGULATOR FOR FERMILAB MAGNET POWER SYSTEMS

Energy Technology Data Exchange (ETDEWEB)

Li Vigni, Vincenzo [Palermo U.

2012-01-01

In this thesis, the design of a digitally controlled DC power system for testing conventional and superconducting magnets is proposed. The designed PID controller performances have been tested by the 30kA test stand for superconducting magnets, Vertical Magnet Test Facility (VMTF), which is hosted at the Fermilab Magnet Test Facility (MTF). The system is implemented on a National Instruments CompactRIO and both real-time and FPGA targets are programmed. A full 24-bit PID algorithm is coded and successfully tested by a manual tuning approach. An automated tuning algorithm is then introduced. As it will be shown by simulation and experimental results, the proposed system meets all design specifications. The current loop stability is up to 14 times better than the existing regulator and a control accuracy less than 4 ppm is achieved. Shorted-bus tests of the PID regulator have been successfully performed on the VMTF power system. In order to test the generalization capability of the designed system towards different types of magnets, the system has been easily adapted to and tested on the 10kA conventional magnet test stand (Stand C at Fermilab). As shown by experimental results, the designed PID controller features really high performancesin terms of steady-state accuracy and effectiveness of the tuning algorithm.

An automatic regulating control system for a graphite moderated reactor using digital techniques

International Nuclear Information System (INIS)

Carvalho Goncalves Junior, J. de.

1989-01-01

The work propose an automatic regulating control system for a graphite moderated reactor using digital techniques. The system uses a microcomputer to monitor the power and the period, to run the control algorithm, and to generate electronic signals to excite the motor, which moves vertically the control rod banks. A nuclear reactor simulator was developed to test the control system. The simulator consists of a software based on the point kinetic equations and implanted in an analogical computer. The results show that this control system has a good performance and versatility. In addition, the simulator is capable of reproducing with accuracy the behavior of a nuclear reactor. (author)

Human factors issues in digital system design and implementation

International Nuclear Information System (INIS)

Galletti, Greg S.

1998-01-01

A goal of the U.S. Nuclear Regulatory Commission (NRC) is to ensure safety in the application of digital equipment upgrades to nuclear power plant control rooms and local control stations. One of the areas of specific interest is the integration of digital technology into existing analog control, display, and information systems and the implications of such integration for operators in regard to their use of this new equipment to safely operate the plant. This paper is a discussion of human performance issues related to the introduction of such digital equipment into operating nuclear power plants. (author)

Integration technique of digital I and C replacement and its Critical Digital Review procedure

International Nuclear Information System (INIS)

Huang, Hui-Wen; Yang, Wen-Long

2013-01-01

Highlights: ► A digital I and C replacement integration technique have been developed. ► Establishment of Nuclear Power Plant Digital Replacement Integration Guideline. ► Preliminary Investigation on I and C System Digitalization. ► Evaluation on I and C System Digitalization. ► Establishment of I and C System Digitalization Architectures. -- Abstract: Institute of Nuclear Energy Research (INER) developed a digital Instrumentation and Control (I and C) replacement integration technique on the basis of requirement of the three existing nuclear power plants (NPPs), which are Chin–Shan (CS) NPP, Kuo–Sheng (KS) NPP, and Maanshan (MS) NPP, in Taiwan, and also developed the related Critical Digital Review (CDR) procedure. The digital I and C replacement integration technique includes: (1) Establishment of Nuclear Power Plant Digital Replacement Integration Guideline, (2) Preliminary Investigation on I and C System Digitalization, (3) Evaluation on I and C System Digitalization, and (4) Establishment of I and C System Digitalization Architectures. These works can be a reference for performing I and C system digital replacement integration of the three existing NPPs of Taiwan Power Company (TPC). A CDR is the review for a critical system digital I and C replacement. The major reference of this procedure is EPRI TR-1011710 (2005) “Handbook for Evaluating Critical Digital Equipment and Systems” which was published by the Electric Power Research Institute (EPRI). With this document, INER developed a TPC-specific CDR procedure. Currently, CDR becomes one of the policies for digital I and C replacement in TPC. The contents of this CDR procedure include: Scope, Responsibility, Operation Procedure, Operation Flow Chart, CDR review items. The CDR review items include the comparison of the design change, Software Verification and Validation (SV and V), Failure Mode and Effects Analysis (FMEA), Evaluation of Diversity and Defense-in-depth (D3), Evaluation of

Development of Testing Platform for Digital I and C System in Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Park, G. Y.; Kim, Y. M.; Jeong, C. H. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2013-10-15

According to digitalization of the NPP (Nuclear Power Plant) I and C (Instrumentation and Control) system, cyber threats against I and C system are increased. Moreover, the complexity of I and C system are increased due to adopt the up-to-date technologies (i. e., smart sensor, wireless network, and Field Programmable Gate Array / Complex Programmable Logic Device) into NPP's I and C system. For example, new issues such as cyber threat are introduced from digitalized I and C systems and components to replace obsolete analog equipment in existing NPPs. Furthermore, use of wireless communication, FPGA/CPLD, and smart sensor could introduce new considerations such as Defense-in-Depth and Diversity. Therefore, the proof testing for digital I and C system is required to verify the adverse effect from use of up-to-date digital technologies and identify the criteria to resolve and mitigate (or prevent) the (possibility of) effects. The objective of this study is developing the Testing Platform for the proof testing. The digital I and C System Test Platform is implemented using test platform hardware, component software, and architectural design. The digital I and C testing platform includes the safety-related PLC and relevant ladder logics, Windows-based C++ codes for host PC. For software, there are seven spike models to confirm the each module's functionality and generate/monitor the signals to/from PLCs. For future work, digital I and C System Test Platform architecture will be implemented using spike models. And a set of acceptance test against cyber security, smart sensor, wireless network, and FPGA/CPLD will be conducted using digital I and C System Test Platform.

Development of Testing Platform for Digital I and C System in Nuclear Power Plants

International Nuclear Information System (INIS)

Park, G. Y.; Kim, Y. M.; Jeong, C. H.

2013-01-01

According to digitalization of the NPP (Nuclear Power Plant) I and C (Instrumentation and Control) system, cyber threats against I and C system are increased. Moreover, the complexity of I and C system are increased due to adopt the up-to-date technologies (i. e., smart sensor, wireless network, and Field Programmable Gate Array / Complex Programmable Logic Device) into NPP's I and C system. For example, new issues such as cyber threat are introduced from digitalized I and C systems and components to replace obsolete analog equipment in existing NPPs. Furthermore, use of wireless communication, FPGA/CPLD, and smart sensor could introduce new considerations such as Defense-in-Depth and Diversity. Therefore, the proof testing for digital I and C system is required to verify the adverse effect from use of up-to-date digital technologies and identify the criteria to resolve and mitigate (or prevent) the (possibility of) effects. The objective of this study is developing the Testing Platform for the proof testing. The digital I and C System Test Platform is implemented using test platform hardware, component software, and architectural design. The digital I and C testing platform includes the safety-related PLC and relevant ladder logics, Windows-based C++ codes for host PC. For software, there are seven spike models to confirm the each module's functionality and generate/monitor the signals to/from PLCs. For future work, digital I and C System Test Platform architecture will be implemented using spike models. And a set of acceptance test against cyber security, smart sensor, wireless network, and FPGA/CPLD will be conducted using digital I and C System Test Platform

A digitized wide range channel for new instrumentation and control system of PUSPATI TRIGA Reactor (RTP)