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Небесная энциклопедия

Космические корабли и станции, автоматические КА и методы их проектирования, бортовые комплексы управления, системы и средства жизнеобеспечения, особенности технологии производства ракетно-космических систем

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Мониторинг СМИ

Мониторинг СМИ и социальных сетей. Сканирование интернета, новостных сайтов, специализированных контентных площадок на базе мессенджеров. Гибкие настройки фильтров и первоначальных источников.

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Поддерживает ввод нескольких поисковых фраз (по одной на строку). При поиске обеспечивает поддержку морфологии русского и английского языка
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Применить Всего найдено 20. Отображено 20.
30-06-2023 дата публикации

Chromatograph carrier gas self-checking system of gas sampling system of high-temperature gas cooled reactor nuclear power plant

Номер: CN116359395A
Принадлежит:

The invention provides a carrier gas self-checking system for a chromatographic instrument of a gas sampling system of a high-temperature gas cooled reactor nuclear power plant. The first helium gas tank and the second helium gas tank are both provided with helium gas which is detected and meets the helium gas purity requirement; the control device is used for controlling the first helium tank to input carrier gas to the chromatographic instrument through a switching valve and controlling the second helium tank to input carrier gas to the chromatographic instrument through the switching valve after helium in the first helium tank is used up, and the control device is used for controlling the second helium tank to input carrier gas to the chromatographic instrument through the switching valve after helium in the first helium tank is used up. And controlling the replaced first helium tank to input to-be-detected gas to the chromatographic instrument through the switching valve so as to obtain ...

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23-05-2023 дата публикации

Diaphragm type deluge valve group monitoring method, device and system and storage medium

Номер: CN116139442A
Принадлежит:

The invention discloses a diaphragm type deluge valve group monitoring method, device and system and a storage medium. The method comprises the following steps: acquiring first detection data of a first water sensor; wherein the first water immersion sensor is arranged in at least one of the following positions: a water outlet of a drip check valve connected with the diaphragm type deluge valve group, a position below an electromagnetic valve drain pipe of the diaphragm type deluge valve group and a position below a hydraulic alarm bell of the diaphragm type deluge valve group; acquiring the current state of the diaphragm type deluge valve group; based on the first detection data and the current state, whether the diaphragm type deluge valve group is abnormal or not is monitored; and generating first alarm information in response to the abnormality of the diaphragm type deluge valve group. According to the technical scheme, the diaphragm type deluge valve group can be monitored in real ...

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07-04-2023 дата публикации

Control device and method for high-temperature gas cooled reactor nuclear power station

Номер: CN115938627A
Принадлежит:

The invention provides a control device and method for a high-temperature gas cooled reactor nuclear power plant, the device comprises at least two controllers for controlling different reactors in the high-temperature gas cooled reactor nuclear power plant, and the at least two controllers comprise a first controller for controlling only a single reactor and/or a second controller for controlling only a single reactor. The first controller is used for acquiring user account information in response to a user input operation and allowing to control the single reactor under the condition that the control authority of the single reactor is determined according to the user account information, and the second controller is used for controlling the single reactor in response to the completion of the execution of the unlocking process. According to the method, the unlocked target reactor is determined from the at least two reactors, and the target reactor is allowed to be controlled, so that on ...

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14-04-2023 дата публикации

High-temperature gas cooled reactor nuclear steam supply module switching method

Номер: CN115966322A
Принадлежит:

According to the high-temperature gas cooled reactor nuclear steam supply module switching method and device and the storage medium, in response to the received nuclear steam supply module switching instruction, the first nuclear steam supply module needing to be switched and the second nuclear steam supply module needing to be switched are determined; the switching instruction comprises switching to a target nuclear steam supply module and a nuclear steam supply module needing to be switched, the first nuclear steam supply module is the nuclear steam supply module needing to be switched, the second nuclear steam supply module is the target nuclear steam supply module, and the second nuclear steam supply module is merged into the steam turbine generator unit; and quitting the steam supply operation of the first nuclear steam supply module. Therefore, the nuclear steam supply module can be safely and efficiently switched, and meanwhile the situation that the steam turbine generator unit ...

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07-04-2023 дата публикации

Nuclear power plant natural disaster response method and device

Номер: CN115936442A
Принадлежит:

The invention provides a nuclear power plant natural disaster response method, and relates to the technical field of nuclear power plant emergency, and the method comprises the steps: obtaining the natural disaster data of a nuclear power plant; determining the type and early warning level of the natural disaster of the nuclear power plant according to the natural disaster data; and determining the response action of the natural disaster of the nuclear power plant according to the type and early warning level of the natural disaster of the nuclear power plant. By establishing perfect natural disaster classification and response, the nuclear power plant can identify the risk in advance according to different types of natural disasters and formulate specific countermeasures, so that the nuclear safety risk and the personal injury risk caused by the natural disasters are reduced.

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25-04-2023 дата публикации

Data compression method and device for loading and unloading steps of nuclear fuel of reactor

Номер: CN116011401A
Принадлежит:

The invention relates to a data compression method and device for a nuclear fuel loading and unloading step of a reactor. According to the specific scheme, track point data of target nuclear fuel are obtained; performing first conversion processing on the track point data to obtain a binary array; performing second conversion processing on the binary array to obtain a decimal array; and performing third conversion processing on the decimal array to obtain an ASCII (American Standard Code for Information Interchange) character group, and determining the ASCII character group as compressed track point data. According to the method, the track point data can be effectively compressed, so that the problems that the data size of the track point data is too large and a large amount of storage space is consumed are solved.

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25-04-2023 дата публикации

Radioactive wet waste drying system and high-temperature gas cooled reactor system

Номер: CN116013568A
Принадлежит:

The invention discloses a radioactive wet waste drying system and a high-temperature gas cooled reactor system.The radioactive wet waste drying system comprises a drying device, a heat exchange device and an exhaust channel, the drying device comprises a drying cavity, and the drying cavity is suitable for containing radioactive wet waste; the drying device is provided with a hot air inlet and a hot air outlet, and the hot air inlet and the hot air outlet are both communicated with the drying cavity; the heat exchange device comprises a heat release side inlet, a heat release side outlet, a cooling medium inlet and a cooling medium outlet; one end of the exhaust channel communicates with the hot air outlet, and the other end of the exhaust channel communicates with the heat release side inlet. Air discharged by the radioactive wet waste drying system does not have radioactivity, and the radioactive wet waste drying system has good safety.

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02-06-2023 дата публикации

Method for realizing laser type ball passing counter of high-temperature gas cooled reactor nuclear power plant

Номер: CN116205264A
Принадлежит:

The invention provides a high-temperature gas cooled reactor nuclear power plant laser type ball passing counter implementation method, and relates to the field of high-temperature gas cooled reactor nuclear power plant fuel loading and unloading. A laser transmitting and receiving device is installed on a shell of the counter, and the laser transmitting and receiving device continuously transmits and receives laser; and the ball passing number of the fuel balls is determined according to the number of the laser pulses received by the laser transmitting and receiving device. Counting of the fuel balls is achieved by improving the counter and installing the laser transmitting and receiving device, the reliability and accuracy of the counter are improved, and calculation of nuclear fuel and reliable operation of a unit are achieved.

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23-06-2023 дата публикации

Deluge alarm valve

Номер: CN116292933A
Принадлежит:

The invention relates to the technical field of fire engineering, in particular to a deluge alarm valve which comprises a valve body and an elastic assembly, the valve body is provided with an inlet, an outlet and a control part, the control part is located between the inlet and the outlet to communicate or block the inlet and the outlet, the control part is provided with a control cavity, and control pressure exists in the control cavity. The elastic assembly is at least partially located in the control cavity and comprises a guide part and an elastic part, the guide part extends in the first direction, one end of the guide part is suitable for being connected with the diaphragm or the end cover, first grooves distributed in the circumferential direction are formed in the outer wall face of the guide part, and the elastic part extends in the first direction. One end of the elastic piece is arranged on the guide piece in a sleeving mode and clamped into the first groove, the other end of ...

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11-04-2023 дата публикации

Method and device for starting sign-in of emergency organization of nuclear power plant

Номер: CN115953853A
Принадлежит:

The invention provides a method and a device for starting sign-in of an emergency organization of a nuclear power plant, relates to the field of nuclear emergency, and is mainly suitable for sign-in of similar nuclear power plant operation units and nuclear power groups when the emergency organization is started. The method comprises the specific steps that a face image of a current person is shot, on-duty time is recorded, and matching is carried out according to the face image to determine a target identity of the current person; determining a target authority according to the target identity, and obtaining a target emergency post corresponding to the target authority according to a current emergency duty table; and generating an emergency response sign-in table according to the target identity, the target emergency post and the arrival time. According to the emergency response sign-in method and device, recognition is carried out according to the face image of the current person to determine ...

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18-04-2023 дата публикации

Implementation method of ultrasonic ball passing counter of high-temperature gas cooled reactor nuclear power plant

Номер: CN115983313A
Принадлежит:

The invention provides a high-temperature gas cooled reactor nuclear power plant ultrasonic ball passing counter implementation method, and relates to the field of high-temperature gas cooled reactor nuclear power plant fuel loading and unloading. An ultrasonic transmitter and an ultrasonic receiver are installed on a shell of the counter, and the ultrasonic transmitter continuously transmits ultrasonic signals; by detecting the number of the ultrasonic grooves which are not received by the ultrasonic receiver, the ball passing number of the fuel balls is determined. Counting of the fuel balls is achieved by improving the counter and installing the ultrasonic transmitter and the ultrasonic receiver, the reliability and accuracy of the counter are improved, and calculation of nuclear fuel and reliable operation of a unit are achieved.

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23-05-2023 дата публикации

Nuclear power plant nuclear grade pipeline thermal stratification monitoring method and system

Номер: CN116153538A
Принадлежит:

The invention provides a nuclear power plant nuclear-grade pipeline thermal stratification monitoring method and system, and the method comprises the steps: obtaining system parameters and historical operation parameters of a primary loop of a nuclear power plant, and determining a thermal stratification risk part based on the system parameters and the historical operation parameters; arranging a plurality of temperature sensors on the outer wall of the pipeline at the thermal stratification risk part according to a preset angle requirement; temperature values collected by all the temperature sensors are obtained, and the difference value of any two temperature values is calculated to obtain the maximum temperature difference; and comparing the maximum temperature difference with the temperature requirement condition to determine a thermal stratification risk condition. According to the method disclosed by the invention, the safety of long-term operation of the nuclear power station is ...

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12-05-2023 дата публикации

Double-layer containment concrete aging state evaluation method

Номер: CN116106123A
Принадлежит:

The invention provides a double-layer containment concrete aging state evaluation method, and relates to the technical field of nuclear power. The method comprises the following steps: respectively arranging a damage detection concrete test block and a special strength measurement concrete test block on an inner-layer containment dome and an outer-layer containment dome of a double-layer containment; obtaining a damage detection result by utilizing the damage detection concrete test block; obtaining a special strength measurement curve by using a special strength measurement concrete test block; carrying out sampling detection on the surface of the inner-layer containment and the surface of the outer-layer containment to obtain a first strength measurement detection result; according to the intensity measurement special curve, calibrating the first intensity measurement detection result to obtain a second intensity measurement detection result; and evaluating the concrete aging state of ...

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14-04-2023 дата публикации

Implementation method of mechanical ball passing counter of high-temperature gas cooled reactor nuclear power plant

Номер: CN115965046A
Принадлежит:

The invention provides a high-temperature gas cooled reactor nuclear power plant mechanical ball passing counter implementation method which is characterized by comprising the steps that a counter is connected with a pipeline through a flange connection structure; a mechanical travel switch is arranged on a shell of the counter; by detecting the action condition of the mechanical travel switch, the ball passing number of the fuel balls is determined according to the number of the falling edges and the number of the rising edges. Counting of the fuel balls is achieved by improving the counter and installing the mechanical travel switch, the reliability and accuracy of the counter are improved, and calculation of nuclear fuel and reliable operation of a unit are achieved.

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30-06-2023 дата публикации

Deluge valve group

Номер: CN116350978A
Принадлежит:

The deluge valve group comprises a deluge valve, the deluge valve comprises a water inlet cavity, a water outlet cavity and a diaphragm cavity, and the water inlet cavity is suitable for being communicated with a fire-fighting pipe network so that water of the fire-fighting pipe network can flow into the water inlet cavity; an inlet of the water inlet pipeline is communicated with the water inlet cavity, and an outlet of the water inlet pipeline is communicated with the diaphragm cavity; an inlet of the water outlet pipeline is communicated with the diaphragm cavity; and at least two of the deluge valve, the water inlet pipeline and the water outlet pipeline are connected through the reinforcing piece. Therefore, the deluge valve set has the advantages of being good in anti-seismic performance and good in reliability.

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23-06-2023 дата публикации

Stop valve

Номер: CN116292934A
Принадлежит:

The invention relates to the technical field of stop valves, in particular to a stop valve which comprises a valve body, a valve clack and a first sealing component, a cavity is formed in the valve body, the valve body is provided with a first opening and a second opening, the valve clack has a first state and a second state, in the first state, the valve clack makes contact with the inner wall face of the valve body so as to seal the first opening and the second opening, and in the second state, the valve clack makes contact with the inner wall face of the valve body. In the second state, the valve clack is far away in the length direction of the valve body to communicate the first opening with the second opening, the first sealing component comprises a C-shaped ring and a fixing piece, the valve body is provided with a first installation groove, the fixing piece is arranged in the first installation groove to be connected with the valve body, the C-shaped ring is provided with an opening ...

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09-05-2023 дата публикации

Method and device for degrading radioactivity level of cooling water of high-temperature gas cooled reactor equipment

Номер: CN116092710A
Принадлежит:

According to the high-temperature gas cooled reactor equipment cooling water radioactivity level degradation method and device and the storage medium provided by the invention, the maximum allowable leakage amount of each user in the at least one user is determined by determining the at least one user causing the release of the radioactive substances to the equipment cooling water system; and according to the maximum allowable leakage amount of each user in the at least one user, calculating the isolation demand time of each user, and performing isolation control on each user based on the isolation demand time of each user. Therefore, according to the high-temperature gas cooled reactor equipment cooling water radioactivity level degradation method provided by the invention, the possibility that an equipment cooling water system is polluted by radioactive substance leakage is reduced, so that the radioactive pollution level is reduced, and the situation that the equipment cooling water ...

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07-07-2023 дата публикации

File generation method, platform and device, electronic equipment and storage medium

Номер: CN116402034A
Принадлежит:

The invention relates to a file generation method, platform and device, electronic equipment and a storage medium, and relates to the technical field of computers. The method comprises the following steps: acquiring a device code of an abnormal device, and acquiring a to-be-executed work content of the abnormal device; querying pre-configured equipment related information according to the equipment code and the working content so as to obtain working file information matched with the equipment code and/or the working content; and generating a work file required for executing maintenance on the abnormal equipment based on the work file information. Therefore, according to the equipment code of the abnormal equipment and the to-be-executed work content, the work file required for executing maintenance on the abnormal equipment is automatically generated, and the work file generation speed is increased.

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27-06-2023 дата публикации

Metal sheet machining tool

Номер: CN116329586A
Принадлежит:

The metal sheet machining tool comprises a first fixing piece and a second fixing piece, the first fixing piece is provided with a boss, the boss is cylindrical, the axial direction of the boss is the first direction, and an annular metal sheet can be arranged on the peripheral side of the boss in a sleeving mode; the second fixing piece and the first fixing piece are oppositely arranged in the first direction, and the second fixing piece can enable a metal sheet to abut against the first fixing piece; the first driving device can drive the first fixing piece to rotate, and the rotating axial direction of the first fixing piece is the first direction; and the tool rest is provided with a tool, the tool rest can drive the tool to move in the second direction, and the first direction is perpendicular to the second direction. Therefore, according to the metal sheet machining tool, cutting of the metal sheet can be reduced conveniently, and the roundness and the size of the outer circle of ...

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16-05-2023 дата публикации

Radiation work risk grade determination method and system based on quantitative analysis

Номер: CN116128300A
Принадлежит:

The invention provides a quantitative analysis-based radiation work risk level determination method and system. The method comprises the following steps of: obtaining radiation risk levels corresponding to items and risk values which have influences on radiation risks; determining each radiation risk quantitative analysis item and a weight corresponding to each radiation risk quantitative analysis item according to each item influencing the radiation risk; establishing a radiation risk analysis model based on each radiation risk quantitative analysis item, the weight corresponding to each radiation risk quantitative analysis item and the radiation risk level corresponding to each risk value; and obtaining working parameter data corresponding to radiation work, and determining a risk level corresponding to the radiation work based on the radiation risk analysis model. According to the technical scheme provided by the invention, the risk level of radiation work of the nuclear power plant ...

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