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AbstractAbstract
[en] At Beijing's Institute of Nuclear Energy Technology a low-cost digital protection system is being developed by using commercial grade components, splitting critical and non-critical functions, and simplifying hardware and software. A prototype is due to be in operation by the end of 1994. (author)
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Li Fu; Yang Zijue; An Zhencai; Zhang Liangju, E-mail: lifu@inet.tsinghua.edu.cn2002
AbstractAbstract
[en] The reactor protection system (RPS) used in the 10 MW high-temperature gas-cooled reactor is the first digital RPS designed and operated in China. In order to ensure its safety and reliability and to reduce the development risk and cost, some measures had to be taken. The measures adopted in the development process include the architecture of defense-in-depth, commercial grade hardware, prototype development model, separation of safety class software and non-safety class software, deterministic behavior of safety software, etc. The measures adopted in the verification and validation (V and V) process include effective dedication on the commercial grade hardware, emphasis on the assessment of the requirements and specifications, emphasis on the demonstration and testing, thorough testing for the safety function, long period demonstration operation, application of automatic test system to improve the efficiency of V and V processes, etc. As a result, this first digital RPS has passed the safety assessment of the National Nuclear Safety Authority. Its performance and safety are proven to be confident and assuring through the demonstration and testing. Thus, the design and V and V process of the first digital protection system in China was successful
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S0029549302001930; Copyright (c) 2002 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.; Country of input: International Atomic Energy Agency (IAEA)
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CONTROL SYSTEMS, ENGINEERED SAFETY SYSTEMS, ENRICHED URANIUM REACTORS, EXPERIMENTAL REACTORS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HELIUM COOLED REACTORS, HTGR TYPE REACTORS, ON-LINE CONTROL SYSTEMS, ON-LINE SYSTEMS, REACTORS, RESEARCH AND TEST REACTORS, TEST FACILITIES, TEST REACTORS, TESTING
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AbstractAbstract
[en] The consideration of making good use of the-state-of-the-arts technology in designing advanced Instrumentation and Control System architecture is discussed. A fully distributed and fully micro-computerized, local network based Instrumentation and Control System is designed for the HTR-10 reactor. The advantages of the system architecture include high reliability and availability, flexibility, economics, etc. It also fits for other production processes
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A Supplemet to the volum; Special Issue of HTGR (Part 1).
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Chinese Journal of Nuclear Science and Engineering; ISSN 0258-0918; ; CODEN HYGODG; v. 13(4); p. 158-162
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Zheng Jian; Yang Zijue; Wang Liqiang
Proceedings of the 10th national conference on nuclear electronics and nuclear detection technology2000
Proceedings of the 10th national conference on nuclear electronics and nuclear detection technology2000
AbstractAbstract
[en] In the field of digital radiography (DR) nowadays, a low noise, digital, highly integrated data acquisition (DAQ) subsystem is very important. The traditional DAQ subsystems of DR are based on the preamplifiers with resistors and capacitors in the feed back loop. The author describes a new kind of preamplifier based on switched integrator
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Chinese Nuclear Society and Chinese Electronics Society, Beijing (China). Nuclear Electroics and Nuclear Detection Technology Subcociety; 587 p; 2000; p. 27-30; 10. national conference on nuclear electronics and nuclear detection technology; Chengdu (China); 7-12 Sep 2000; Available from China Nuclear Information Centre
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[en] In 1984 work started on developing and building a 5MW test heating reactor (THR) at the Institute of Nuclear Energy Technology of Tsinghua University, China. The I and C system for the THR was developed at the same time. Although a fully computerized instrumentation and control (I and C) system was feasible and should perform substantially better than a conventional hard-wired system, its advantages were not yet fully appreciated by those heading the project or the authorities who were concerned about reliability. Lack of experience in using such systems was a real concern. The compromise design included a mixture in which the computers replaced conventional instruments wherever possible but not in performing or actuating protection functions for which a conventional protection system was provided. As the THR is a new type of reactor, it seemed appropriate to the designers initially to have the computer provide only monitoring functions. Its role will be extended to include control functions after sufficient operating experience is gained. (author)
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[en] The design, functions, application, and the relationship to the conventional nuclear reactor instrument of the process computer system for 5 MW nuclear district heating plant are discussed. The hardware configuration of the process computer system is briefly described. It is a dual PDP11/73 computer system with automatic diagnosis and switch. The intelligent, rugged data measurement stations IMP (Isolated Measurement Pods) is briefly discussed. Last, basic idea of the real time view aid generation system specially developed for the system is introduced
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[en] The configuration and design polestar of the digital protection system controlling high temperature gas-cooled test reactor (HTR-10) are introduced briefly, and the particular measures to enhance its reliability are described. The test results of the system show that the digital protection not only enhances the visibility and operability for operators and effectively reduce the volume and cost, but also enhance reliability of the protection system for the reactor
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Nuclear Power Engineering; ISSN 0258-0926; ; v. 23(3); p. 50-53
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AbstractAbstract
[en] In the field of digital radiography (DR) nowadays, a low noise, digital, highly integrated data acquisition (DAQ) subsystem is very important. The traditional DAQ subsystems of DR are based on the preamplifiers with resistors and capacitors in the feed back loop. The author describes a new kind of preamplifier based on switched integrator
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Journal Article
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Nuclear Electronics and Detection Technology; ISSN 0258-0934; ; v. 22(2); p. 152-154
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AbstractAbstract
[en] The protection system installed in 10 MW High-Temperature-gas-Cooled Reactor (HTR-10) is the first digital protection system in China. The verification and validation (V and V) process to the digital protection system which is the mandatory way to ensure its quality and reliability is executed for the first time in China. The main characteristics of the development process of the digital protection system of HTR-10 can be summarized as: the development cycle is in a prototype way, commercial grade hardware is adopted, the safety software is separated from other supporting software to make the critical safety software easy to be tested. The corresponding verification and validation process is tightly couple with every stage of the development, and the V and V of the requirement and specification, V and V of safety software and the testing of the integrated protection system are the most important V and V activities. As a result, the digital protection system is successfully passed the safety review and is licensed to be used in HTR-10
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Nuclear Power Engineering; ISSN 0258-0926; ; v. 22(6); p. 508-512
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[en] The system provides the means of monitor,control and protection for 5 MW THR. It covers six subsystems, they are the nutron flux measurement system, the reactor protection system, the reactor control system, the alarm system, the on-line process computer system and the central control room. The control system overall design is based on the type and the use of 5 MW THR, as well as nuclear and thermal characteristics of the reactor. The design follows the relative code and standards for nuclear power plants safety design
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