Abstract:
A nuclear instrumentation and control system is disclosed herein. The nuclear instrumentation and control system can include a housing and a plurality of selectively removable finished board assemblies configured to be installed within the hosing and electrically coupled to the instrumentation and control system nuclear reactor. At least one of the selectively removable finished board assemblies includes an input/output circuit. The nuclear instrumentation and control system can further include a daughter card including a control circuit, wherein the daughter card is configured to be selectively coupled to the at least one selectively removable base board of the plurality of selectively removable base boards via a mechanical connector and an electrical connector.
Abstract:
In an operation monitoring apparatus of a nuclear power plant, a first operation console (12) that can be operated by an operator and includes displays (31 to 37), an operation command console (14) that can be operated by a shift supervisor and includes displays (41 to 44) , a transfer device (51) that can display an image displayed on the displays (31 to 37) of the first operation console (12) on the displays (41 to 44) of the operation command console (14), and a switching device (54) that switches an image on the displays (41 to 44) of the operation command console (14) to the image on the displays (31 to 37) of the first operation console transferred by the transfer device (51) are provided. With this configuration, it is possible to improve communications between the supervisor and the operation in operation of the nuclear power plant.
Abstract:
A central control device of a nuclear power plant monitors and controls the nuclear power plant. The central control device includes monitoring operation devices (for example, an alarm VDU, a common system VDU, and a safety system VDU of an operation console) each having both a function as a display unit that displays information on the nuclear power plant (for example, operation information, safety information, and the like) and a function as an operation unit that operates the nuclear power plant, and a control unit that controls these monitoring operation devices. The control unit selects an operation procedure document corresponding to an input operation to a monitoring operation device and displays the operation procedure document on the monitoring operation device.
Abstract:
Provide an operation management support apparatus for power plant, supporting a maintenance work and preventing a user from violation of the operational safety programs, caused by a human error in case where a power plant temporarily deviates from LCO. The operation management support apparatus for power plant includes: an alarm device 12 that compares a plant data measuring by sensors 3a-3x installed in a nuclear power plant 2 with preset alarm the value and generates an alarm output instruction signal for instructing an alarm output in case of determining that the power plant is abnormal; an operational safety program DB 14 that stores an information in relation to an operational safety program of the power plant; an support device 13 that extracts an information in relation to the operational safety program of which the alarm output represents a conflict from the operational safety program DB 14 based on the plant data in relation to the alarm output in case of receiving the alarm output instruction signal; and a display device 15 (16) that displays the plant data and the information in relation to the operational safety program, extracted by the support deice.
Abstract:
The invention relates to a method of determining at least one technological uncertainty factor in respect of nuclear fuel elements (23) as a function of variations in the production parameters of the elements (23) in relation to nominal values. The inventive method comprises a step involving the use, for at least one production parameter, of a collective variation in said parameter in relation to the nominal value within a batch of produced elements (23). The invention can be used, for example, to design, produce and check pellets for light water reactors.
Abstract:
According to an embodiment, a digital process type monitor device includes a plurality of modules and a mother board connected to each of the modules. Each module includes: a base board connected to a connector and having an FPGA for main control and an IPGA for sub board control mounted thereon; and a sub board for a main-machine I/F process, having an FPGA for an I/F process mounted hereon. Each sub board has storage devices for storing man-machine I/F information on the sub board. Each of the FPGA writes transmission data into a predetermined region of a transmission area and has a common transmission protocol to share the transmission data between the respective modules.
Abstract:
A distribution control system (DCS) control module for a transformer in nuclear power engineering, includes: an input command processing logic unit (1), a malfunction processing logic unit (2), a state processing logic unit (3), an output command generating logic unit (4) and a 6.6 kV switchgear of the transformer. The DCS control module utilizes the DCS integral with the power units to realize the control of 6.6 kV transformer switch, the sharing of the operator station with the power unit control system, and the overall monitoring, and the operation reliability of the power units is improved.
Abstract:
A method and apparatus for controlling components in a component control system in a nuclear power plant includes an image processing system and display processor (IPS-DP) for issuing an encrypted command for a selected component in a component command system (CCS) in the nuclear power plant; a soft controller for receiving the encrypted command and matching the command with the selected component in the CCS for issuing a control command to the selected component; and control channel gateway for receiving the encrypted command from the IPS-DP and soft controller, deciphering the encrypted command, and, if authenticated, issuing a control command for said selected component in the CCS. Security and isolation, while complying with applicable codes and regulations, are assured.
Abstract:
An alarm significance mapping method assigns the subset of parameters and their alarms considered to be of a safety-critical nature in an industrial control system and displays that subset on an apex screen display and other selected appropriate displays, such as a touch-responsive display in the form of alarm icons for presentation to the system operators. Each alarm icon on the `apex` display is coupled or concatenated to other displays through a display page hierarchy so that the operator, by selecting a particular alarm icon on the `apex` screen, can follow the alarm `thread` through the multi-level display page hierarchy to the ultimate condition or conditions that cause an alarm on the `apex` screen.
Abstract:
Alarm acknowledgment can be made not only at the alarm tile array of a given console but via other touch sensitive alarm indications in the screen displays of the monitoring system at the same or other consoles; also, touching one tile can acknowledge multiple alarm sources.