Abrégé

A method and device for evaluating the degree of neutron irradiation embrittlement of a nuclear power plant reactor pressure vessel. The initial electrical resistivity of the steel of a reactor pressure vessel is measured and the electrical resistivity of the steel of the reactor pressure vessel of any arbitrary point in time after being embrittled by neutron irradiation is acquired in real-time to calculate the macroscopic mechanical properties and/or neutron irradiation fluence; and, the degree of irradiation embrittlement of the reactor pressure vessel is analyzed and evaluated on the basis of the macroscopic mechanical properties and/or neutron irradiation fluence. The method and device are economical, environmentally friendly, safe, and highly efficient, allow real-time monitoring of the degree of irradiation embrittlement of a specific part of the reactor pressure vessel, and allow simultaneous monitoring of the degree of irradiation embrittlement of multiple parts of the reactor pressure vessel.

Classes IPC  ?

• G21C 17/003 - Inspection à distance des enceintes, p. ex. des cuves de pression

Abrégé

A method and system for detecting the integrity of a fuel element cladding of a nuclear power station. The system comprises a detection assembly (6), a comparison assembly (7), and an alarm assembly (8). The detection assembly (6) is used for detecting and outputting the activity concentration of an inert gas contained in a loop coolant. The comparison assembly (7) is used for receiving the outputted obtained activity concentration, comparing the detected activity concentration with a preset alarm threshold condition, and generating and sending an alarm signal if the alarm threshold condition is satisfied. The alarm assembly (8) is used for receiving the sent alarm signal and giving an alarm according to a preset alarm mode. In the method, the breakage rate of a fuel element cladding is detected by monitoring the activity concentration of the inert gas contained in the loop coolant, the feasibility and the sensitivity are higher, and mistake measurement possibly caused by a non-fuel element failure can be avoided; in addition, one or more alarm thresholds can be set, and the breakage rate limit value of the fuel element cladding concerned during the safe operation of the nuclear power plant can be quantitatively monitored.

Classes IPC  ?

• G21C 17/04 - Détection de rupture de gaine

Abrégé

A nuclear power plant reactor protection system (100) and a safety control method therein. The protection system (100) comprises: an emergency shutdown system (10) divided into N protection channels, each protection channel obtaining protection parameters from a signal preprocessing system (11) to carry out threshold comparison; a special driving system (20) connected to the N protection channels, receiving a threshold comparison result, performing special driving logic processing according to the threshold comparison result, and outputting a first special driving instruction for driving an actuator that needs to be operated before a reactor reaches a controllable state and after a design reference accident of a nuclear power plant takes place; and an automatic safety system (30) connected to the special driving system (20) by means of a safety-level ring network (40), and generating a first device-level control instruction for controlling the actuator that needs to be operated when the reactor is converted from the controllable state to a safe shutdown state and after the design reference accident of the nuclear power plant takes place. The system and method can reduce the complexity of the maintenance and regular testing scheme for the protection system.

Classes IPC  ?

• G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
• G21D 3/04 - Dispositions de sécurité

Abrégé

A method and system for collecting a vibration phase signal of a nuclear reactor cooling pump, falling within the technical field of nuclear power plant security. The system comprises: a vibration probe (11), a vibration signal processor (12), a phase probe (22), a reference pulse signal processor (23) and a phase signal processor (31). The vibration probe (11) is electrically connected to the vibration signal processor (12), the phase probe (22) is electrically connected to the reference pulse signal processor (23), and the vibration signal processor (12) and the reference pulse signal processor (23) are both in a communication connection with the phase signal processor (31). A reference pulse signal is acquired by means of the newly added phase probe (22), and then, the acquired reference pulse signal and an existing vibration signal are calculated by means of the phase signal processor (31) so as to obtain a vibration phase signal of a main shaft of a nuclear reactor cooling pump. In this way, the system for collecting a vibration phase signal of a nuclear reactor cooling pump can monitor the vibration phase signal of the main shaft of the nuclear reactor cooling pump, and can thus analyze a vibration condition of the nuclear reactor cooling pump more comprehensively.

Classes IPC  ?

• G01M 7/02 - Test de vibration

Abrégé

The present invention discloses a nuclear power plant core state monitoring method, server and system, solving the technical problem that no solution exists in the prior art for monitoring a core state using a self-powered neutron detector. The present solution includes: acquiring first measurement data from a distributed control system of a nuclear power plant, acquiring second measurement data from a self-powered neutron detector of a nuclear power plant core measurement system, and on the basis of the first measurement data and the second measurement data acquiring a core state parameter and a core margin, and finally outputting the core state parameter and core margin. Also provided is a control solution suitable for a self-powered neutron detector technique core monitor, including acquiring a system signal, combining the same with a core parameter and processing to acquiring a core state parameter and core margin, so as to provide the entire nuclear power plant with more comprehensive core data support, providing necessary and accurate information for reliable operation of a unit and correct operation by an operator.

Classes IPC  ?

• G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p. ex. pour la mesure de la radioactivité, des contraintes

Abrégé

A nuclear power plant diverse driving system, method and diverse protecting system, the nuclear power plant diverse driving system (1) being used to ensure the safety of the nuclear power plant when a reactor protection system (2) fails, comprising: a signal receiving module (11), used to receive a detection signal; a logic processing module (12), used to perform a logic processing on the detection signal so as to determine whether a design basis accident occurs, and generate a drive signal when such an accident is determined to have occurred; a signal output module (13), used to output the drive signal to an execution mechanism (3) so as to drive the execution mechanism (3) to operate, thus realizing automatic detection of the design basis accident and generation of the drive signal correspondingly so as to automatically control the operation of the execution mechanism (3).

Classes IPC  ?

• G21D 3/06 - Dispositions de sécurité réagissant à des défaillances à l'intérieur de l'installation

Abrégé

A nuclear instrumentation system of a nuclear power plant and positioning method therefor. The system comprises: a source range (SR) channel, an intermediate range (IR) channel, and a power range (PR) channel. Each channel comprises a detector disposed on the periphery of a pressure vessel. Each of the detectors of the PR channel and the IR channel comprises several fission chambers, and the detectors of the PR channel and the IR channel share some of the several fission chambers. Some detectors choose to use fission chambers, and therefore have improved anti-Gamma radiation capability, anti-noise performance, and anti-electromagnetic interference performance. Moreover, sharing fission chambers decreases the number of detectors and reduces subsequent workload for detector installation and positioning. Furthermore, increasing the redundancy of some channels improves system reliability. "Bucket-suspending type" installation allows easy detector installation and pull-out operations and protects persons against high radiation. A cable connection board is installed at a hoisting opening of an operating platform and away from a reactor core, such that signal transmission would not be easily interfered and affected by the reactor core environment.

Classes IPC  ?

• G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p. ex. pour la mesure de la radioactivité, des contraintes

Abrégé

A power supply method and system for a hydrostatic test on a primary circuit (100) of a nuclear power plant. The method comprises: S1, an auxiliary power supply (21) supplies power in sequence via at least one column of inlet wire to start a main pump (241) on this column of inlet wire, and limits loads of a device, the device and the running main pump (241) being on the same column of inlet wire; S2, the auxiliary power supply (21) supplies power via the at least one column of inlet wire to start a charging pump (242) on this column of inlet wire; S3, the auxiliary power supply (21) supplies power to start a hydrostatic test pump (243) so as to pressurize a primary circuit (100) to a target pressure value; and S4, automatically start, if the auxiliary power supply (21) is de-energized in the above power supply steps, an emergency power supply (23) on one of columns of inlet wires to supply power to loads on this column of inlet wire. The method does not need a main power supply for use, and is high in safety and reliability.

Classes IPC  ?

• G21C 17/00 - SurveillanceTests

Abrégé

A method and a system for supplying emergency power to a nuclear power plant. The method comprises: providing a secondary battery energy storage system (2100), connecting the secondary battery energy storage system (2100) to an emergency bus (2910), online monitoring the secondary battery energy storage system (2100), starting, by a control system, the secondary battery energy storage system (2100) in case of power failure of power-consuming devices of a nuclear power plant, and supplying power to the power-consuming devices of the nuclear power plant through the emergency bus (2910). The system and method enhance security of the nuclear power plant in natural disasters.

Classes IPC  ?

• H02J 9/00 - Circuits pour alimentation de puissance de secours ou de réserve, p. ex. pour éclairage de secours
• G21D 3/04 - Dispositions de sécurité

Abrégé

The invention is applicable to the field of nuclear power control, which provides a digitalized control system (DCS) of a nuclear power unit, and an information processing method and device for the DCS. Task information, digitalized operation list (2) information corresponding to the task information, and supporting interface (3) information are outputted by the main body of a program (1). The digitalized operation list (2) corresponding to a specified task is searched for according to the program's main body (1). The detailed information of the task, the device information according to the detailed information of the task, and task link information are outputted by the found digitalized operation list (2). The digitalized operation list (2) issues a linking instruction to the supporting interface (3). The supporting interface (3) receiving the linking instruction outputs cross-system monitoring parameters and operation instructions. Digitalized processing of the overall program of the nuclear power unit, overcomes deficiencies of DCS visibility. The running efficiency of the overall program of the nuclear power unit is increased, and the advantage of information processing of the DCS is fully employed.

Classes IPC  ?

• G21D 3/00 - Commande des installations à énergie nucléaire
• G21C 17/00 - SurveillanceTests
• G05B 19/418 - Commande totale d'usine, c.-à-d. commande centralisée de plusieurs machines, p. ex. commande numérique directe ou distribuée [DNC], systèmes d'ateliers flexibles [FMS], systèmes de fabrication intégrés [IMS], productique [CIM]

Abrégé

Disclosed are a reagent for testing the purification capacity of a radioactive gas in a nuclear power plant, preparation method thereof and an iodide filter testing equipment using this reagent. The reagent is prepared by mixing methyl phosphate compound or dimethyl acetal compound, acetonitrile, trimethyl chlorosilane and radioactive iodine sources and carrying out a reaction at a temperature of 20℃-50℃ under an inert gas for 10-40 min. The prepared products except methyl iodide are non-toxic or little toxic to the nuclear grade impregnated activated carbon in the iodide filter.

Classes IPC  ?

• C07C 17/093 - Préparation d'hydrocarbures halogénés par remplacement par des halogènes
• C07C 19/07 - Composés acycliques saturés contenant des atomes d'halogène contenant de l'iode
• B01D 35/143 - Indicateurs de l'état du filtre
• G21F 9/02 - Traitement des gaz

Abrégé

A method for joint configuration of nuclear power plant fuel includes the following steps: (S1) for at least one operating unit, based on an equilibrium cycle or transition cycle reactor core design, at least one new fuel element is added to at least one operating unit; (S2) after running a combustion cycle, and on the basis of the new fuel elements in step (S1), more first spent fuel elements are obtained from the at least one operating unit than are obtained from the equilibrium cycle or transition cycle reactor core design, and said first spent fuel elements are kept in reserve; (S3) for at least one new starting unit, a scheduled number of new fuel elements, as well as the first spent fuel elements obtained for reserve in step (S2), are set in the first reactor cores of at least one new starting unit.

Classes IPC  ?

• G21C 3/30 - Assemblages d'un certain nombre d'éléments combustibles sous forme d'une unité rigide