Настройки

Укажите год
-

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

Подробнее
-

Мониторинг СМИ

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

Подробнее

Форма поиска

Поддерживает ввод нескольких поисковых фраз (по одной на строку). При поиске обеспечивает поддержку морфологии русского и английского языка
Ведите корректный номера.
Ведите корректный номера.
Ведите корректный номера.
Ведите корректный номера.
Укажите год
Укажите год

Применить Всего найдено 6. Отображено 6.
21-05-2014 дата публикации

Pre-commissioning preparation method of nuclear power station waste heat discharging system

Номер: CN103811084A
Принадлежит:

The invention provides a pre-commissioning preparation method of a nuclear power station waste heat discharging system, which aims at solving the problem that sampling and detecting are carried out to obtain boron concentration before a waste heat discharging system in the prior art puts into operation. The preparation method comprises the following steps of boosting, heating and adjusting boron concentration. In the step of adjusting the boron concentration, the boron concentration in a coolant system of a reactor is directly adjusted, so that the increment value of the boron concentration in the coolant system of the reactor is a concentration variable delta M, and after the waste heat discharging system is connected with the coolant system of the reactor, the boron concentration in the waste heat discharging system and a reactor coolant system loop is greater than or equal to that stipulated by the technical specification. By adopting the method, the defects in the prior art that sampling ...

Подробнее
15-12-2010 дата публикации

Device and system for vacuum-pumping loop of pressurized water reactor of nuclear power station

Номер: CN0101916596A
Принадлежит:

The invention discloses a device for vacuum-pumping a loop of a pressurized water reactor of a nuclear power station, for vacuum-pumping the loop comprising a reactor pressure container, a pressure stabilizer and a steam generator. The vacuum-pumping device is respectively communicated with the reactor pressure container and the pressure stabilizer so as to form a sealed pumping loop. The vacuum-pumping device comprises a vacuum-pumping frame which is accessed into the sealed pumping loop so as to separate water from steam in the sealed pumping loop. The invention also discloses a system for vacuum-pumping a loop of a pressurized water reactor of a nuclear power station. The device and the system of the invention can be connected to a loop so as to form the sealed pumping loop and separate water from steam in the sealed pumping loop, therefore promoting the running economical efficiency of the nuclear power station and decreasing the abrasion ratio of the device in the loop.

Подробнее
15-12-2010 дата публикации

Method for vacuumizing and exhausting reactor primary circuit of pressurized water reactor nuclear power station

Номер: CN0101916595A
Принадлежит:

The invention discloses a method for vacuumizing and exhausting a reactor primary circuit of a pressurized water reactor nuclear power station. The reactor primary circuit of the pressurized water reactor nuclear power station comprises a reactor coolant system main pump, a steam generator, a voltage stabilizer and a reactor pressure vessel which are communicated through a main pipeline. The method comprises the following steps of: extracting gas from the reactor primary circuit until the air pressure of the reactor primary circuit reaches a preset vacuum standard; and supplementing water to the reactor primary circuit until the water level of the reactor pressure vessel at least exceeds the upper surface of the main pipeline. The method for vaccumizing and exhausting the reactor primary circuit of the pressurized water reactor nuclear power station has the advantages of shortening the overhaul time of the pressurized water reactor nuclear power station, effectively reducing the abrasion ...

Подробнее
30-05-2023 дата публикации

Data processing method and device and storage medium

Номер: CN116185388A
Принадлежит:

The invention provides a data processing method and device and a storage medium, and relates to the technical field of industrial internet. The method comprises the following steps: collecting and converging heterogeneous multi-source OT data and IT data to form a model database; packaging the data in the model database into various types of industrial models; and calling the corresponding industrial model according to the application development requirement to construct the application. According to the method, the data development difficulty can be reduced, the development time is shortened, configuration personnel of all departments of an enterprise can quickly complete application development with different complexity and different application types in a quality-guaranteeing manner, the development cost is reduced, and service requirements are quickly responded.

Подробнее
21-05-2014 дата публикации

Safety injection system of nuclear power station and method for clearing injection pipeline

Номер: CN103811083A
Принадлежит:

The invention provides a safety injection system of a nuclear power station and a method for clearing an injection pipeline. The clearing method comprises the steps of pressurizing the inside of a medium-pressure injection tank, switching on an isolation valve, and rinsing the injection pipeline under the effect of the pressure difference. By adopting the method for rinsing the injection pipeline of the medium-pressure injection tank of the nuclear power station, corrosive precipitate in the pipeline can be obviously removed, the sealing property of a check valve can be greatly improved, the repairing times and the personnel radiation dosage can be reduced, the major repair of the nuclear power station can be avoided, and the overhauling of the check valve at a low level can be avoided.

Подробнее