1022results 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.

A passive safety system includes a containment, a reactor in the containment, a plurality of safety injection tanks connected with the reactor and having water and nitrogen gas to supply water thereof into the reactor through a safety injection line communicating to the first safety injection line upon a loss of coolant accident, a plurality of core makeup tanks connected with the reactor to supply water thereof into the reactor through a second safety injection line communicating to a safety injection line upon the loss of coolant accident, and a plurality of passive residual heat removal systems to remove residual heat from the reactor upon the loss of coolant accident or a non-loss of coolant accident. The water in each of the safety injection tank is stably supplied to the reactor for many hours by a differential head resulting from gravity or gas pressure.

The invention relates to a method for monitoring nuclear reactor canned motor pump operation fault and a monitoring system. By aiming at a structural characteristic of a canned motor pump, the method for monitoring the nuclear reactor canned motor pump operation fault is established by the processes of signal acquisition, signal analysis, characteristic quantity extraction, abnormity discrimination, alarm, characteristic quantity database establishment and data reanalysis. The invention of the monitoring system adopts a distant controlling technology based on the standardization and modularization of PXI bus and FPGA, the reliability and easy maintenance performance of the system can be enhanced, the monitoring object enables configuration graphical, interface enables visualization, the operation is simple, the data export is convenient. The monitoring method and the monitoring system of the present invention are suitable for monitoring the fault of the nuclear reactor canned motor pump.

An offshore, floating, moored, nuclear power generating plant and multi-purpose platform is disclosed herein. In a preferred embodiment, the invention consists of a spar or cell spar platform with multi-purpose, all weather topside decks, attached to a submerged “dry tank” that further includes: reactor generator deck(s), power plant main control deck, and central plant deck, that are all integrated within a watertight ballast hull. The invention design further includes cells that are modular for facilitating factory assembly and ultimate construction in a shipyard environment. Reactor vessels are typical naval nuclear reactor having a time tested outstanding safety record. A plurality of reactor generator modules are interconnected and operate independently and collectively and are transmitted by a plurality of high voltage direct current (HVDC) submarine cables through a transformer to the electrical grid. Multipurpose topside decks house vessel commend, crew, and any ancillary and co-generation equipment. The present invention, constructed in a multi-path manufacturing process, provides exceptional economic, environmental, sustainability, security, safety, and operational advantages over the current art of power generation.

The invention discloses a method and a system for nuclear power equipment state monitoring. The method for nuclear power equipment state monitoring comprises the following steps of sending parameter request information to request real-time state parameters of nuclear power equipment, acquiring the real-time state parameters, carrying out the comparison between the real-time state parameters or a real-time state parameter value subjected to computer processing and a preset threshold value to determine if an alerting signal should be sent out, and storing the real-time state parameters or the real-time state parameter value subjected to the computer processing and the alerting signal in a database. The invention also provides the system for nuclear power equipment state monitoring. The method and the system have the advantages that 1, round-the-clock real-time monitoring of nuclear power station key equipment is realized and alerting information of corresponding equipment is obtained; and 2, a worker can carry out remote access and fast check real-time operation parameters of key equipment without carrying out in-site checking of parameter information in a master control chamber so that an alerting reason is analyzed timely or a potential equipment fault is found timely, and thus the precious time for solution of a real or potential accident is saved.

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.

Method and system for supplying emergency power to nuclear power plant, wherein the method includes, providing accumulator battery system, connected to emergency bus, the accumulator battery system is monitored by online monitoring system; in case of power loss of electrical devices of the nuclear power plant, the online monitoring system starts the accumulator battery system to provide power supply to the electrical devices of the nuclear power plant via the emergency bus. The present application is adapt to the key technologies and battery management technologies of million kilowatt-class advanced pressurized water reactor nuclear power plant, facilitating to improve the safety of the nuclear power plant in case of serious natural disasters beyond design working conditions.

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.

A pressurized water nuclear reactor (PWR) has an internal pressurizer volume containing a steam bubble and is surrounded by a containment structure. A condenser is disposed inside the containment structure and is operatively connected with an external heat sink disposed outside of the containment structure. A valve assembly operatively connects the PWR with the condenser responsive to an abnormal operation signal such that the condenser condenses steam from the steam bubble while rejecting heat to the external heat sink and returns the condensed water to the PWR. A quench tank contains water with dissolved neutron poison. A valved tank pressurizing path selectively connects the steam bubble to the quench tank to pressurize the quench tank, and a valved soluble poison delivery path selectively connects the quench tank to the PWR such that the quench tank under pressure from the steam bubble discharges water with dissolved neutron poison into the PWR.

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.

The invention is suitable for the implementation field of accident management in a nuclear power station and a method of settling a severe accident for an improved 1000MW class PWR nuclear power station is provided. The method comprises the following steps of: reading measured data of the nuclear power station in a severe accident condition and judging the severity degree of the accident according to the data; determining the execution sequence for the diagnosis tree of the accident condition in a severe accident management guidance and the logical sequence for the condition of accident diagnosis in the diagnosis tree of accident condition according to the severity degree of the accident; entering the corresponded diagnosis tree of the accident condition according to the severity degree of the accident and diagnosing the accident according to the condition of the accident diagnosis in the diagnosis tree of the accident condition and entering the corresponded accident management guidance. Through the judgment of the severity of the accident and according to the diagnosis tree of the accident condition, the invention diagnoses and settles the accident with symptom as the guide and with pertinence, thereby realizing efficient, quick and correct judgment and settlement of the accident when the accident happens.

The present invention relates to a nuclear power plant and safety system with fuse element and gravity elevator, the buildings of the power plant subjected to contamination being buried below sea level and under borated water basins, and having a safety system free of electrical and electronic components to act in the event of possible accidents comprising, among others, means for flooding the buildings of the power plant with thermal fuses and gravity elevators for operator evacuation in the event of an emergency.

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 discloses a protection method for digitalized instrument control diversity of a nuclear power station. The method comprises the following steps that a diverse actuation system (DAS) is used for obtaining a common cause failure (CCF) which is formed by overlapping abnormal working status of the nuclear power station; the DAS is used for driving manual control on operation and control of a key safe function in the CCF, the key safe function comprises at least one of reaction control, waste heat elimination, a reactor coolant device, containment isolation and containment integrity; if the operation and control of the key safe function can not be subjected to the manual control according to the requirement of response time, the DAS is used for implementing automatic driving operation. According to the protection method for the digitalized instrument control diversity of the nuclear power station, occurrence of the CCF can be effectively prevented. Additionally, the invention further discloses a protection system for the digitalized instrument control diversity of the nuclear station.

The invention relates to an accident analysis method for a digital control diversity protection system of a million-kilowatt nuclear power station. The method analyzes that a pile main protection system of a 'digital control system (DCS)' in a million-kilowatt nuclear power project is in software common cause failure, and simultaneously, the method superposes the expected operation transient or design basis accident, in the case that an operator has no time to perform manual intervention, the method further researches on adding a diverse actuation system (DAS) in the DCS to ensure the safety of the pile. A DAS scheme is determined after rounded accident analysis of the nuclear power station, and the DAS scheme comprises corresponding automatic protection signals and setting values, so as to guarantee that the accident consequence meets the requirement of a 'diversity and defense in depth (3D)' acceptance criterion.

A method for monitoring running status of a nuclear power plant comprises: a nuclear power plant real-time monitoring apparatus establishing a dynamic rule base according to historical data of nuclear power equipment in normal running status; the nuclear power plant real-time monitoring apparatus acquiring, in real time, an online running status parameter of the nuclear power equipment; and if the online running status parameter does not match the dynamic rule base, the nuclear power plant real-time monitoring apparatus determining that the online running status parameter is abnormal. In the method for monitoring running status of a nuclear power plant, non-real-time running data and real-time running data of a nuclear power plant system are input in a simulation model to perform a simulation test, thereby implementing effective real-time monitoring on running of equipment of the nuclear power plant. Moreover, further disclosed are an apparatus and a system for monitoring running status of a nuclear power plant.

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 invention relates to a method and a system for controlling and switching a computerized work station and a backup disc. The method comprises the following steps that: a transfer switch sends a switching command; a logic processing unit judges the working modes of the computerized work station and the backup disc on the basis of the switching command, and sending a state signal to a control cabinet; and the control cabinet receives the state signal and takes corresponding interlocking and activating operations. The invention realizes the switching of control rights of the computerized work station and the backup disc of a nuclear power station main control room, guarantees the isolation of train A power supply and train B power supply in the switching process, does not cause failure of switching function when any switching fails, meets the single failure criterion, and ensures that the normal operation and accident handling of a nuclear power station unit can be maintained by the backup disc when the computer working station fails, thus improving the security and economy of the nuclear power station unit.

Embodiments of the invention disclose a nuclear power plant diversity driving system, a nuclear power plant diversity driving method and a diversity protection system. The nuclear power plant diversity driving system is used for protecting the safety of a nuclear power plant when a reactor protection system fails, and comprises a signal receiving module used for receiving a detection signal, logic processing modules used for logically processing the detection signal to judge whether there is a design basis accident and generating a driving signal when judging that there is a design basis accident, and a signal output module used for outputting the driving signal to an actuator to drive the actuator to act. According to the invention, a design basis accident can be detected automatically, and a driving signal can be generated correspondingly to automatically make the actuator act.

A nuclear reactor protection system includes a plurality of functionally independent modules, each of the modules configured to receive a plurality of inputs from a nuclear reactor safety system, and logically determine a safety action based at least in part on the plurality of inputs, each of the functionally independent modules comprising a digital module or a combination digital and analog module, an analog module electrically coupled to one or more of the functionally independent modules, and one or more nuclear reactor safety actuators communicably coupled to the plurality of functionally independent modules to receive the safety action determination based at least in part on the plurality of inputs.

The invention discloses a radiation protection control method for unit operation and maintenance during fuel damage of a pressurized water reactor nuclear power station. The radiation protection control method comprises the steps of: carrying out radiation control through scavenging and chemical operation of a main loop; monitoring relevant channel radioactivity conditions; measuring and evaluating air pollution of a production site; implementing iodine removal and scavenging on a reactor plant aiming at the radioactive contamination condition; and carrying out collective protection and personnel protection on the production site. Aiming at the defect of personal iodine internal contamination caused by poor radiation protection control after fuels of the pressurized water reactor nuclear power station are damaged in the prior art, the invention provides the radiation protection control method capable of carrying out effective control and protection without causing internal contamination to workers.

The invention discloses a method and system for on-line monitoring of the running state of nuclear power equipment. The system includes a nuclear power equipment database; a model building module used for building a nuclear power equipment characteristic parameter on-line calculation model according to the nuclear power equipment database; and a nuclear power equipment running state diagnosis module used for analog calculation of a characteristic parameter predicted value of nuclear power equipment to be tested of the previous moment before the current moment according to the nuclear power equipment characteristic parameter calculation model, a contrastive analysis of the characteristic parameter predicted value and a real-time detection value of the characteristic parameter of the nuclear power equipment is made, and an on-line monitoring result of the running state of the nuclear power equipment is obtained according to the contrastive analysis. A nuclear power plant manager can discriminate abnormal or fault equipment among numerous nuclear power equipment according to the monitoring result, thereby providing a scientific basis for guiding equipment maintenance or replacement work, and improving operation safety and stability of the nuclear power plant.

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.

An assembly is provided including a mobile structure including a main pipe equipped with a first end intended to be connected to a water supply and a second end intended to be connected to a circuit connected to the primary circuit of the reactor, and including between these two ends in the direction of circulation of the water, a pump, a water heating device, an injector for continuously injecting the powdered neutron-absorbing element into the water of the main pipe, a first mixer for mixing and dissolving powder with water and a controller driving and controlling the flow rate of the water and the flow rate of the powder injected.

An emergency temporary spent fuel pool cooling system for a nuclear power generating facility that has a permanently installed primary loop within the nuclear containment and a mobile temporary secondary loop. The secondary loop is housed in transport vehicles that can be stored off site and is connectable in heat exchange relationship with the primary loop through quick disconnect couplings that are accessible on the outside of the reactor containment. The transport vehicles also include self-contained power and compressed air sources for powering and controlling the entire emergency cooling system. The system also has a make-up water injection capability for refueling the spent fuel pool and secondary loop.

A nuclear power plant comprises a pressurized water reactor (PWR) and a steam generator driving a turbine driving an electric generator. A condenser condenses steam after flowing through the turbine. Responsive to a station blackout, the nuclear power plant is electrically isolated and a bypass valve is opened to convey bypass steam flow from the steam generator to the condenser without flowing through the turbine. The thermal power output of the PWR is gradually reduced over the transition time interval. After opening, the bypass valve is gradually closed over the transition time interval. A supplemental bypass valve may also be opened responsive to the station blackout to convey supplemental bypass steam flow from the steam generator to a feedwater system supplying secondary coolant feedwater to the steam generator. The supplemental bypass steam flow does not flow through the turbine and does not flow through the condenser.

Liquid nitrogen, the densest and highly transportable form of nitrogen, and the cold nitrogen gas it produces when released from its container, for emergency cooling of fuel rods and nuclear reaction chambers and fighting hazardous fires is disclosed. Liquid nitrogen may be disbursed via a thermally-activated heat valve attached to a container of liquid nitrogen.