1014results about "Power plant safety arrangement" patented technology

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.

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.

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 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.

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 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.

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.