Patent Application
20160196886
The present invention relates to a reactor cooling system.
In a nuclear power plant (e.g., a boiling-water nuclear power plant), even after an operation stop, it is necessary to supply cooling water and cool a reactor core in order to remove decay heat generated in the reactor core. Usually, after the operation stop of the nuclear power plant, a part of the cooling water in a reactor pressure vessel (RPV) is discharged to a pipe connected to the RPV, the discharged cooling water is cooled by exchanging heat with seawater in a heat exchanger connected to the pipe, and the cooled cooling water is returned to the RPV through a return pipe. In this way, after the operation stop of the nuclear power plant, the decay heat of the reactor core is allowed to escape to the seawater using the heat exchanger.
An electric pump is used for supply of the cooling water in the RPV to the heat exchanger and supply of the seawater to the heat exchanger. Electric power for driving the electric pump is necessary for the removal of the decay heat after the nuclear power plant stop. When an abnormal event of a loss of an external power supply occurs during the stop of the nuclear power plant, an emergency generator is driven for supply of electricity to the electric pump, and the removal of the decay heat during the stop of the nuclear power plant is performed.
On the other hand, assuming that, although a probability is extremely low, a loss of power supply from the outside and a multiple failure of dynamic components overlap, there has been proposed a passive cooling system that makes use of a natural force such as the gravity.
For example, JP-T-9-508700 proposes a passive cooling system that emits heat from a primary containment vessel (PCV) to the atmosphere. The passive cooling system is a system in which heat exchangers are set in the PCV and on the atmosphere side, the heat exchangers are connected by a pipe through which a coolant passes, and heat is transported making use of boiling and condensation of the coolant.
PTL 1: JP-T-9-508700
In PTL 1, the heat exchanger is set in the PCV. However, when the heat exchanger is set in a RPV, there are problems described below.
When heat in the RPV is transported to the outside of the RPV by the heat exchanger during power supply loss, since the coolant is sent to the heat exchanger, a pipe piercing through the RPV is necessary. It is necessary to periodically inspect the heat exchanger. When the heat exchanger is set in a RPV main body, it is necessary to provide a connecting section to the pipe, which pierces through the RPV, inside the RPV to enable detachment of the heat exchanger for inspection and repair. After reactor operation, an operator cannot enter the RPV. Therefore, it is necessary to remotely perform detachment and recovery work. Time and costs are required.
Slight condensed water is generated by a heat leak from an in-vessel heat exchanger during normal operation. If the condensed water is mixed in main steam, it is likely that heat efficiency is deteriorated.
It is an object of the present invention to easily perform inspection and repair of a reactor cooling system that can cool a reactor for a long time without requiring electric power.
In the present invention, the in-vessel heat exchanger is fixed on the inner side of an upper lid of the RPV, one of through-pipes piecing through the upper lid is connected to the in-vessel heat exchanger and the other side forms a connection element on the outer side of the upper lid.
According to the present invention, it is extremely easy to perform inspection and repair of a reactor cooling system that can cool a reactor for a long period without requiring electric power.
Problems, configurations, and effects other than those explained above are made clear by the following explanation of embodiments.
In a nuclear power plant, since decay heat is generated from a reactor core even after a stop, it is necessary to allow the decay heat to escape to a heat sink such as the atmosphere or the seawater. A cooling system provided by the present invention is a passive facility. The cooling system can cool a reactor even if power supply is lost for a long time. Embodiments for facilitating setting and maintenance of the cooling facility in the present invention are explained below.
An embodiment of the present invention is explained with reference to
In
If a power-driven cooling facility stops because of a power supply loss or the like and it is necessary to cool the reactor with the cooling facility provided by the present invention, the valve 4 is opened and the coolant is fed to the in-vessel heat exchanger 2. The coolant flowed into the in-vessel heat exchanger 2 is heated and boiled by steam in the RPV 1 to change to steam and moves to the air-cooling heat exchanger 5. In the air-cooling heat exchanger 5, the coolant is cooled by natural convection of the air to return to liquid. Since the air-cooling heat exchanger 5 is set in a position higher than the in-vessel heat exchanger 2, the coolant flows into the in-vessel heat exchanger 2 again with the gravity. In this way, after the valve 4 is opened, this cooling cycle continues without power by a natural phenomenon. The steam, from which heat is deprived by the coolant in the in-vessel heat exchanger 2, condenses to return to water and moves to the reactor core. The heat generated in the reactor core is emitted to the atmosphere in this way.
In
During a periodical inspection, the through-pipes 32 and the pipes 31c are disconnected by the connection elements 3 and the upper lid 10 of the RPV 1 is detached. The upper lid 10 are detached from a RPV main body together with in-vessel heat exchangers 2 and stored in a work area of a reactor building 7. The in-vessel heat exchangers 2 are present in a work floor together with the upper lid 10. Therefore, an operator can perform the periodical inspection/repair during the storage with visual observation or the like while performing exposure management.
On the other hand, when the in-vessel heat exchangers 2 are connected to the RPV main body (the “RPV main body” indicates a body portion of a lower part excluding the upper lid 10 in the RPV), in order to configure a mechanism for removing only the in-vessel heat exchangers 2 from the inside of the RPV 1 for inspection/repair, it is necessary to set connection elements between the RPV 1 and the in-vessel heat exchangers 2. During the periodical inspection, the RPV 1 is submerged in order to block a radiation. Therefore, to disconnect the connection elements, a machine that performs remote operation underwater is necessary. Costs and time are required for the inspection/repair.
Therefore, the inspection/repair is remarkably facilitated by attaching the in-vessel heat exchanger to the upper lid 10 as in this embodiment.
A second embodiment of the present invention is explained with reference to
On heat transfer pipe surfaces of the in-vessel heat exchangers 2, steam generated in the RPV 1 is condensed, dropped by the gravity, and returned to water in the RPV. Even during normal operation in which the cooling system is not operating, a heat leak to the outside of the RPV 1 occurs a little via the in-vessel heat exchangers 2. At this point, condensed water is generated. In a steam space in the RPV 1, flows toward main steam pipes 9 are generated. When the condensed water generated by the heat leak is captured by the flows of the steam and mixed in the main steam, it is likely that heat efficiency is deteriorated a little.
Therefore, in this embodiment, with respect to the circumferential direction of the RPV 1, the in-vessel heat exchangers 2 are prevented from being disposed right above main steam pipe inlets where the main steam pipes 9 are attached to the RPV 1. That is, by setting the in-vessel heat exchanges 2 in positions shifted from right above the main steam pipe introduction ports, the condensed water generated by the heat leak is suppressed from flowing into the main steam pipes 9. Consequently, it is possible to reduce the likelihood of the heat efficiency deterioration.
A third embodiment of the present invention is explained with reference to
On the heat transfer pipe surfaces of the in-vessel heat exchangers 2, the steam in the RPV 1 condenses and liquid films are generated. In condensation heat transfer, the liquid films have large heat resistance and affect a heat exchange amount. When a plurality of heat transfer pipes are set in the steam, the steam enters from gaps among the heat transfer pipes in various places. It is likely that the generated liquid films are not efficiently discharged to the outside of the heat exchangers. In this case, the liquid films having the large heat resistance tend to remain in the heat exchangers. Therefore, it is likely that a heat exchange amount of the heat exchangers decreases.
In this embodiment, covers 11 that are opened in upper and lower parts and cover side surfaces of the in-vessel heat exchangers 2 are set. With the covers 11, the steam flows along the heat transfer pipes from up to down. The steam flowed into the insides of the covers 11 from above the heat transfer pipes condenses on the heat transfer pipe surfaces. A condensed water amount increases downward and the liquid films become thicker. Inside the covers, the condensed water can be efficiently discharged from the in-vessel heat exchangers by stable steam flows flowing from up to down. It is possible to reduce the size of the in-vessel heat exchangers.
A fourth embodiment of the present invention is explained with reference to
As explained in the second embodiment, the condensed water is generated from the in-vessel heat exchangers 2 by the heat leak even during the normal operation. If the condensed water is mixed in the main steam, it is likely that the heat efficiency is deteriorated.
In this embodiment, lower outlets of the covers 11, which cover the in-vessel heat exchangers 2, are coupled to upper inlets of condensed water channels 12 attached to the main body side of the RPV 1. Lower outlets of the condensed water channels 12 are located further on the lower side than a water level in the RPV 1 during the normal operation. The condensed water generated in the in-vessel heat exchangers 2 is discharged from the in-vessel heat exchangers 2 and then flows down along the covers 11. Further, the condensed water is returned to the water through the condensed water channels 12. At this point, since the condensed water is not exposed to the steam space in the RPV, the condensed water is not mixed in the main steam. It is possible to eliminate the likelihood of the heat efficiency deterioration due to the mixing of the condensed water in the main steam.
In this embodiment, setting of in-vessel heat exchangers in an existing nuclear power plant is explained. The configuration of a cooling system is the same as the configuration shown in
When the in-vessel heat exchangers 2 are set in the upper lid 10 of the RPV 1, through-holes, through which the pipes 32 for feeding the coolant are inserted, are machined in the detached upper lid 10. Since the upper lid 10 is placed on the work floor, underwater work is unnecessary. The pipes 32 are inserted through the through-holes, the in-vessel heat exchangers 2 are set on the inner side of the upper lid 10, and the connection elements 3 such as flanges are attached to the pipes 32 on the outer side of the upper lid 10. The connection elements 3 are connected to the pipes 31 connected to the air-cooling heat exchangers 5 set anew. When the in-vessel heat exchangers 2 are set on the inside of the upper lid 10, it is possible to easily carry out work without requiring underwater work.
On the other hand, when the in-vessel heat exchangers 2 are set in the main body of the RPV 1, because of a reason explained below, costs increase compared with when the in-vessel heat exchangers 2 are set in the upper lid 10. First, it is necessary to machine a through-hole through which a pipe for feeding the coolant is inserted in the main body of the RPV 1. However, since a radiation is strong in the RPV after operation, the radiation needs to be blocked by water. The machining needs to be performed underwater and by remote control. The setting of the in-vessel heat exchangers and the pipes also needs to be performed underwater and by remote control. Therefore, setting costs increase.
When the passive cooling system provided by the present invention is introduced into an existing plant, it is possible to set the cooling system at low costs by applying the present invention.
Note that the present invention is not limited to the embodiments explained above. Various modifications are included in the present invention. For example, the embodiments are explained in detail in order to plainly explain the present invention. The embodiments are not always limited to embodiments including all of the explained configurations. A part of the configuration of a certain embodiment can be replaced with the configuration of another embodiment. The configuration of another embodiment can also be added to the configuration of a certain embodiment. The configuration of another embodiment can be added to, deleted from, and replaced with a part of the configurations of the embodiments.
The cooling system of the present invention is applied to a nuclear power plant.
| Filing Document | Filing Date | Country | Kind |
|---|---|---|---|
| PCT/JP2013/071679 | 8/9/2013 | WO | 00 |
