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秦山核电厂反应堆保护系统及其相关设备数字化改造规划和实施策略 被引量:9

Upgrading Planning and Executive Strategy for Reactor Protection System and Relative Equipment in Qinshan Nuclear Power Plant
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摘要 秦山核电厂采用数字化技术改造了基于模拟技术的反应堆保护系统。与此同时,采用同一数字化安全仪控平台对堆外核测系统进行了改造。文章结合该厂原有系统的历史和现状,在广泛了解目前国际上数字化安全仪控平台的发展状况、国外核电厂在该领域的应用现状的基础上制定适合秦山核电厂工程实际的改造规划和"以我为主,中外合作,充分利用国内技术力量"的实施策略。分析了影响和制约在役核电厂反应堆保护系统及其相关设备改造的主要因素,并对可实施性作总体评估,以了解改造过程中所面临的问题和困难,预先准备相应对策,确保技术改造目标的实现。 Qinshan Nuclear Power Plant(QNPP) is the first nuclear power plant in China which completed the reactor protection system(RPS) upgrading with new digital safety instrumentation and control(IC) platform instead of original analog system.At the same time,the nuclear instrumentation system(NIS) was upgraded with the same digital IC platform.For adapting QNPP's actual engineering situation,the upgrading planning was taken by comprehensively investigating current development and application of digital safety IC platform in the worldwide scope and by reviewing plant's original systems operation history.The project executive strategy-QNPP's leading role with necessary overseas cooperation and internal technical supports as great as possible,was determined.Some significant factors might influence and restrict the RPS and relative equipment upgrading executive actions in an operating NPP were analyzed.Finally,the engineering feasibility was briefly assessed to recognize the anticipated issues and difficulties and to prepare the relative solutions in advance for the purpose of ensuring the RPS upgrading objectives completely realized.
作者 蒋祖跃
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2010年第1期65-69,共5页 Atomic Energy Science and Technology
关键词 反应堆保护系统 数字化 改造 规划 策略 reactor protection system digitalisation upgrading planning strategy
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参考文献5

  • 1国家核安全局.HAF102-2004核动力厂设计安全规定[S].北京:中国法制出版社,2004.
  • 2国家技术监督局.GB/T 5963-1995 反应堆保护系统的隔离准则[S].北京:中国标准出版社,1995.
  • 3IEC 60880-1986 Software for computer in the safety systems of nuclear power stations[S].Geneva:IEC,1986.
  • 4IEC 60880-2-2000 Software for computer in the safety systems of nuclear power stations part 2:Software aspects of defense against common cause failures,use of software tools of pre-developed software[S].Geneva:IEC,2000.
  • 5NUREG-0800 Rev.4 Section 7.0 Instrumentation and controls-overview of review process[S].Washington D.C.,U.S.:NRC,1997.

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