1018results about "Power plant safety arrangement" patented technology

The present invention is directed to a control system device that forces a machine operator to comply with the regulation by not allowing the machine to operate until the maintenance log has been completed. By disabling the equipment, the control unit prevents an operator from starting or operating the equipment prior to performing the required checks and documenting his / her identification number for verification purposes. Once the log has been entered, the system provides numerous methods for downloading of the data for long-term storage and retrieval. The system also has provisions to alert the managerial staff if the equipment is operated beyond the minimum check period while providing for a means to notify the operator that the required check interval has been reached.

The invention provides a priority management system of a nuclear power plant; the priority management system of the nuclear power plant is mainly used for managing instruction priorities and interfaces among a digital instrument control system and other systems of the nuclear power plant and driving devices of engineered safety facilities; the priority management system is used for directly receiving instructions from an engineered safety driving cabinet ESFAC, a safety related control cabinet SRC, a diversified driving control cabinet DAC, a serious accident control cabinet SAC and a power plant standard automatic system PSAS in a hard wiring manner, collecting feedback information of a field executor, supporting a self-diagnostic function and a periodic test of a safety system, and transmitting the feedback information, a self-diagnostic result, a quantitative test result and the like of the field executor to a DCS (Data Communication System) of the nuclear power plant; the priority logic part of the priority management system is in the form of a logic circuit; therefore, the priority management system is completely different from the DCS; and thus, software common-cause failures can be effectively avoided.

In a computer-implemented method of designing a nuclear reactor of a given reactor plant, an initial, test reactor core design is generated for the given plant based on a plurality of limits input by a user. The limits include a plurality of transient licensing constraints to be satisfied for operating the given plant. The method includes selecting, from a set of automated tools, one or more automated tools to evaluate the test core design, and operating one of more of selected automated tools to output data for display to the user. The displayed data is related to a core design that satisfies the limits inclusive of the transient licensing constraints.

The invention discloses a transient test control method and system used in a debugging and starting process of a nuclear power station, which are used for solving the technical problems in the prior art that the program is complicated, guiding points and operation sheets are excessive and the execution efficiency is low when SOP (State Occurrence Procedure) of a unit of the nuclear power station is used for processing a single nuclear power accident, so that the whole accident processing efficiency in a transient testing process of the nuclear power station is low; the decreasing speed of temperatures and pressure of a primary circuit is high under the special conditions without reactor core residual heat and the like during the debugging and starting process, the SOP cannot control in time, and the requirements on the control of the unit in a testing process cannot be completely met. The method comprises the following steps: starting the SOP of the unit of the nuclear power station and a transient test control regulation; carrying out accident detection on the unit of the nuclear power station through the transient test control regulation to obtain detection information; and determining an accident type of the unit of the nuclear power station based on the detection information, determining an accident processing policy based on the accident type, and intercepting a circulating execution manner of the SOP based on the processing policy, so as to carry out intervene control on the unit of the nuclear power station.

A nuclear power plant and a fuel pool water cooling facility and method are provided that can suppress the decrease of a water level in a fuel pool with no power supply at the time of malfunction of a circulating water system.The nuclear power plant includes a reactor pressure vessel 2 that encompasses a reactor 1 containing nuclear fuel; a containment vessel 3 for housing the reactor pressure vessel 2; a fuel pool 11 for storing spent fuel 12; a reactor building 10 that houses the reactor pressure vessel 2, the containment vessel 3 and the fuel pool 11; a circulating water system 21 adapted to forced-circulating-cool the fuel pool water 14 in the fuel pool 11; and at least one heat pipe 13 for transferring heat of the fuel pool water 14 in the fuel pool 11 and discharging the heat to the atmosphere.

An enhanced passive containment air cooling system for a nuclear power plant that increases the heat transfer surface on the exterior of the nuclear plant's containment vessel. The increased surface area is created by forming a tortuous path in or on at least a substantial part of the exterior surface of the containment vessel over which a cooling fluid can flow and follow the tortuous path. The tortuous path is formed from a series of indentations and protrusions in or on the exterior surface that form a circuitous path for the cooling fluid.

The invention relates to an accident monitor system for a nuclear power unit and a monitor method thereof. The system comprises a state display device for displaying the system parameters and the equipment state of the entire nuclear power unit, wherein the state display device comprises a state monitor module, a parameter monitor module and an operation link module. The accident monitor system of the nuclear power unit and the monitor method thereof can effectively classify various complex information of the nuclear power unit to provide rapid and accurate system parameters and equipment state to operators together by using only one display device, thereby fully using the digitization characteristics. The possible control risk resulting from frequent switching of control frames due to the digitization can be obviated through continuous display of the important parameters and the important equipment state. Different supervision images can be achieved through reasonable links, and the rapid navigation among electronic program images can ensure smooth unit control so as to effectively reduce the work loads of the operators.

A nuclear reactor includes a pressure vessel and a nuclear reactor core disposed in the pressure vessel. A subterranean containment structure contains the nuclear reactor. An ultimate heat sink (UHS) pool is disposed at grade level, and an upper portion of the subterranean containment structure defines at least a portion of the bottom of the UHS pool. In some embodiments, the upper portion of the subterranean containment structure comprises an upper dome, which may protrude above the surface of the UHS pool to define an island surrounded by the UHS pool. In some embodiments, a condenser comprising a heat exchanger including hot and cold flow paths is disposed inside the subterranean containment structure; and cooling water lines operatively connect the condenser with the UHS pool.

The present invention relates to a containment filtered venting system used for a nuclear power plant, the system comprising: a containment filtered venting container for storing a composition of the containment filtered venting system; an entrance pipe connected to the containment filtered venting container and a nuclear reactor building; a combined nozzle connected from the entrance pipe and immersed in a filtering solution filled in a part of the container; a cyclone separator for removing most of droplets and aerosols having large sizes, which have escaped from the combined nozzle and then been mixed with the filtering solution, and guiding the filtering solution to a metal filter; the metal filter which is connected to an upper end of the cyclone separator and filters out the remaining droplets and aerosols; a molecular sieve for removing organic iodine from exhaust gas filtered through the metal filter; and an exit pipe interconnecting the containment filtered venting container and a stack.

An emergency core cooling system is provided with a hybrid safety system composed of an active safety system and a static safety system for ensuring the safety against a severe natural phenomenon such as a giant earthquake and a mega hurricane. An emergency core cooling system for a boiling water reactor includes four safety divisions in total: three safety divisions for an active safety system having a high pressure reactor core cooling system, a low pressure reactor core cooling system, a residual heat removal system, and an emergency diesel generator; and one safety division for a static safety system having an isolation condenser, a gravity drop reactor core cooling system, and a static containment vessel cooling system.