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    • 22. 发明公开
    • 소프트웨어를 이용한 고장 모사 장치 및 방법
    • 使用软件进行故障的设备和方法
    • KR1020120086500A
    • 2012-08-03
    • KR1020110007768
    • 2011-01-26
    • 한국원자력연구원한국수력원자력 주식회사
    • 이영준김만철장승철최종균
    • G06F9/455
    • G06F11/3676G06F11/3688
    • PURPOSE: A malfunction simulating device using software and a method thereof are provided to reduce costs for measuring hardware malfunction by defining a position of the malfunction in detail through the software and preventing permanent damage to hardware. CONSTITUTION: A malfunction simulating unit(110) executes a malfunction simulation by recording an operation value in a specific position in a software executing area for the malfunction simulation. A malfunction detecting unit(130) detects malfunction generated in software by comparing an execution value of the software with a standard execution value. A scanning unit calculates an execution address by scanning the software executing area. The scanning unit includes a counter(111) which counts the number of times of execution according to each command by scanning the software executing area and a distribution calculating unit(112) which selects a section about the number of times of execution to calculate a distribution chart.
    • 目的:提供使用软件的故障模拟装置及其方法,以通过软件详细定义故障的位置并防止对硬件的永久性损坏来降低测量硬件故障的成本。 构成:故障模拟单元(110)通过在用于故障模拟的软件执行区域中的特定位置记录操作值来执行故障模拟。 故障检测单元(130)通过将软件的执行值与标准执行值进行比较来检测在软件中产生的故障。 扫描单元通过扫描软件执行区域来计算执行地址。 扫描单元包括:计数器(111),其通过扫描软件执行区域而根据每个命令对执行次数进行计数;分布计算单元(112),其选择关于执行次数的部分来计算分布 图表。
    • 23. 发明公开
    • 통합 디지털 공학적 안전설비-기기제어계통 및 그 방법
    • 集成数字工程安全特征 - 组件控制系统及其方法
    • KR1020080074346A
    • 2008-08-13
    • KR1020070013299
    • 2007-02-08
    • 한국원자력연구원한국수력원자력 주식회사
    • 김동훈허섭이철권황인구박기용이현철이동영최종균권기춘
    • G21D3/04G21C7/36
    • Y02E30/39G21D3/04G21D3/001Y02E30/40
    • An integrated digital engineered safety features component control system and a method thereof are provided to improve the safety and an economical efficiency of a power plant by preventing a malfunction of the engineered safety features component in a single processor. An integrated digital engineered safety features component control system includes m group controllers(401) and a plurality of loop controllers(402). The m group controllers operate independently. The loop controllers of a dual structure operate independently. Each of m group controllers receives an engineered safety features start signal which is generated from a plant protection system and a radiation monitoring system. Each of m group controllers determines an operation of a first nuclear steam supply system engineered safety feature and a second system engineered safety feature by performing a corresponding logic in response to the start signal, and outputs an operation signal of the engineered safety features. Each of the loop controller of the dual structure controls engineered safety features by performing a control logic for the engineered safety features. The m group controller and the loop controller are formed in one system.
    • 提供集成的数字工程安全特征部件控制系统及其方法,以通过防止单个处理器中的工程安全特征部件的故障来提高发电厂的安全性和经济效率。 集成的数字工程安全特征组件控制系统包括m组控制器(401)和多个环路控制器(402)。 m组控制器独立运行。 双重结构的回路控制器独立运行。 m组控制器中的每一个接收从工厂保护系统和辐射监测系统产生的工程安全特征启动信号。 m组控制器中的每一个通过响应于起始信号执行相应的逻辑来确定第一核蒸汽供应系统工程安全特征的操作和第二系统设计的安全特征,并输出工程安全特征的操作信号。 双重结构的每个回路控制器通过执行工程安全功能的控制逻辑来控制工程安全功能。 m组控制器和回路控制器形成在一个系统中。
    • 24. 发明公开
    • 독립적 이중화 구조 리던던시를 갖는 디지털 원자로보호계통 및 그 방법
    • 基于可编程逻辑控制器的数字反应器保护系统,具有独立的双重结构冗余每通道及其方法
    • KR1020080051417A
    • 2008-06-11
    • KR1020060122449
    • 2006-12-05
    • 한국원자력연구원
    • 이철권허섭김동훈황인구박기용이현철이동영최종균김창회
    • G21D3/04G21C7/36G21D3/00G21C7/00
    • Y02E30/39
    • A programmable logic controller based digital reactor protection system with an independent double structure redundancy per a channel and a method thereof are provided to improve stability and reliability of a nuclear power plant so as to maintain the nuclear power plant in a safety state and to prevent radioactive rays and radioactive materials from being leaked to the outside. A programmable logic controller based digital reactor protection system with an independent double structure redundancy per a channel includes four channels(200) of a redundancy structure which operates independently. Each channel includes a first group and a second group. The first group includes a first bistable processor(201a) among double bistable processors and a first coincidence processor(202a) among double coincidence processors. The second group includes a second bistable processor(201b) among the dual bistable processors and a second coincidence processor(202b) among the dual coincidence processors. The first and second bistable processors generate trip signals by comparing input signals with a predetermined stored trip set value on the basis of a plurality of sensing signals indicating states of reactor systems. The first and second coincidence processors generate a final trip signal by performing 2/4 logic compounding of the trip signals outputted from the bistable processors of a corresponding group among the four channels. A reactor is stopped by driving a reactor trip breaker or engineered safety features are operated by driving an engineered safety features-component control system according to the final trip signal by independent operation of the first and second groups of the redundancy structure in each channel.
    • 提供了一种基于可编程序逻辑控制器的数字反应堆保护系统,其具有每个通道独立的双重结构冗余及其方法,以提高核电厂的稳定性和可靠性,从而将核电站维持在安全状态并防止放射性 射线和放射性物质泄漏到外面。 每个通道具有独立的双重结构冗余的基于可编程逻辑控制器的数字电抗器保护系统包括独立操作的冗余结构的四个通道(200)。 每个通道包括第一组和第二组。 第一组包括双双稳态处理器之中的第一双稳态处理器(201a)和双重重合处理器中的第一重合处理器(202a)。 第二组包括双双稳态处理器中的第二双稳态处理器(201b)和双重重合处理器中的第二重合处理器(202b)。 第一和第二双稳态处理器基于指示反应堆系统的状态的多个感测信号,通过将输入信号与预定存储的跳闸设定值进行比较来产生跳闸信号。 第一和第二重合处理器通过执行从四个通道中的相应组的双稳态处理器输出的跳闸信号的2/4逻辑复合来产生最终跳闸信号。 通过驱动反应器跳闸断路器来停止反应堆,或通过独立操作每个通道中的冗余结构的第一组和第二组,通过根据最终跳闸信号驱动工程安全特征组件控制系统来操作工程安全特征。
    • 26. 发明授权
    • 원자력 발전소 중대사고 대응 장치 및 방법
    • 用于复制核电厂严重事故的装置和方法
    • KR101553892B1
    • 2015-09-17
    • KR1020140052697
    • 2014-04-30
    • 한국원자력연구원
    • 허섭김창회장통일손광섭박재창최종균황인구
    • G21D3/06G21C9/00
    • Y02E30/40G21D3/06G21C9/00G21C17/00
    • 본 발명은 원자력 발전소에서 사고 발생시, 보다 효과적으로 대응할 수 있도록 하기 위한 것으로, 적어도 하나의 계측기로부터 원자력 발전소의 사고 증상과 관련된 계측 정보를 감지하는 신호수신부와, 상기 신호수신부에서 계측된 값들에 대하여 기 설정된 기준에 따라 유효성을 검증하고, 유효성이 검증된 값들에 근거하여 사고 발생 여부를 판단 및, 발생된 사고의 증상을 완화시키기 위한 완화 기능을 적어도 하나 제시하는 사고 정보 처리 모듈, 및, 상기 제시된 완화 기능을 이행할 수 있는 적어도 하나의 작업 경로를 정의하고, 정의된 작업 경로들 중 기 설정된 기준에 따른 최적의 경로를 검출하는 사고 대응 모듈을 포함하는 것을 특징으로 한다.
    • 本发明是为了有效地应对核电厂产生的事故。 一种处理核电站严重事故的装置,包括:信号接收部,从至少一个测量装置检测与核电厂的事故现象相关的测量信息; 事故信息处理模块,其根据对信号接收部分中的测量值的预定参考来验证有效性,基于验证值确定事故的产生,并且指示用于减轻事故症状的至少一个减轻功能; 以及事故对应模块,其定义用于执行减轻功能的至少一个过程路径,并根据所定义的过程路径的预定参考来检测优化的路径。
    • 28. 发明公开
    • 원전 안전계통을 위한 연산모듈 및 동작 방법
    • 核电厂安全系统的计算模块和操作方法
    • KR1020140022487A
    • 2014-02-25
    • KR1020120086643
    • 2012-08-08
    • 한국원자력연구원두산중공업 주식회사
    • 최종균박원만김동훈허섭천세우황인구권기춘이동영김창회김장열이성진김봉석하형준
    • G21D3/04
    • Y02E30/40G21D3/04
    • Disclosed are an operation module for a safety system of a nuclear power plant which implements a control function directly on a hardware in an FPGA-based controller, does not require operating system software, and simplifies the structure of the controller and an operation method thereof. In one embodiment, the operation module for a safety system of a nuclear power plant and the operation method thereof do not require operation system software by implementing a control function directly on the hardware (FPGA) and improves the operational reliability of a controller by simplifying the structure of the controller. Also, by implementing the control function directly on the hardware (FPGA), the present invention strengthens the network connection and improves accordingly to the security compared to a software-based controller; enhances the response time of the safety system thanks to a faster processing speed than the software-based controller by processing the control function in a distributed manner or in parallel; and facilitates the replacement of the controller without a big change in the control structure of the safe system when the replacement of a controller in an analog safety system for a nuclear power plant is necessary. [Reference numerals] (110) Second FPGA for application logic; (120) First FPGA for bus control; (160) Communication port; (170) Reset circuit; (AA) Operation module; (BB) I/O module; (CC) Backplane bus module; (DD) Receiving route of the operation module; (EE) Transmission route of the operation module
    • 公开了一种用于核电站安全系统的操作模块,其直接在基于FPGA的控制器的硬件上实现控制功能,不需要操作系统软件,并且简化了控制器的结构及其操作方法。 在一个实施例中,用于核电站安全系统的操作模块及其操作方法不需要直接在硬件(FPGA)上实现控制功能的操作系统软件,并且通过简化控制器的操作来提高控制器的操作可靠性 控制器的结构。 此外,通过在硬件(FPGA)上直接实现控制功能,本发明与基于软件的控制器相比,加强了网络连接并相应地提高了安全性; 通过以分布式或并行处理控制功能,通过比基于软件的控制器更快的处理速度来增强安全系统的响应时间; 并且当需要更换核电厂的模拟安全系统中的控制器时,便于更换控制器而不会对安全系统的控制结构发生重大变化。 (附图标记)(110)应用逻辑的第二FPGA; (120)第一个用于总线控制的FPGA; (160)通讯口; (170)复位电路; (AA)操作模块; (BB)I / O模块; (CC)背板总线模块; (DD)操作模块的接收路由; (EE)操作模块的传输路由