The invention is applicable to the corium localizing and cooling systems of a nuclear reactor designed for localization of severe beyond design-basis accidents, in particular, to the devices for directing corium of a nuclear reactor to the corium trap. The technical result of the claimed invention is to increase the efficiency of localization and cooling of the nuclear reactor core melt.

The goal of the invention is to eliminate the guide assembly failure due to the concentration of impact load in the conical part of the guide assembly and, therefore, the instantaneous penetration of the core, fragments of the reactor vessel internals and the reactor vessel head into the core catcher.

According to the claimed invention, the guide assembly of the nuclear reactor corium localizing and cooling system installed under the reactor vessel and supported on the cantilever truss contains a cylindrical part, a conical part with an opening made in it, with their walls covered with heat-resistant and fusible material and divided into sectors by bearing ribs arranged radially relative to the opening, and a bearing frame consisting of the outer upper bearing ring, the outer lower bearing ring, the inner bearing shell, the outer upper bearing shell, the middle bearing shell divided into sectors by bearing ribs, the outer lower bearing shell, support ribs, base, upper inclined plate connecting the conical head, bearing ribs and the middle bearing shell, lower inclined plate connecting the conical head, bearing ribs, the middle bearing shell and the outer upper bearing shell.

3 claims, 4 figures of drawings

The invention is applicable to the corium localizing and cooling systems of a nuclear reactor designed for localization of severe beyond design-basis accidents, in particular, to the devices for directing corium of a nuclear reactor to the corium trap. The technical result of the claimed invention is to increase the efficiency of localization and cooling of the nuclear reactor core melt.

The goal of the invention is to eliminate the guide assembly failure due to the concentration of impact load in the conical part of the guide assembly and, therefore, the instantaneous penetration of the core, fragments of the reactor vessel internals and the reactor vessel head into the core catcher.

According to the claimed invention, the guide assembly of the nuclear reactor corium localizing and cooling system installed under the reactor vessel and supported on the cantilever truss contains a cylindrical part, a conical part with an opening made in it, with their walls covered with heat-resistant and fusible material and divided into sectors by bearing ribs arranged radially relative to the opening, and a bearing frame consisting of the outer upper bearing ring, the outer lower bearing ring, the inner bearing shell, the outer upper bearing shell, the middle bearing shell divided into sectors by bearing ribs, the outer lower bearing shell, support ribs, base, upper inclined plate connecting the conical head, bearing ribs and the middle bearing shell, lower inclined plate connecting the conical head, bearing ribs, the middle bearing shell and the outer upper bearing shell.

3 claims, 4 figures of drawings

A high-temperature containment-isolation system for transferring heat from a nuclear reactor containment to a high-pressure heat exchanger is presented. The system uses a high-temperature, low-volatility liquid coolant such as a molten salt or a liquid metal, where the coolant flow path provides liquid free surfaces a short distance from the containment penetrations for the reactor hot-leg and the cold-leg, where these liquid free surfaces have a cover gas maintained at a nearly constant pressure and thus prevent high-pressures from being transmitted into the reactor containment, and where the reactor vessel is suspended within a reactor cavity with a plurality of refractory insulator blocks disposed between an actively cooled inner cavity liner and the reactor vessel.

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 consists in increasing the reliability of the corium localizing and cooling system of a nuclear reactor, increase of heat removal efficiency from corium of a nuclear reactor.

The technical result is achieved by using the membraned, drum and thermal protection installed in the area between the layered vessel and cantilever truss in the corium localizing and cooling system of a nuclear reactor.

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 consists in increasing the reliability of the corium localizing and cooling system of a nuclear reactor, increase of heat removal efficiency from corium of a nuclear reactor.

The technical result is achieved by using the membraned, drum and thermal protection installed in the area between the layered vessel and cantilever truss in the corium localizing and cooling system of a nuclear reactor.

The present disclosure relates to a radioactive material reduction facility, including a containment, a boundary section provided inside the compartment to partition an inner space of the containment into a first space for accommodating a reactor coolant system and a second space formed between the first space and the containment, and surround the reactor coolant system to prevent radioactive material discharged from the reactor coolant system or a line connected to the reactor coolant system inside the first space from being directly discharged into the second space during an accident, an in-containment refueling water storage tank (IRWST) installed between the first space and the second space and formed to accommodate refueling water, and a first discharge line formed to guide the flow of steam and radioactive material formed in the first space inside the boundary section into the in-containment refueling water storage tank. Specifically, the radioactive material reduction facility according to the present disclosure may include a plurality of pools separated from each other, and the plurality of pools may include at least a first pool and a second pool, and the steam and the radioactive material may be discharged to the second pool through the first pool during an accident.

The present disclosure relates to a radioactive material reduction facility, including a containment, a boundary section provided inside the compartment to partition an inner space of the containment into a first space for accommodating a reactor coolant system and a second space formed between the first space and the containment, and surround the reactor coolant system to prevent radioactive material discharged from the reactor coolant system or a line connected to the reactor coolant system inside the first space from being directly discharged into the second space during an accident, an in-containment refueling water storage tank (IRWST) installed between the first space and the second space and formed to accommodate refueling water, and a first discharge line formed to guide the flow of steam and radioactive material formed in the first space inside the boundary section into the in-containment refueling water storage tank. Specifically, the radioactive material reduction facility according to the present disclosure may include a plurality of pools separated from each other, and the plurality of pools may include at least a first pool and a second pool, and the steam and the radioactive material may be discharged to the second pool through the first pool during an accident.

The invention relates to nuclear power engineering and is designed to improve the safety of nuclear power plants by providing the ability to retain the melt in the nuclear reactor vessel at different severity of accidents in both passive and active mode.

In-vessel melt retention system containing a reactor located in a cavity, a coolant circulation pump outside the reactor vessel and a storage tank, characterized in that the storage tank is located in the cavity under the reactor vessel head; there are additional sump tanks above the reactor vessel head to collect coolant in LOCAs, the storage tank is connected to the top of the sump tanks by coolant supply channels.

The in-vessel melt retention system can be applied in nuclear power plants of various types, and can increase their safety by providing melt retention in the reactor vessel in various types of accidents.

The invention relates to nuclear power engineering and is designed to improve the safety of nuclear power plants by providing the ability to retain the melt in the nuclear reactor vessel at different severity of accidents in both passive and active mode.

In-vessel melt retention system containing a reactor located in a cavity, a coolant circulation pump outside the reactor vessel and a storage tank, characterized in that the storage tank is located in the cavity under the reactor vessel head; there are additional sump tanks above the reactor vessel head to collect coolant in LOCAs, the storage tank is connected to the top of the sump tanks by coolant supply channels.

The in-vessel melt retention system can be applied in nuclear power plants of various types, and can increase their safety by providing melt retention in the reactor vessel in various types of accidents.

A heat exchanger includes a body having an inlet header through which a fluid is introduced, and an outlet header through which the fluid is discharged; and one or more plates accommodated in the body and provided with flow path modules providing flow paths for the fluid introduced through the inlet header to flow to the outlet header. The heat exchanger further includes at least one flow path adjuster each having at least a portion thereof accommodated in the body and being movable or rotatable to open or close a part or all of the flow paths or to change directions of the flow paths so that a flow of the fluid is adjusted.