摘要:
The invention relates to the field of nuclear energy, in particular, to systems that ensure the safety of nuclear power plants (NPP), and can be used in severe accidents that lead to reactor pressure vessel and its containment destruction. The technical result of the claimed invention is to increase the safety of a nuclear power plant by excluding the release of liquid and solid radioactive materials (corium) outside the device for confining core melt in the event of a severe accident with the core melt discharge out of the nuclear reactor. The object of the current invention is to improve the efficiency and reliability of the the device for confining core melt by improving the corium cooling conditions. The set object is solved based on the use of the filler formed in the cassettes, the upper and the lower ones. The cassettes have vertical and horizontal channels that ensure uniform distribution of the melt in the cooled body.
摘要:
The invention relates to nuclear engineering, in particular, to systems that ensure the safety of nuclear power plants (NPP), and can be used in severe accidents that lead to the core meltdown, nuclear reactor pressure vessel destruction and the release of the melt into the space of the NPP containment. The technical result is the increase of the reliability of the water-cooled water-moderated nuclear reactor core melt cooling and confinement system. The object to be solved by the claimed invention is to increase the efficiency of heat removal from the melt and increase the structure reliability. The designated object is solved by using the damper installed inside the melt trap body as part of the water-cooled water-moderated nuclear reactor core melt cooling and confinement system.
摘要:
The invention relates to nuclear power industry, namely to systems providing safety of nuclear power plants (NPP), and can be used during severe accidents leading to reactor vessel and NPP containment failure. The melt cooling and confinement system includes a cone-shaped guide plate installed under the reactor vessel bottom, cantilever girder installed under the guide plate and supporting the same, core catcher installed under the cantilever girder and equipped with cooled cladding in form of a multi-layer vessel for protection of the external heat-exchange wall from dynamic, thermal and chemical impacts, and filler material for melt dilution inside the multi-layer vessel. The said multi-layer vessel contains internal and external metal layers with an intermediate layer in the form of a non-metal filler located in between. Bearing ribs are installed between the internal and external layers at an azimuth pitch (S pitch ) that meets the following criterion: d ext /15
摘要:
If a molten core holding apparatus (core catcher) is disposed below a reactor pressure vessel in a reactor containment vessel, water leak cannot be detected at a pedestal floor. Thus the reactor containment vessel has to be separately equipped with a mechanism for detecting the water leak. A water leak detection floor (11) transversally suspended by a pedestal side wall (22) is installed between a reactor pressure vessel (1) and a molten core holding apparatus (10). If a water leak occurs at the reactor pressure vessel (1), the water leak detection floor receives and detects the leak water. In a core meltdown accident, corium melts and penetrates the water leak detection floor and deposits on the molten core holding apparatus.
摘要:
There is provided a molten corium holding device which can hold a molten corium for a predetermined period even when the molten corium is exposed to heat or undergoes any chemical reaction and which is applicable to practical use. The molten corium holding device which is to be arranged below a reactor pressure vessel. There is provided a molten corium holding device provided below a nuclear reactor pressure vessel, wherein the holding device is configured to include, on a base material in contact with a cooling medium, a multilayer stack structure composed of a first heat-resistant layer, a second heat-resistant layer formed on the first heat-resistant layer and low in heat conductivity than the first heat-resistant layer, and a corrosion-resistant impact-absorbing layer formed on the second heat-resistant layer.
摘要:
An object is to provide a corium cooling structure that is capable of accumulating corium and debris that have flowed out from a reactor in small divided portions and of sufficiently cooling the high-temperature corium and debris, a reactor containment vessel provided with the same, and a nuclear power plant provided with the same. A capture portion (62) that captures the corium that has flowed out from a reactor (12) and a plurality of pipe portions (63) that are provided in a coolant storing portion (56) and into which the corium flows via the capture portion (62) are provided.
摘要:
An embodiment of a nuclear power plant has: a reactor vessel (11) containing a core (10); a reactor containment vessel (12) containing the reactor vessel (12); and a radiation heat reflecting member (30) disposed at a portion below the reactor vessel (11) inside the reactor containment vessel (12). The radiation heat reflecting member (30) may block radiation heat, which is emitted toward a side wall surface (23) of the reactor containment vessel (12) from the core (31) that has been put in a molten state by an accident and flowed downward from the reactor vessel (11) to be accumulated at a lower portion (19) of the reactor containment vessel (12). The radiation heat reflecting member (47) may block radiation heat, which is emitted toward a supporting structure (42) supporting devices (44) disposed inside the reactor containment vessel (12).
摘要:
The invention relates to a nuclear fuel assembly comprising: a housing (2) defining an inner space divided into a central portion (10), referred to as a fissile area, in which a bundle of nuclear fuel pins (11) is arranged, an upper portion (14), and a lower portion (12); a lower end comprising a coolant supply inlet; an upper end comprising a coolant discharge outlet; the pins of the bundle of pins comprising an upper plenum and/or lower plenum; means (18) for placing the lower portion (12) of the inner space of the housing in communication with the area (20) surrounding the assembly, referred to as the interconnecting area through the wall of the housing (2), said means being sealed below a given pressure threshold in the inner portion; and upper neutron protection means (22.1) inside the housing.