A nuclear reactor instrumentation system including a plurality of in core nuclear instrumentation assemblies arranged in a gap between a number of fuel assemblies charged in a reactor core. The income nuclear instrumentation assemblies each include a fixed type neutron detector assembly having a plurality of fixed type neutron detectors dispersively arranged in a core axial direction and a fixed type gamma thermometer assembly having a plurality of fixed type gamma ray heat detectors arranged at least in a same core axial direction as the fixed type neutron detectors. A power range detector signal processing device is operatively connected to the fixed type neutron detector assemblies through signal cables. A gamma thermometer signal processing device is operatively connected to the fixed type gamma thermometer assembly of the in core nuclear instrumentation assembly through a signal cable.
A reactor power output measurement device measuring a neutron flux with a traversing incore probe (TIP) traversing in a vertical direction in a core of a reactor, and calibrating a detection sensitivity of a local power range monitor based on a measured neutron flux distribution in the axial direction inside the reactor, which is provided with an integrated control device 9 for transmitting control data to all of TIP drive control devices 13a through 13e and performing control/monitor of all of detector drive systems 17a through 17e. An integrated unit operation/monitor device 10 for operating/monitoring the integrated control device 9, and a TIP integrated controller 8 comprising an integrated unit input/output device 11 for inputting detection signals obtained from TIP detectors 18a through 18e to the integrated control device 9 via the integrated unit input/output device 11, and which switches to the integrated unit operation/monitor device 10 when the drive unit operation/monitor devices 15a through 15e suffer from failure.
An incore monitoring method of a nuclear reactor, includes, measuring neutron flux levels at pitch levels corresponding to local power range monitor sensors arranged along an axial direction inside a detector assembly installed in a nuclear reactor; performing power calculation, including calculation of thermal characteristics, of fuel assembly group consisting of fuel assemblies adjacent to the corresponding detector assembly, based on indicated values of the local power range monitor sensors of the corresponding detector assembly at a first time, calculating thermal characteristics at a second, subsequent time in which the power calculation is not calculated, based on values indicated by the local power range monitor sensors and calculated thermal characteristics at the first time and values indicated by the corresponding local power range monitor sensors at the second time, and monitoring the calculated thermal characteristics.
A web-based system monitors a plurality of different gas turbine plants and includes a server system that summarizes data from a plurality of plants. The system also includes a client system including a browser and a storage device for storing information. The server system is configured to be coupled to the client system and retrieves operational data from the plurality of gas turbine plants, stores the data in the centralized database, and generates graphical representations of the operational data based on the stored data. More specifically, operational data from a plurality of turbine plants is summarized and viewable remotely with the server system.
