JP2007113950A - Nuclear power plant - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To provide a nuclear power plant which can heighten the share of electricity generated by nuclear energy in comparison with that generated by thermal power, hydropower and the like. <P>SOLUTION: A control valve 105 is placed in a pipe 118 for supplying the steam generated in a steam generator 113 to a turbine 102. The steam generated in the steam generator 113 during the power generation is supplied to the turbine 102 and then is condensed by a condenser 104. The control valve 105 is allowed to work so that the steam generated in the steam generator 113 when electricity is not generated can be condensed by a condenser 106 without passing through the turbine 102. <P>COPYRIGHT: (C)2007,JPO&INPIT

Description

  The present invention relates to a nuclear power plant, and more particularly to a nuclear power plant that can easily adjust output.

  The demand for electric power changes according to the change of the season, and also changes every moment even within a certain day. The change in the daily power demand has a peak at about 14:00 as shown in FIG.

  On the other hand, since electric power has characteristics that are difficult to store, basically, electric power to be generated is changed according to demand. For this reason, in a general electric power system, power is generated using nuclear power, thermal power, and hydraulic power. As shown in FIG. The amount of generated power is adjusted.

  By the way, power generation methods include those using nuclear power, thermal power, and hydropower, as well as those using wind power, geothermal power, and solar power. However, nuclear power, thermal power, and hydropower that can stably generate power over a certain scale are available. Among the power generation methods by, nuclear power generation can generate power at the lowest price.

  Here, a nuclear power plant that generates power using nuclear power will be described. FIG. 4 is a diagram showing a schematic configuration of a pressurized water (PWR) nuclear power plant, and FIG. 5 is a diagram showing a schematic configuration of a boiling water (BWR) nuclear power plant.

  First, a pressurized water nuclear power plant will be described. A pressurized water nuclear power plant uses water heated in a nuclear reactor, heats water different from this to generate steam, and rotates the turbine with the generated steam to generate power.

  For this reason, in the pressurized water nuclear power plant, the reactor pressure vessel 112 for storing the fuel 110 and the control rod 111 and the steam generator 113 are stored in the reactor containment vessel 101, and both are connected via the tubes 114 and 115. Connected. Further, a pressurizer 116 that applies pressure to water flowing inside is connected to the pipe 114, and a pump 117 for circulating the internal water between the reactor pressure vessel 112 and the steam generator 113 is connected to the pipe 115. Is arranged.

  In the steam generator 113, water circulated between the reactor pressure vessel 112 and the steam generator 113 heats another water to generate steam, and the generated steam is sent to the turbine 102 via the pipe 118. Supply.

  The steam supplied to the turbine 102 is cooled by the condenser 104 and returned to water. The turbine 102 is rotated by the pressure difference generated at this time. When the turbine 102 rotates, the generator 103 coupled with the shaft of the turbine 102 rotates, and the generator 103 generates electric power by this rotation.

  The condenser 104 includes a pipe 140 and a pump 141 for taking cooling water such as seawater used for cooling the steam, a pipe 142 for discharging the cooling water, and a pipe for returning the water obtained by cooling the steam to the steam generator 113. 143 and pump 144.

  Next, the boiling water nuclear power plant will be described. In a boiling water nuclear power plant, water heated in a nuclear reactor is directly boiled, and power is generated by rotating a turbine with steam generated thereby.

  For this reason, in the boiling water nuclear power plant, the reactor pressure vessel 212 for storing the fuel 210 and the control rod 211 is stored in the reactor containment vessel 201. The reactor pressure vessel 212 is provided with a pipe 213 and a pump 214 for circulating internal water. Further, the reactor containment vessel 201 is provided with a pressure suppression pool 215 for suppressing the internal pressure, and water is placed in the inside thereof.

  Water heated in the reactor pressure vessel 212 is supplied to the turbine 202 through a pipe 216 as steam.

  The steam supplied to the turbine 202 is cooled by the condenser 204 and returned to water, and the turbine 202 is rotated by the pressure difference generated at this time. When the turbine 202 rotates, the generator 203 whose shaft is coupled to the turbine 202 rotates, and the generator 203 generates electric power by this rotation.

  The condenser 204 includes a pipe 240 and a pump 241 for taking cooling water such as seawater used for cooling the steam, a pipe 242 for discharging the cooling water, and returning water obtained by cooling the steam to the reactor pressure vessel 212. A tube 243 and a pump 244 are included.

  As described above, nuclear power generation is advantageous in price, but its output (generated power) cannot be easily adjusted. For this reason, the power generation by nuclear power is currently generating only the electric power a shown in FIG. In other words, it is necessary to operate power generated by nuclear power so that its output is below the lower limit of demand forecast.

  Then, an object of this invention is to provide the nuclear power plant which can raise the ratio of the electric power generated by a nuclear power with respect to the electric power generated by a thermal power, a hydropower, etc.

  In order to achieve the above-described object, the invention according to claim 1 is a nuclear power plant that rotates a turbine by steam generated by using heat generated in a nuclear reactor and generates power by a generator connected to the turbine. In the present invention, steam flow control means is provided for condensing after supplying the steam to the turbine during power generation and condensing the steam without going through the turbine during non-power generation.

  According to a second aspect of the present invention, in the first aspect of the invention, the steam flow path control means includes a first steam pipe that guides the steam to the turbine, and the steam from the middle of the first steam pipe. And a second steam pipe for guiding the steam to the condenser, and a contact point between the first steam pipe and the second steam pipe, and the steam is sent to the first steam pipe and the second steam. And a control valve for guiding to either of the pipes.

  The invention of claim 3 is the invention of claim 2, further comprising a second condenser different from the first condenser for condensing steam supplied to the turbine, and the second condenser. The steam pipe guides the steam to the second condenser.

  According to the present invention, it is possible to easily adjust the output of a nuclear power plant, and it is possible to increase the ratio of power generated by nuclear power to power generated by thermal power or hydraulic power.

  Hereinafter, an embodiment of a nuclear power plant according to the present invention will be described in detail with reference to the accompanying drawings.

  FIG. 1 is a diagram showing a schematic configuration of a pressurized water (PWR) nuclear power plant in the first embodiment.

  As shown in the figure, a pressurized water nuclear power plant to which the present invention is applied stores a reactor pressure vessel 112 storing a fuel 110 and a control rod 111 and a steam generator 113 in a reactor containment vessel 101. Are connected via a pipe 114 and a pipe 115. Further, a pressurizer 116 that applies pressure to water flowing inside is connected to the pipe 114, and a pump 117 for circulating the internal water between the reactor pressure vessel 112 and the steam generator 113 is connected to the pipe 115. Is arranged.

  In the steam generator 113, water circulated between the reactor pressure vessel 112 and the steam generator 113 heats another water to generate steam, and the generated steam is sent to the turbine 102 via the pipe 118. Supply.

  The steam supplied to the turbine 102 is cooled by the condenser 104 and returned to water. The turbine 102 is rotated by the pressure difference generated at this time. When the turbine 102 rotates, the generator 103 coupled with the shaft of the turbine 102 rotates, and the generator 103 generates electric power by this rotation.

  The condenser 104 includes a pipe 140 and a pump 141 for taking cooling water such as seawater used for cooling the steam, a pipe 142 for discharging the cooling water, and a pipe for returning the water obtained by cooling the steam to the steam generator 113. 143 and pump 144.

  Further, a control valve 105 is provided on a pipe 118 that supplies steam generated by the steam generator 113 to the turbine 102, and the condenser 106 is connected from the control valve 105 via the pipe 150. The condenser 106 includes a pipe 160 and a pump 161 for taking cooling water such as seawater used for cooling the steam, a pipe 162 for discharging the cooling water, and a pipe for returning the water obtained by cooling the steam to the steam generator 113. 163 and a pump 164, and the pipe 163 is connected to the pipe 143 through the control valve 107.

  The condenser 106 has a sufficient capacity corresponding to the amount of steam that can be generated by the steam generator 113.

  In the pressurized water nuclear power plant shown in FIG. 1, during power generation, the turbine 102 is rotated by the steam generated by the steam generator 113 and the generator 103 is rotated as in the conventional case. Operates the control valve 105 and the control valve 107 to return the steam generated by the steam generator 113 to the water by the condenser 106 without going through the turbine 102 and to return to the steam generator 113. .

  Thus, by operating the control valve 105 and the control valve 107, the pressurized water nuclear power plant to which the present invention is applied can stop power generation without stopping the nuclear reactor.

  FIG. 2 is a diagram illustrating a schematic configuration of a boiling water (BWR) nuclear power plant in the first embodiment.

  As shown in the figure, in a boiling water nuclear power generation plan to which the present invention is applied, a reactor pressure vessel 212 for storing a fuel 210 and a control rod 211 is stored in a reactor containment vessel 201. The reactor pressure vessel 212 is provided with a pipe 213 and a pump 214 for circulating internal water. Further, the reactor containment vessel 201 is provided with a pressure suppression pool 215 for suppressing the internal pressure, and water is placed in the inside thereof.

  Water heated in the reactor pressure vessel 212 is supplied to the turbine 202 through a pipe 216 as steam.

  The steam supplied to the turbine 202 is cooled by the condenser 204 and returned to water, and the turbine 202 is rotated by the pressure difference generated at this time. When the turbine 202 rotates, the generator 203 whose shaft is coupled to the turbine 202 rotates, and the generator 203 generates electric power by this rotation.

  The condenser 204 includes a pipe 240 and a pump 241 for taking cooling water such as seawater used for cooling the steam, a pipe 242 for discharging the cooling water, and returning water obtained by cooling the steam to the reactor pressure vessel 212. A tube 243 and a pump 244 are included.

  In addition, a control valve 205 is provided in a pipe 216 that supplies steam generated in the reactor pressure vessel 212 to the turbine 202, and a condenser 206 is connected from the control valve 205 through the pipe 250. . The condenser 206 includes a pipe 260 and a pump 261 for taking cooling water such as seawater used for cooling the steam, a pipe 262 for discharging the cooling water, and returning water obtained by cooling the steam to the reactor pressure vessel 212. A pipe 263 and a pump 264 are provided, and the pipe 263 is connected to the pipe 243 through the control valve 207.

  The condenser 206 has a sufficient capacity according to the amount of steam that can be generated in the reactor pressure vessel 212.

  In the boiling water nuclear power plant shown in FIG. 2, at the time of power generation, the turbine 202 is rotated by the steam generated in the reactor pressure vessel 212 and the generator 203 is rotated as before, but the power generation is stopped. In this case, the control valve 205 and the control valve 207 are operated, and the steam generated in the reactor pressure vessel 212 is returned to the water by the condenser 206 without going through the turbine 202 and returned to the reactor pressure vessel 212. To work.

  By operating the control valve 205 and the control valve 207 as described above, the pressurized water nuclear power plant to which the present invention is applied can stop power generation without stopping the nuclear reactor.

It is the figure which showed schematic structure of the pressurized water type (PWR) nuclear power plant. It is the figure which showed schematic structure of the boiling water type | mold (BWR) nuclear power plant. It is the figure which showed the example of a change of electric power demand. It is the figure which showed schematic structure of the conventional pressurized water type | mold (PWR) nuclear power plant. It is the figure which showed schematic structure of the conventional boiling water type | mold (BWR) nuclear power plant.

Explanation of symbols

DESCRIPTION OF SYMBOLS 101 Primary containment vessel 102 Turbine 103 Generator 104 Condenser 105 Control valve 106 Condenser 107 Control valve 110 Fuel 111 Control rod 112 Reactor pressure vessel 113 Steam generator 114 Pipe 115 Pipe 116 Pressurizer 117 Pump 118 Pipe 140 Pipe 141 Pump 142 Pipe 143 Pipe 144 Pump 150 Pipe 160 Pipe 161 Pump 162 Pipe 163 Pipe 164 Pump 201 Reactor containment vessel 202 Turbine 203 Generator 204 Condenser 205 Control valve 206 Condenser 207 Control valve 210 Fuel 211 Control rod 212 reactor pressure vessel 213 pipe 214 pump 215 pressure suppression pool 216 pipe 240 pipe 241 pump 242 pipe 243 pipe 244 pump 250 pipe 260 pipe 261 pump 262 pipe 263 pipe 264 pump

Claims (3)

In a nuclear power plant that rotates a turbine with steam generated by using heat generated in a nuclear reactor and generates power with a generator connected to the turbine,
A nuclear power plant comprising steam flow path control means for condensing water after supplying the steam to the turbine during power generation and condensing the steam without going through the turbine during non-power generation. The steam flow path control means includes
A first steam pipe for directing the steam to the turbine;
A second steam pipe for guiding the steam to a condenser from the middle of the first steam pipe;
A control valve disposed at a contact point between the first steam pipe and the second steam pipe, and for guiding the steam to either the first steam pipe or the second steam pipe. The nuclear power plant according to claim 1. A second condenser different from the first condenser for condensing the steam supplied to the turbine;
The nuclear power plant according to claim 2, wherein the second steam pipe guides the steam to the second condenser.

Images