WO2023187898A1 - Nuclear power system and control method therefor - Google Patents
Nuclear power system and control method therefor Download PDFInfo
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- WO2023187898A1 WO2023187898A1 PCT/JP2022/014989 JP2022014989W WO2023187898A1 WO 2023187898 A1 WO2023187898 A1 WO 2023187898A1 JP 2022014989 W JP2022014989 W JP 2022014989W WO 2023187898 A1 WO2023187898 A1 WO 2023187898A1
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- 238000000034 method Methods 0.000 title claims description 20
- 239000001257 hydrogen Substances 0.000 claims abstract description 181
- 229910052739 hydrogen Inorganic materials 0.000 claims abstract description 181
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims abstract description 176
- 238000004519 manufacturing process Methods 0.000 claims abstract description 99
- 230000005611 electricity Effects 0.000 claims abstract description 88
- 238000010248 power generation Methods 0.000 claims abstract description 85
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 40
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 claims description 16
- 239000001301 oxygen Substances 0.000 claims description 16
- 229910052760 oxygen Inorganic materials 0.000 claims description 16
- 150000002431 hydrogen Chemical class 0.000 claims description 4
- 230000003247 decreasing effect Effects 0.000 claims 2
- 230000007774 longterm Effects 0.000 claims 2
- 239000002826 coolant Substances 0.000 description 8
- 230000001276 controlling effect Effects 0.000 description 7
- 230000000694 effects Effects 0.000 description 5
- 238000005868 electrolysis reaction Methods 0.000 description 5
- 239000007789 gas Substances 0.000 description 3
- 238000009835 boiling Methods 0.000 description 2
- 230000007423 decrease Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 230000001105 regulatory effect Effects 0.000 description 2
- 239000007787 solid Substances 0.000 description 2
- 239000000446 fuel Substances 0.000 description 1
- 125000004435 hydrogen atom Chemical group [H]* 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 229920000642 polymer Polymers 0.000 description 1
- 238000000746 purification Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D9/00—Arrangements to provide heat for purposes other than conversion into power, e.g. for heating buildings
Definitions
- the nuclear power generation system of this embodiment includes a nuclear reactor 1, a turbine 2 that rotates with the steam generated in the reactor 1, and a turbine 2 that rotates with the driving force accompanying the rotation of the turbine 2 and generates electricity.
- a generator 3 outputs electricity (A) to the power grid, and a part of the electricity (electricity (B)) generated by this generator 3 is stored, and this stored electricity (electricity (C)) is used as electricity.
- a storage battery 6 that outputs to the grid, a hydrogen production machine 4 that produces hydrogen using part of the steam (steam (D)) generated in the reactor 1 as a heat source, and a hydrogen production machine 4 that stores the hydrogen produced by this hydrogen production machine 4.
- a hydrogen storage device 5 (the hydrogen stored in the hydrogen storage device 5 is traded on the market or transported to a purchaser); a condenser 7 that cools the steam from the turbine 2 and returns it to water; It is generally composed of a feed water heater 8 in which water from the condenser 7 is supplied, heated, and circulated to the nuclear reactor 1. Note that the condenser 7 is supplied with heat from the hydrogen production machine 4.
- the hydrogen producing machine 4 of this embodiment shown in FIG. 5 is a further improvement of the hydrogen producing machine 4 of the third embodiment shown in FIG.
Abstract
In order to maintain constant reactor-core output while also supplying electrical output that responds to long-period and short-period fluctuations in demand, the present invention is characterized in being provided with: a nuclear reactor; a turbine that rotates under steam generated in the nuclear reactor; a generator that rotates under drive force accompanying the rotation of the turbine to generate electricity and output same to a power grid; a storage battery that stores a portion of the electricity generated by the generator and that outputs the stored electricity to the power grid; a hydrogen production machine that produces hydrogen utilizing as a heat source a portion of the steam generated in the nuclear reactor; a hydrogen storage container that stores hydrogen produced by the hydrogen production machine; and a control device that, in response to fluctuations in demand, controls how the use of the steam generated in the nuclear reactor is allocated to power generation in the generator, hydrogen production in the hydrogen production machine, and electricity storage in the storage battery.
Description
本発明は原子力発電システム及びその制御方法に係り、特に、原子炉で発生した蒸気の一部を熱源として用いて水素を製造するものに好適な原子力発電システム及びその制御方法に関する。
The present invention relates to a nuclear power generation system and its control method, and in particular to a nuclear power generation system and its control method suitable for producing hydrogen using a portion of steam generated in a nuclear reactor as a heat source.
原子力発電システムにおいて、原子炉で発生した蒸気の一部を熱源として用いて水素を製造する先行技術文献として特許文献１がある。
In a nuclear power generation system, there is Patent Document 1 as a prior art document in which hydrogen is produced using a portion of steam generated in a nuclear reactor as a heat source.
この特許文献１には、原子炉の冷却材が導管を経て蒸気発生器に導かれ、この蒸気発生器内で間接的な熱交換により蒸気を発生させ、この発生した蒸気を蒸気タービンに導くが、一部の蒸気は蒸気導管を介して水素精製ユニットに導入されて水素を製造する発電設備が記載されている。
In this Patent Document 1, coolant of a nuclear reactor is guided to a steam generator through a conduit, steam is generated by indirect heat exchange within the steam generator, and the generated steam is guided to a steam turbine. , a power generation facility is described in which some steam is introduced via a steam conduit to a hydrogen purification unit to produce hydrogen.
近年原子力発電システムにおいて負荷追従運転に対応することが求められている。さらに今後は炉心出力を一定に保持しながら、異なる２つの周期の需要変動（長周期的、短周期的）に対応する電気出力を供給する高度な負荷追従運転が要求される可能性がある。
In recent years, nuclear power generation systems have been required to support load following operation. Furthermore, in the future, there is a possibility that sophisticated load-following operation will be required to maintain a constant core output while supplying electrical output that corresponds to two different cycles of demand fluctuations (long-cycle and short-cycle).
ところが、短周期的な需要変動に対しては、炉心の熱出力制御は、燃料棒の伝熱特性に支配されるため、応答速度に限界があり、また、長周期的な需要変動に対しては、蓄電池では、蓄電池の放電ロスにより調整力を維持することが困難となる、といった課題がある。
However, in response to short-term demand fluctuations, core thermal output control is governed by the heat transfer characteristics of the fuel rods, so there is a limit to response speed; The problem with storage batteries is that it becomes difficult to maintain adjustment power due to discharge loss of the storage batteries.
しかしながら、上述した特許文献１に記載されている発電設備には、短周期的な需要変動及び長周期的な需要変動に対しての課題に対する解決策に関しては何も記載されていない。
However, the power generation equipment described in Patent Document 1 mentioned above does not describe any solutions to the problems of short-period demand fluctuations and long-period demand fluctuations.
本発明は上述の点に鑑みなされたもので、その目的とするところは、炉心出力を一定に保持しながら長周期的、短周期的の需要変動に対応する電気出力を供給することができる原子力発電システム及びその制御方法を提供することにある。
The present invention has been made in view of the above points, and its purpose is to provide a nuclear power plant capable of supplying electrical output corresponding to long-period and short-period demand fluctuations while maintaining a constant core output. An object of the present invention is to provide a power generation system and a control method thereof.
本発明の原子力発電システムは、上記目的を達成するために、原子炉と、該原子炉で発生した蒸気で回転するタービンと、該タービンの回転に伴う駆動力で回転して発電し電力系統へ出力する発電機と、該発電機で発電した電気の一部を蓄電し、この蓄電した電力を電力系統へ出力する蓄電池と、前記原子炉で発生した蒸気の一部を熱源として用いて水素を製造する水素製造機と、該水素製造機で製造した水素を貯蔵する水素貯蔵器と、前記原子炉での発生蒸気の用途を前記発電機での発電、前記水素製造機での水素製造、前記蓄電池での電気の蓄電に、どのように配分するかを需要変動に応じて制御する制御装置と、を備えていることを特徴とする。
In order to achieve the above object, the nuclear power generation system of the present invention includes a nuclear reactor, a turbine that rotates using steam generated in the nuclear reactor, and a driving force generated by the rotation of the turbine that rotates to generate electricity and send it to the power grid. A generator that outputs electricity, a storage battery that stores a part of the electricity generated by the generator and outputs this stored electricity to the power grid, and a part of the steam generated in the reactor that is used as a heat source to produce hydrogen. A hydrogen production machine to produce hydrogen, a hydrogen storage device to store the hydrogen produced by the hydrogen production machine, and uses of the steam generated in the nuclear reactor to generate electricity in the generator, hydrogen production in the hydrogen production machine, and The present invention is characterized by comprising a control device that controls how to allocate electricity stored in a storage battery according to demand fluctuations.
また、本発明の原子力発電システムの制御方法は、上記目的を達成するために、原子炉と、該原子炉で発生した蒸気で回転するタービンと、該タービンの回転に伴う駆動力で回転して発電し電力系統へ出力する発電機と、該発電機で発電した電気の一部を蓄電し、この蓄電した電力を電力系統へ出力する蓄電池と、前記原子炉で発生した蒸気の一部を熱源として用いて水素を製造する水素製造機と、該水素製造機で製造した水素を貯蔵する水素貯蔵器と、制御装置とを備えた原子力発電システムを制御するに当たって、前記原子炉での発生蒸気の用途を前記発電機での発電、前記水素製造機での水素製造、前記蓄電池での電気の蓄電に、どのように配分するかを需要変動に応じて、前記制御装置で制御することを特徴とする。
Furthermore, in order to achieve the above object, the method for controlling a nuclear power generation system of the present invention includes a nuclear reactor, a turbine that rotates with the steam generated in the nuclear reactor, and a turbine that rotates with the driving force accompanying the rotation of the turbine. A generator that generates electricity and outputs it to the power grid, a storage battery that stores a portion of the electricity generated by the generator and outputs the stored power to the power grid, and a heat source that uses some of the steam generated in the reactor. In controlling a nuclear power generation system equipped with a hydrogen production machine that produces hydrogen using hydrogen as a hydrogen generator, a hydrogen storage device that stores the hydrogen produced by the hydrogen production machine, and a control device, The control device controls how the usage is distributed among power generation by the generator, hydrogen production by the hydrogen production machine, and storage of electricity by the storage battery, according to demand fluctuations. do.
本発明によれば、炉心出力を一定に保持しながら長周期的、短周期的の需要変動に対応する電気出力を供給することができる。
According to the present invention, it is possible to supply electrical output corresponding to long-period and short-period demand fluctuations while keeping core output constant.
以下、図示した実施例に基づいて、本発明の原子力発電システム及びその制御方法を説明する。なお、各図において、同一構成部品には同一符号を使用する。
Hereinafter, the nuclear power generation system and its control method of the present invention will be explained based on the illustrated embodiments. In each figure, the same reference numerals are used for the same components.
また、下記はあくまでも実施の例であり、発明の内容を下記具体的態様に限定することを意図する趣旨ではない。
Furthermore, the following is merely an example of implementation, and is not intended to limit the content of the invention to the specific embodiments below.
以下で説明する各実施例は、異なる２つの周期の需要変動（長周期的、短周期的）に対応する電気出力を供給することを目的とする。なお、どれほどの周期であれば長周期であり、どれほどの周期であれば短周期であるかについては限定するものではない。例えば、周期が１時間以上のものを長周期、１時間未満のものを短周期と定義しても良い。また、周期が２時間以上のものを長周期、２時間未満のものを短周期と定義しても良い。また、周期が２４時間以上のものを長周期、２４時間未満のものを短周期と定義しても良い。
Each of the embodiments described below aims to supply electrical output that corresponds to demand fluctuations of two different cycles (long cycle and short cycle). Note that there is no limitation on how long a period is a long period and how long a period is a short period. For example, a period of one hour or more may be defined as a long period, and a period of less than one hour may be defined as a short period. Further, a period of 2 hours or more may be defined as a long period, and a period of less than 2 hours may be defined as a short period. Further, a period of 24 hours or more may be defined as a long period, and a period of less than 24 hours may be defined as a short period.
図１に、本発明の原子力発電システムの実施例１を示すシステム構成を示す。
FIG. 1 shows a system configuration showing a first embodiment of the nuclear power generation system of the present invention.
図１に示すように、本実施例の原子力発電システムは、原子炉１と、この原子炉１で発生した蒸気で回転するタービン２と、このタービン２の回転に伴う駆動力で回転して発電し、電気（Ａ）を電力系統へ出力する発電機３と、この発電機３で発電した電気の一部（電気（Ｂ））を蓄電し、この蓄電した電力（電気（Ｃ））を電力系統へ出力する蓄電池６と、原子炉１で発生した蒸気の一部（蒸気（Ｄ））を熱源として用いて水素を製造する水素製造機４と、この水素製造機４で製造した水素を貯蔵する水素貯蔵器５（水素貯蔵器５で貯蔵されている水素は、市場取引されたり、購入者へ輸送される）と、タービン２からの蒸気を冷却して水に戻す復水器７と、この復水器７の水が給水されて加熱され原子炉１へ循環する給水加熱器８とから概略構成されている。なお、復水器７には、水素製造機４からの熱が供給されている。
As shown in FIG. 1, the nuclear power generation system of this embodiment includes a nuclear reactor 1, a turbine 2 that rotates with the steam generated in the reactor 1, and a turbine 2 that rotates with the driving force accompanying the rotation of the turbine 2 and generates electricity. A generator 3 outputs electricity (A) to the power grid, and a part of the electricity (electricity (B)) generated by this generator 3 is stored, and this stored electricity (electricity (C)) is used as electricity. A storage battery 6 that outputs to the grid, a hydrogen production machine 4 that produces hydrogen using part of the steam (steam (D)) generated in the reactor 1 as a heat source, and a hydrogen production machine 4 that stores the hydrogen produced by this hydrogen production machine 4. a hydrogen storage device 5 (the hydrogen stored in the hydrogen storage device 5 is traded on the market or transported to a purchaser); a condenser 7 that cools the steam from the turbine 2 and returns it to water; It is generally composed of a feed water heater 8 in which water from the condenser 7 is supplied, heated, and circulated to the nuclear reactor 1. Note that the condenser 7 is supplied with heat from the hydrogen production machine 4.
また、発電機３で発電して蓄電池６へ蓄電される電気の一部（電気（Ｂ））は、原子力発電で使わない（電力系統へ出力しない）電力を、蓄電池６の充電に利用していることになる。
In addition, some of the electricity generated by the generator 3 and stored in the storage battery 6 (electricity (B)) is used to charge the storage battery 6, which is not used in nuclear power generation (not output to the power grid). There will be.
そして、本実施例の原子力発電システムでは、原子炉１での発生蒸気の用途を発電機３での発電、水素製造機４での水素製造、蓄電池６での電気の蓄電に、どのように配分するかを需要変動に応じて制御する制御装置９を備えていることを特徴としている。
In the nuclear power generation system of this embodiment, how is the use of the steam generated in the reactor 1 allocated to power generation in the generator 3, hydrogen production in the hydrogen production machine 4, and storage of electricity in the storage battery 6? It is characterized in that it is equipped with a control device 9 that controls whether or not the vehicle is operated in accordance with demand fluctuations.
上記した制御装置９における原子炉１での発生蒸気の用途を発電機３での発電、水素製造機４での水素製造、蓄電池６での電気の蓄電に、どのように配分するかを需要変動に応じて制御する具体例について、以下に説明する。
The above-mentioned control device 9 determines how to allocate the use of the steam generated in the reactor 1 to power generation by the generator 3, hydrogen production by the hydrogen generator 4, and storage of electricity in the storage battery 6 based on demand fluctuations. A specific example of controlling according to the following will be described below.
本実施例の制御装置９は、原子炉１の発生蒸気量を変えることなく電力の需給状態を考慮して発電量を増やす場合には、水素製造機４での水素製造量と蓄電池６での蓄電量を減らすか、又は蓄電池６からの電力系統への電気出力(電気（Ｃ）)を増やし、原子炉１の発生蒸気量を変えることなく電力の需給状態を考慮して発電量を減らす場合には、水素製造機４での水素製造量と蓄電池６での蓄電量を増やすか、又は蓄電池６からの電力系統への電気出力(電気（Ｃ）)を減らすように制御する。
The control device 9 of this embodiment controls the amount of hydrogen produced by the hydrogen generator 4 and the amount of hydrogen produced by the storage battery 6 when increasing the amount of power generation by taking into consideration the power supply and demand situation without changing the amount of steam generated by the reactor 1. When reducing the amount of power generation by reducing the amount of stored electricity or increasing the electrical output (electricity (C)) from the storage battery 6 to the power grid, taking into account the power supply and demand situation without changing the amount of steam generated by the reactor 1. In this case, control is performed to increase the amount of hydrogen produced by the hydrogen generator 4 and the amount of electricity stored in the storage battery 6, or to reduce the electrical output (electricity (C)) from the storage battery 6 to the power system.
また、本実施例の制御装置９は、原子炉１の発生蒸気量を変えることなく電力の需給状態を考慮して発電量を長周期で変化させる場合には、水素製造機４での水素製造量、又は蓄電池６での蓄電量を変化させ、原子炉１の発生蒸気量を変えることなく電力の需給状態を考慮して発電量を短周期で変化させる場合には、蓄電池６から電力系統への電気出力(電気（Ｃ）)を変化させるように制御する。
In addition, the control device 9 of this embodiment controls the hydrogen production in the hydrogen production machine 4 when changing the amount of power generation in a long period in consideration of the power supply and demand situation without changing the amount of steam generated in the reactor 1. When changing the amount of electricity stored in the storage battery 6 and changing the amount of power generation in a short period taking into consideration the supply and demand state of electricity without changing the amount of steam generated in the reactor 1, the amount of electricity stored in the storage battery 6 is changed in a short period. control to change the electrical output (electricity (C)) of the
また、本実施例の制御装置９は、原子力発電システムの長周期の需要変動に対応するために、発電機３からの蓄電池６の蓄電のための電気出力（電気（Ｂ））を変化させ、蓄電池６の蓄電量を変化させることで、発電機３から電力系統への電気出力（電気（Ａ））を変化させると共に、水素製造機４での水素製造に用いる原子炉１で発生した蒸気の一部（蒸気（Ｄ））の蒸気量を変化させ、タービン２を回転させるための原子炉１から導入される蒸気量を変化させて発電機３における発電量を変化させることで、発電機３から電力系統への電気出力（電気（Ａ））を変化させ、かつ、原子力発電システムの短周期の需要変動に対応するために、蓄電池６から電力系統への電気出力(電気（Ｃ）)を変化させるように制御し、これらを同時に実施することで、原子炉１で発生する蒸気を変えることなく、長周期、短周期の需要変動に対応することができる。
In addition, the control device 9 of this embodiment changes the electrical output (electricity (B)) for storing power in the storage battery 6 from the generator 3 in order to respond to long-cycle demand fluctuations of the nuclear power generation system. By changing the amount of electricity stored in the storage battery 6, the electrical output (electricity (A)) from the generator 3 to the power grid can be changed, and the steam generated in the nuclear reactor 1 used for hydrogen production in the hydrogen production machine 4 can be changed. By changing the amount of steam (steam (D)) and changing the amount of steam introduced from the reactor 1 to rotate the turbine 2, the amount of power generated in the generator 3 is changed. In order to change the electrical output (electricity (A)) from the storage battery 6 to the power grid and to respond to short-term demand fluctuations of the nuclear power generation system, the electrical output (electricity (C)) from the storage battery 6 to the power grid is changed. By controlling to change and performing these simultaneously, it is possible to respond to long-cycle and short-cycle demand fluctuations without changing the steam generated in the reactor 1.
また、本実施例の制御装置９は、水素貯蔵器５に貯蔵した水素の需要が高い場合には、水素製造機４での水素製造に用いる原子炉１で発生した蒸気の一部（蒸気（Ｄ））の蒸気量を増加させて水素製造機４での水素製造を増加させ、その分、発電機３からの蓄電池６の蓄電のための電気出力（電気（Ｂ））を減少させ、水素貯蔵器５に貯蔵した水素の需要が低い場合には、水素製造機４での水素製造に用いる原子炉１で発生した蒸気の一部（蒸気（Ｄ））の蒸気量を減少させて水素製造機４での水素製造を減少させ、その分、発電機３からの蓄電池６の蓄電のための電気出力（電気（Ｂ））を増加させるよう制御する。
Furthermore, when the demand for hydrogen stored in the hydrogen storage device 5 is high, the control device 9 of this embodiment controls a portion of the steam (steam) generated in the reactor 1 used for hydrogen production in the hydrogen production machine 4. D)) increases the amount of steam produced in the hydrogen production machine 4, and correspondingly decreases the electrical output (electricity (B)) from the generator 3 for storing electricity in the storage battery 6, When the demand for hydrogen stored in the storage device 5 is low, the amount of steam (steam (D)) generated in the reactor 1 used for hydrogen production in the hydrogen production machine 4 is reduced to produce hydrogen. Control is performed to reduce hydrogen production in the generator 4 and increase the electric output (electricity (B)) from the generator 3 for storing electricity in the storage battery 6 accordingly.
また、本実施例の制御装置９は、蓄電池６の蓄電量が必要な場合には、水素製造機４での水素製造に用いる原子炉１で発生した蒸気の一部（蒸気（Ｄ））の蒸気量を減少させて水素製造機４での水素製造を減少させ、その分、発電機３からの蓄電池６の蓄電のための電気出力（電気（Ｂ））を増加させ、蓄電池６の蓄電量が不要な場合には、水素製造機４での水素製造に用いる原子炉１で発生した蒸気の一部（蒸気（Ｄ））の蒸気量を増加させて水素製造機４での水素製造を増加させ、その分、発電機３からの蓄電池６の蓄電のための電気出力（電気（Ｂ））を減少させるように制御する。
In addition, when the amount of electricity stored in the storage battery 6 is required, the control device 9 of this embodiment controls a portion of the steam (steam (D)) generated in the reactor 1 used for hydrogen production in the hydrogen production machine 4. The amount of steam is reduced to reduce hydrogen production in the hydrogen generator 4, and the electric output (electricity (B)) from the generator 3 for storing electricity in the storage battery 6 is increased accordingly, thereby reducing the amount of electricity stored in the storage battery 6. If it is not necessary, increase the amount of steam of a part of the steam (steam (D)) generated in the reactor 1 used for hydrogen production in the hydrogen production machine 4 to increase hydrogen production in the hydrogen production machine 4. control is performed so that the electrical output (electricity (B)) from the generator 3 for storing electricity in the storage battery 6 is reduced accordingly.
更に、本実施例の制御装置９は、原子力発電システムの短周期の需要変動に対応するために、蓄電池６から電力系統への電気出力(電気（Ｃ）)を常に調整して、蓄電池６の蓄電量を常に確保するように制御する。
Furthermore, the control device 9 of this embodiment constantly adjusts the electrical output (electricity (C)) from the storage battery 6 to the power grid in order to respond to short-term demand fluctuations of the nuclear power generation system. Control is performed to always ensure the amount of stored electricity.
このような本実施例によれば、炉心出力を一定に保持しながら長周期的、短周期的の需要変動に対応する電気出力を供給することができる。
According to this embodiment, it is possible to supply electrical output corresponding to long-period and short-period demand fluctuations while keeping the core output constant.
また、原子炉１の熱源を利用するため、水素製造効率が向上すると共に、発電機３で発電して蓄電池６へ蓄電される電気の一部（電気（Ｂ））である原子力発電で使わない（電力系統へ出力しない）電力を、蓄電池６の充電に利用しているため、システムとしての効率向上が図れる効果がある。
In addition, since the heat source of the nuclear reactor 1 is used, hydrogen production efficiency is improved, and some of the electricity generated by the generator 3 and stored in the storage battery 6 (electricity (B)) is not used in nuclear power generation. Since electric power (which is not output to the power grid) is used to charge the storage battery 6, the efficiency of the system can be improved.
図２に、本発明の原子力発電システムの実施例２を示すシステム構成を示し、図３に、本発明の原子力発電システムの実施例２に採用される水素製造機の一例を示す。
FIG. 2 shows a system configuration showing a second embodiment of the nuclear power generation system of the present invention, and FIG. 3 shows an example of a hydrogen production machine employed in the second embodiment of the nuclear power generation system of the present invention.
図３に示すように、本実施例の原子力発電システムに採用される水素製造機４は、原子炉１で発生した蒸気の一部（蒸気（Ｄ））を熱交換して水を放出する第１の熱交換器４ａと、この第１の熱交換器４ａで熱交換された水をさらに温めるヒータ４ｂと、このヒータ４ｂからの水を水電解し水素及び酸素を生成して水素貯蔵器５へ送る電解装置４ｃと、酸素貯蔵器４ｇとから成る。熱交換器４ａでは、蒸気（Ｄ）と水（Ｈ２Ｏ）が直接混合せず、伝熱管を介して熱交換を行い、蒸気（Ｄ）によって水（Ｈ２Ｏ）の温度が上昇する。ヒータ４ｂは、外部電力または発電機３からの電力によって駆動し、水（Ｈ２Ｏ）の温度を上昇させる。熱交換器４ａとヒータ４ｂは電解装置４ｃの作動温度に応じて水（Ｈ２Ｏ）の温度を上昇させるものであり、熱交換器４ａまたはヒータ４ｂにおいて水（Ｈ２Ｏ）が沸騰して水蒸気となる場合もある。電解装置４ｃでは、水電解方式により水または水蒸気から水素と酸素を得る装置であり、例えば、固体高分子形電解や固体酸化物形電解による方式である。電解装置４ｃから得られた水素は水素貯蔵器５に貯留され、電解装置４ｃから得られた酸素は酸素貯蔵器４ｇに貯蔵される。
As shown in FIG. 3, the hydrogen production machine 4 adopted in the nuclear power generation system of this embodiment is a hydrogen generator that heat-exchanges a part of the steam (steam (D)) generated in the nuclear reactor 1 and releases water. 1 heat exchanger 4a, a heater 4b that further warms the water heat exchanged with this first heat exchanger 4a, and a hydrogen storage device 5 that electrolyzes the water from this heater 4b to generate hydrogen and oxygen. It consists of an electrolytic device 4c for supplying oxygen to the oxygen tank, and an oxygen storage device 4g. In the heat exchanger 4a, steam (D) and water (H 2 O) are not directly mixed, but are exchanged via heat exchanger tubes, and the temperature of water (H 2 O) is increased by the steam (D). The heater 4b is driven by external power or power from the generator 3, and raises the temperature of water (H 2 O). The heat exchanger 4a and the heater 4b raise the temperature of water (H 2 O) according to the operating temperature of the electrolyzer 4c, and the water (H 2 O) is boiled in the heat exchanger 4a or the heater 4b. Sometimes it becomes water vapor. The electrolyzer 4c is a device that obtains hydrogen and oxygen from water or steam using a water electrolysis method, such as a method using solid polymer type electrolysis or solid oxide type electrolysis. Hydrogen obtained from the electrolysis device 4c is stored in the hydrogen storage device 5, and oxygen obtained from the electrolysis device 4c is stored in the oxygen storage device 4g.
そして、本実施例では、第１の熱交換器４ａからの水（Ｅ）を復水器７に送ると共に、第１の熱交換器４ａから復水器７に送る水（Ｅ）の量を流量調整弁１０によって制御し、復水器７の温度を一定に保持するようにしたものである。流量調整弁１０による水（Ｅ）の量の制御のみで復水器７の温度を一定に保持できない場合、熱交換器１１を用いて復水器７の温度を制御することができる。熱交換１１では、冷却材１２、１３の流量を流量調整弁１４により調整し、熱交換器１１の出口での水（Ｅ）の温度を調整する。冷却材１２はタンク１６に貯留され、ポンプ１５によってタンク１６と熱交換器１１の間を循環する構造である。
In this embodiment, the water (E) from the first heat exchanger 4a is sent to the condenser 7, and the amount of water (E) sent from the first heat exchanger 4a to the condenser 7 is The temperature of the condenser 7 is maintained constant by controlling the flow rate regulating valve 10. When the temperature of the condenser 7 cannot be kept constant only by controlling the amount of water (E) using the flow rate regulating valve 10, the temperature of the condenser 7 can be controlled using the heat exchanger 11. In the heat exchanger 11, the flow rates of the coolants 12 and 13 are adjusted by the flow rate adjustment valve 14, and the temperature of the water (E) at the outlet of the heat exchanger 11 is adjusted. The coolant 12 is stored in a tank 16 and circulated between the tank 16 and the heat exchanger 11 by a pump 15.
このような本実施例によれば、実施例１と同様な効果が得られることは勿論、水素製造機４の第１の熱交換器４ａから水（Ｅ）を復水器７に戻し、流入する水（Ｅ）の量及び温度を制御することで、復水器７の温度を一定に保つ助けとなる。
According to this embodiment, not only can the same effects as in embodiment 1 be obtained, but also the water (E) is returned to the condenser 7 from the first heat exchanger 4a of the hydrogen generator 4, and the water (E) is returned to the condenser 7. Controlling the amount and temperature of the water (E) used helps keep the temperature of the condenser 7 constant.
復水器７では、通常、タービンで仕事をした蒸気が冷却され、凝縮水となって放出される。復水器７に流入した水（Ｅ）は、凝縮水と混合して原子炉１に戻る。流入した水（Ｅ）が一定量かつ一定温度であれば、復水器７から放出される水の温度変化を低減することができ、原子炉１に流入する水の温度を一定に保つことができる。
In the condenser 7, the steam that has done work in the turbine is usually cooled and released as condensed water. The water (E) flowing into the condenser 7 mixes with condensed water and returns to the reactor 1. If the inflow water (E) has a constant amount and temperature, it is possible to reduce the temperature change of the water discharged from the condenser 7, and it is possible to maintain the temperature of the water flowing into the reactor 1 constant. can.
これにより、原子炉１内で核燃料により沸騰する蒸気を安定的に生成することができる。従って、原子力発電システムの安定化（原子炉１の一定出力の確保）を図ることができる効果がある。
Thereby, steam boiling from the nuclear fuel can be stably generated within the nuclear reactor 1. Therefore, it is possible to stabilize the nuclear power generation system (ensuring a constant output of the nuclear reactor 1).
図４に、本発明の原子力発電システムの実施例３として、水素製造機４の他の例を示す。
FIG. 4 shows another example of the hydrogen production machine 4 as Embodiment 3 of the nuclear power generation system of the present invention.
図４に示す本実施例の水素製造機４は、図３に示した実施例２の水素製造機４を、更に改良したものである。
The hydrogen producing machine 4 of this embodiment shown in FIG. 4 is a further improvement of the hydrogen producing machine 4 of the second embodiment shown in FIG.
即ち、本実施例の水素製造機４は、第１の熱交換器４ａとヒータ４ｂとの間に第２の熱交換器４ｄを設置すると共に、電解装置４ｃと水素貯蔵器５との間に第３の熱交換器４ｅを設置し、電解装置４ｃから水素貯蔵器５へ送る水素の熱を第３の熱交換器４ｅで回収し、この第３の熱交換器４ｅで回収した熱を第２の熱交換器４ｄにおいて水または蒸気に放出するようにしたものである。
That is, in the hydrogen production machine 4 of this embodiment, a second heat exchanger 4d is installed between the first heat exchanger 4a and the heater 4b, and a second heat exchanger 4d is installed between the electrolyzer 4c and the hydrogen storage device 5. A third heat exchanger 4e is installed, and the heat of hydrogen sent from the electrolyzer 4c to the hydrogen storage device 5 is recovered by the third heat exchanger 4e, and the heat recovered by this third heat exchanger 4e is transferred to a third heat exchanger 4e. In the second heat exchanger 4d, the heat is released into water or steam.
本実施例の第３の熱交換器４ｅは、電解装置４ｃで生成される水素の放出系統から熱を回収するが、これが酸素の放出系統でも、両方でも良い。第３の熱交換器４ｅにおいて水素または酸素の放出系統から熱を回収するため、水素貯蔵器５または酸素貯蔵器４ｇに流入する気体の温度が低下する。
The third heat exchanger 4e of this embodiment recovers heat from the hydrogen release system produced by the electrolyzer 4c, but this may be the oxygen release system or both. Since heat is recovered from the hydrogen or oxygen release system in the third heat exchanger 4e, the temperature of the gas flowing into the hydrogen storage device 5 or the oxygen storage device 4g decreases.
このような本実施例によれば、実施例２と同様な効果が得られることは勿論、製造された水素は高温であるが、水素貯蔵器５に貯蔵する前に第３の熱交換器４ｅで熱を回収することにより、熱損失が減少し、ヒータ４ｂの消費電力を抑えることができるため効率が増加する効果がある。
According to this embodiment, the same effects as in embodiment 2 can be obtained, and the produced hydrogen is at a high temperature, but before being stored in the hydrogen storage device 5, the hydrogen is heated in the third heat exchanger 4e. By recovering heat, heat loss is reduced and power consumption of the heater 4b can be suppressed, which has the effect of increasing efficiency.
また、水素貯蔵器５または酸素貯蔵器４ｇに貯蔵する気体の温度を下げることができるため、気体の容積を減らすことで水素貯蔵器５または酸素貯蔵器４ｇの加圧破損を防止することができる効果がある。
Furthermore, since the temperature of the gas stored in the hydrogen storage device 5 or the oxygen storage device 4g can be lowered, it is possible to prevent pressure damage to the hydrogen storage device 5 or the oxygen storage device 4g by reducing the volume of the gas. effective.
図５に、本発明の原子力発電システムの実施例４として、水素製造機４の更に他の例を示す。
FIG. 5 shows still another example of the hydrogen production machine 4 as Embodiment 4 of the nuclear power generation system of the present invention.
図５に示す本実施例の水素製造機４は、図４に示した実施例３の水素製造機４を、更に改良したものである。
The hydrogen producing machine 4 of this embodiment shown in FIG. 5 is a further improvement of the hydrogen producing machine 4 of the third embodiment shown in FIG.
即ち、本実施例の水素製造機４は、図４に示した実施例３の水素製造機４に加え、原子炉１と第１の熱交換器４ａとの途中（原子炉１と水素製造機４との間）に第４の熱交換器４ｆを配置し、第４の熱交換器４ｆと第１の熱交換器４ａとの熱交換を冷却材４ｉを介して行い、冷却材４ｉを循環させるためのポンプ４ｈを設置し、原子炉１で発生した蒸気の一部を第４の熱交換器４ｆで熱交換して熱を放出した蒸気を第１の熱交換器４ａに送ると共に、第４の熱交換器４ｆからの水を復水器７に送るようにしたものである。
That is, in addition to the hydrogen producing machine 4 of the third embodiment shown in FIG. A fourth heat exchanger 4f is disposed between the fourth heat exchanger 4f and the first heat exchanger 4a, and heat exchange between the fourth heat exchanger 4f and the first heat exchanger 4a is performed via the coolant 4i, and the coolant 4i is circulated. A pump 4h is installed to heat a part of the steam generated in the reactor 1 through a fourth heat exchanger 4f, and the steam that releases heat is sent to the first heat exchanger 4a. Water from heat exchanger 4f of No. 4 is sent to condenser 7.
このような本実施例によれば、実施例３と同様な効果が得られることは勿論、沸騰水型原子炉の場合には、原子炉１からの蒸気は原子炉１内部の核燃料からの放射性物質を含むため、原子炉１と第１の熱交換器４ａとの途中（原子炉１と水素製造機４との間）に第４の熱交換器４ｆを追設することで、万が一、伝熱管の破損等によって第４の熱交換器４ｆ内部で蒸気と冷却材４ｉが混合することが生じても、第１の熱交換器４ａが存在するため、水素製造機４で生成される水素及び酸素に放射性物質が混入し、外部に放出されることを防ぐ効果がある。
According to this embodiment, not only can the same effects as in embodiment 3 be obtained, but also in the case of a boiling water reactor, the steam from the reactor 1 is radioactive from the nuclear fuel inside the reactor 1. Because it contains substances, by adding a fourth heat exchanger 4f between the reactor 1 and the first heat exchanger 4a (between the reactor 1 and the hydrogen production machine 4), it is possible to prevent Even if steam and coolant 4i mix inside the fourth heat exchanger 4f due to breakage of a heat tube, etc., the presence of the first heat exchanger 4a prevents the hydrogen produced by the hydrogen generator 4 and It has the effect of preventing radioactive substances from mixing with oxygen and being released to the outside.
なお、本発明は上述した実施例に限定されるものではなく、様々な変形例が含まれる。例えば、上述した実施例は本発明を分かりやすく説明するために詳細に説明したものであり、必ずしも説明したすべての構成を備えるものに限定されるものではない。また、ある実施例の構成の一部を他の実施例の構成に置き換える事が可能であり、また、ある実施例の構成に他の実施例の構成を加える事も可能である。また、各実施例の構成の一部について、他の構成の追加・削除・置換をする事が可能である。
Note that the present invention is not limited to the embodiments described above, and includes various modifications. For example, the embodiments described above are described in detail to explain the present invention in an easy-to-understand manner, and the present invention is not necessarily limited to having all the configurations described. Furthermore, it is possible to replace a part of the configuration of one embodiment with the configuration of another embodiment, and it is also possible to add the configuration of another embodiment to the configuration of one embodiment. Furthermore, it is possible to add, delete, or replace a part of the configuration of each embodiment with other configurations.
１…原子炉、２…タービン、３…発電機、４…水素製造機、４ａ…第１の熱交換器、４ｂ…ヒータ、４ｃ…電解装置、４ｄ…第２の熱交換器、４ｅ…第３の熱交換器、４ｆ…第４の熱交換器、４ｇ…酸素貯蔵器、４ｈ、１５…ポンプ、４ｉ…冷却材、５…水素貯蔵器、６…蓄電池、７…復水器、８…給水加熱器、９…制御装置、１０、１４…流量調整弁、１１…熱交換器、１２、１３…冷却材、１６…タンク。
DESCRIPTION OF SYMBOLS 1... Nuclear reactor, 2... Turbine, 3... Generator, 4... Hydrogen production machine, 4a... First heat exchanger, 4b... Heater, 4c... Electrolyzer, 4d... Second heat exchanger, 4e... First 3 heat exchanger, 4f... fourth heat exchanger, 4g... oxygen storage, 4h, 15... pump, 4i... coolant, 5... hydrogen storage, 6... storage battery, 7... condenser, 8... Feed water heater, 9...control device, 10, 14...flow rate adjustment valve, 11...heat exchanger, 12, 13...coolant, 16...tank.
Claims (16)
- 原子炉と、該原子炉で発生した蒸気で回転するタービンと、該タービンの回転に伴う駆動力で回転して発電し電力系統へ出力する発電機と、該発電機で発電した電気の一部を蓄電し、この蓄電した電力を電力系統へ出力する蓄電池と、前記原子炉で発生した蒸気の一部を熱源として用いて水素を製造する水素製造機と、該水素製造機で製造した水素を貯蔵する水素貯蔵器と、前記原子炉での発生蒸気の用途を前記発電機での発電、前記水素製造機での水素製造、前記蓄電池での電気の蓄電に、どのように配分するかを需要変動に応じて制御する制御装置と、を備えていることを特徴とする原子力発電システム。 A nuclear reactor, a turbine that rotates with the steam generated in the reactor, a generator that rotates with the driving force accompanying the rotation of the turbine to generate electricity and output it to the power grid, and a portion of the electricity generated by the generator a storage battery that stores electricity and outputs the stored electricity to the power grid; a hydrogen production machine that produces hydrogen using part of the steam generated in the reactor as a heat source; and a hydrogen production machine that produces hydrogen using the hydrogen production machine. Demand is made on how to allocate the use of the hydrogen storage device for storage and the steam generated in the nuclear reactor to power generation in the generator, hydrogen production in the hydrogen production machine, and electricity storage in the storage battery. A nuclear power generation system characterized by comprising: a control device that controls according to fluctuations.
- 請求項１に記載の原子力発電システムであって、
前記制御装置は、前記原子炉の発生蒸気量を変えることなく電力の需給状態を考慮して発電量を増やす場合には、前記水素製造機での水素製造量と前記蓄電池での蓄電量を減らすか、又は前記蓄電池からの前記電力系統への電気出力を増やし、
前記原子炉の発生蒸気量を変えることなく電力の需給状態を考慮して発電量を減らす場合には、前記水素製造機での水素製造量と前記蓄電池での蓄電量を増やすか、又は前記蓄電池からの前記電力系統への電気出力を減らすように制御することを特徴とする原子力発電システム。 The nuclear power generation system according to claim 1,
The control device reduces the amount of hydrogen produced by the hydrogen production machine and the amount of electricity stored in the storage battery when increasing the amount of power generation in consideration of the power supply and demand state without changing the amount of steam generated by the reactor. or increasing the electrical output from the storage battery to the power grid;
If the amount of power generation is to be reduced in consideration of the power supply and demand situation without changing the amount of steam generated by the reactor, the amount of hydrogen produced by the hydrogen generator and the amount of electricity stored in the storage battery are increased, or the amount of electricity stored in the storage battery is increased. A nuclear power generation system characterized in that the electric power output from the electric power system is controlled to be reduced. - 請求項１に記載の原子力発電システムであって、
前記制御装置は、前記原子炉の発生蒸気量を変えることなく電力の需給状態を考慮して発電量を長周期で変化させる場合には、前記水素製造機での水素製造量、又は前記蓄電池での蓄電量を変化させ、前記原子炉の発生蒸気量を変えることなく電力の需給状態を考慮して発電量を短周期で変化させる場合には、前記蓄電池から前記電力系統への電気出力を変化させるように制御することを特徴とする原子力発電システム。 The nuclear power generation system according to claim 1,
In the case where the amount of power generation is changed over a long period in consideration of the power supply and demand state without changing the amount of steam generated by the reactor, the control device is configured to When changing the amount of electricity stored in the reactor and changing the amount of power generation in a short period in consideration of the supply and demand state of electricity without changing the amount of steam generated by the reactor, change the electrical output from the storage battery to the power grid. A nuclear power generation system characterized by being controlled so as to - 請求項３に記載の原子力発電システムであって、
前記制御装置は、前記原子力発電システムの長周期の需要変動に対応するために、前記発電機からの前記蓄電池の蓄電のための電気出力を変化させ、前記蓄電池の蓄電量を変化させることで前記発電機から前記電力系統への電気出力を変化させると共に、前記水素製造機での水素製造に用いる前記原子炉で発生した蒸気の一部の蒸気量を変化させ、前記タービンを回転させるための前記原子炉から導入される蒸気量を変化させて前記発電機における発電量を変化させることで前記発電機から前記電力系統への電気出力を変化させ、かつ、前記原子力発電システムの短周期の需要変動に対応するために、前記蓄電池から前記電力系統への電気出力を変化させるように制御することを特徴とする原子力発電システム。 The nuclear power generation system according to claim 3,
In order to respond to long-term demand fluctuations of the nuclear power generation system, the control device changes the electrical output from the generator for storing electricity in the storage battery, and changes the amount of electricity stored in the storage battery. The method for rotating the turbine by changing the electric output from the generator to the power system and changing the amount of steam generated in the nuclear reactor used for hydrogen production in the hydrogen production machine. Changing the amount of steam introduced from the nuclear reactor to change the amount of power generated in the generator, thereby changing the electrical output from the generator to the power grid, and short-term demand fluctuations of the nuclear power generation system. A nuclear power generation system characterized in that the electric power output from the storage battery to the electric power system is controlled to be changed in order to cope with the above. - 請求項４に記載の原子力発電システムであって、
前記制御装置は、前記水素貯蔵器に貯蔵した水素の需要が高い場合には、前記水素製造機での水素製造に用いる前記原子炉で発生した蒸気の一部の蒸気量を増加させて前記水素製造機での水素製造を増加させると共に、前記発電機からの前記蓄電池の蓄電のための電気出力を減少させ、かつ、
前記水素貯蔵器に貯蔵した水素の需要が低い場合には、前記水素製造機での水素製造に用いる前記原子炉で発生した蒸気の一部の蒸気量を減少させて前記水素製造機での水素製造を減少させると共に、前記発電機からの前記蓄電池の蓄電のための電気出力を増加させるように制御することを特徴とする原子力発電システム。 The nuclear power generation system according to claim 4,
When the demand for hydrogen stored in the hydrogen storage device is high, the control device increases the amount of steam of a part of the steam generated in the nuclear reactor used for hydrogen production in the hydrogen production machine, and increasing hydrogen production in a production machine and decreasing electrical output from the generator for storing electricity in the storage battery, and
When the demand for hydrogen stored in the hydrogen storage device is low, the amount of steam generated in a part of the steam generated in the nuclear reactor used for hydrogen production in the hydrogen production machine is reduced, and the hydrogen production in the hydrogen production machine is reduced. A nuclear power generation system characterized in that control is performed to reduce production and increase electrical output from the generator for storing electricity in the storage battery. - 請求項４又は５に記載の原子力発電システムであって、
前記制御装置は、前記蓄電池の蓄電量が必要な場合には、前記水素製造機での水素製造に用いる前記原子炉で発生した蒸気の一部の蒸気量を減少させて前記水素製造機での水素製造を減少させると共に、前記発電機からの前記蓄電池の蓄電のための電気出力を増加させ、かつ、
前記蓄電池の蓄電量が不要な場合には、前記水素製造機での水素製造に用いる前記原子炉で発生した蒸気の一部の蒸気量を増加させて前記水素製造機での水素製造を増加させると共に、前記発電機からの前記蓄電池の蓄電のための電気出力を減少させるように制御することを特徴とする原子力発電システム。 The nuclear power generation system according to claim 4 or 5,
When the amount of electricity stored in the storage battery is required, the control device reduces the amount of steam of a part of the steam generated in the nuclear reactor used for hydrogen production in the hydrogen production machine, and increases the amount of electricity stored in the hydrogen production machine. reducing hydrogen production and increasing electrical output from the generator for storage of the battery; and
When the amount of electricity stored in the storage battery is not required, increasing the amount of some of the steam generated in the nuclear reactor used for hydrogen production in the hydrogen production machine to increase hydrogen production in the hydrogen production machine. A nuclear power generation system characterized in that the electric power output from the generator for storing electricity in the storage battery is controlled to be reduced. - 請求項４乃至６のいずれか１項に記載の原子力発電システムであって、
前記制御装置は、前記原子力発電システムの短周期の需要変動に対応するために、前記蓄電池から前記電力系統への電気出力を常に調整して、前記蓄電池の蓄電量を常に確保するように制御することを特徴とする原子力発電システム。 The nuclear power generation system according to any one of claims 4 to 6,
In order to respond to short-term demand fluctuations of the nuclear power generation system, the control device constantly adjusts the electrical output from the storage battery to the power grid, and performs control so as to always ensure the amount of electricity stored in the storage battery. A nuclear power generation system characterized by: - 請求項１乃至７のいずれか１項に記載の原子力発電システムであって、
前記原子力発電システムは、前記タービンからの蒸気を冷却して水に戻し、この水を給水加熱器へ給水する復水器を備えており、一方、前記水素製造機は、前記原子炉で発生した蒸気の一部を熱交換して水を放出する第１の熱交換器と、該第１の熱交換器で熱交換された水をさらに温めるヒータと、該ヒータからの水を水電解し水素及び酸素を生成して前記水素貯蔵器へ送る電解装置と、酸素貯蔵器４ｇとから成り、
前記第１の熱交換器からの前記水を前記復水器に送ると共に、前記第１の熱交換器から前記復水器に送る前記水の量を制御し、前記復水器の温度を一定に保持することを特徴とする原子力発電システム。 The nuclear power generation system according to any one of claims 1 to 7,
The nuclear power generation system includes a condenser that cools the steam from the turbine and returns it to water, and supplies this water to the feed water heater, while the hydrogen production machine is configured to cool steam generated in the nuclear reactor. A first heat exchanger that heat exchanges part of the steam and releases water; a heater that further warms the water heat exchanged with the first heat exchanger; and a heater that electrolyzes the water from the heater to produce hydrogen. and an electrolytic device that generates oxygen and sends it to the hydrogen storage device, and an oxygen storage device 4g,
The water from the first heat exchanger is sent to the condenser, and the amount of water sent from the first heat exchanger to the condenser is controlled to keep the temperature of the condenser constant. A nuclear power generation system characterized by being maintained at - 請求項８に記載の原子力発電システムであって、
前記第１の熱交換器と前記ヒータとの間に第２の熱交換器を設置すると共に、前記電解装置と前記水素貯蔵器との間に第３の熱交換器を設置し、前記電解装置から前記水素貯蔵器へ送る前記水素の熱を前記第３の熱交換器で回収し、前記第３の熱交換器で回収した前記熱を前記第２の熱交換器へ放出することを特徴とする原子力発電システム。 The nuclear power generation system according to claim 8,
A second heat exchanger is installed between the first heat exchanger and the heater, and a third heat exchanger is installed between the electrolyzer and the hydrogen storage device, and the electrolyzer The third heat exchanger recovers the heat of the hydrogen sent from the hydrogen to the hydrogen storage device, and the heat recovered by the third heat exchanger is released to the second heat exchanger. nuclear power generation system. - 請求項９に記載の原子力発電システムであって、
前記原子炉と前記第１の熱交換器との途中に第４の熱交換器を配置し、前記原子炉で発生した蒸気の一部を前記第４の熱交換器で熱交換して熱を放出した蒸気を前記第１の熱交換器に送ると共に、前記第４の熱交換器からの水を前記復水器に送ることを特徴とする原子力発電システム。 The nuclear power generation system according to claim 9,
A fourth heat exchanger is disposed between the nuclear reactor and the first heat exchanger, and a part of the steam generated in the nuclear reactor is heat exchanged with the fourth heat exchanger to generate heat. A nuclear power generation system characterized in that released steam is sent to the first heat exchanger, and water from the fourth heat exchanger is sent to the condenser. - 原子炉と、該原子炉で発生した蒸気で回転するタービンと、該タービンの回転に伴う駆動力で回転して発電し電力系統へ出力する発電機と、該発電機で発電した電気の一部を蓄電し、この蓄電した電力を電力系統へ出力する蓄電池と、前記原子炉で発生した蒸気の一部を熱源として用いて水素を製造する水素製造機と、該水素製造機で製造した水素を貯蔵する水素貯蔵器と、制御装置とを備えた原子力発電システムを制御するに当たって、
前記原子炉での発生蒸気の用途を前記発電機での発電、前記水素製造機での水素製造、前記蓄電池での電気の蓄電に、どのように配分するかを需要変動に応じて、前記制御装置で制御することを特徴とする原子力発電システムの制御方法。 A nuclear reactor, a turbine that rotates with the steam generated in the reactor, a generator that rotates with the driving force accompanying the rotation of the turbine to generate electricity and output it to the power grid, and a portion of the electricity generated by the generator a storage battery that stores electricity and outputs the stored electricity to the power grid; a hydrogen production machine that produces hydrogen using part of the steam generated in the reactor as a heat source; and a hydrogen production machine that produces hydrogen using the hydrogen production machine. In controlling a nuclear power generation system equipped with a hydrogen storage device and a control device,
The control method determines how to allocate the use of steam generated in the nuclear reactor to power generation in the generator, hydrogen production in the hydrogen production machine, and storage of electricity in the storage battery according to demand fluctuations. A method for controlling a nuclear power generation system, characterized in that it is controlled by a device. - 請求項１１に記載の原子力発電システムの制御方法であって、
前記原子炉の発生蒸気量を変えることなく電力の需給状態を考慮して発電量を増やす場合には、前記水素製造機での水素製造量と前記蓄電池での蓄電量を減らすか、又は前記蓄電池からの前記電力系統への電気出力を増やし、
前記原子炉の発生蒸気量を変えることなく電力の需給状態を考慮して発電量を減らす場合には、前記水素製造機での水素製造量と前記蓄電池での蓄電量を増やすか、又は前記蓄電池からの前記電力系統への電気出力を減らすように前記制御装置で制御することを特徴とする原子力発電システムの制御方法。 A method for controlling a nuclear power generation system according to claim 11,
In order to increase the amount of power generated by taking into consideration the power supply and demand situation without changing the amount of steam generated by the reactor, the amount of hydrogen produced by the hydrogen generator and the amount of electricity stored in the storage battery should be reduced, or the amount of electricity stored in the storage battery should be reduced. increasing the electrical output to said power system from
If the amount of power generation is to be reduced in consideration of the power supply and demand situation without changing the amount of steam generated by the reactor, the amount of hydrogen produced by the hydrogen generator and the amount of electricity stored in the storage battery should be increased, or the amount of electricity stored in the storage battery should be increased. A method for controlling a nuclear power generation system, characterized in that the control device performs control so as to reduce the electrical output from the nuclear power generation system to the power system. - 請求項１１に記載の原子力発電システムの制御方法であって、
前記原子炉の発生蒸気量を変えることなく電力の需給状態を考慮して発電量を長周期で変化させる場合には、前記水素製造機での水素製造量、又は前記蓄電池での蓄電量を変化させ、前記原子炉の発生蒸気量を変えることなく電力の需給状態を考慮して発電量を短周期で変化させる場合には、前記蓄電池から前記電力系統への電気出力を変化させるように前記制御装置で制御することを特徴とする原子力発電システムの制御方法。 A method for controlling a nuclear power generation system according to claim 11,
When changing the power generation amount over a long period of time without changing the amount of steam generated by the reactor, taking into account the power supply and demand situation, the amount of hydrogen produced by the hydrogen production machine or the amount of electricity stored in the storage battery may be changed. and when changing the amount of power generation in a short period in consideration of the power supply and demand state without changing the amount of steam generated by the reactor, the control is performed so as to change the electrical output from the storage battery to the power grid. A method for controlling a nuclear power generation system, characterized in that it is controlled by a device. - 請求項１３に記載の原子力発電システムの制御方法であって、
前記原子力発電システムの長周期の需要変動に対応するために、前記発電機からの前記蓄電池の蓄電のための電気出力を変化させ、前記蓄電池の蓄電量を変化させることで前記発電機から前記電力系統への電気出力を変化させると共に、前記水素製造機での水素製造に用いる前記原子炉で発生した蒸気の一部の蒸気量を変化させ、前記タービンを回転させるための前記原子炉から導入される蒸気量を変化させて前記発電機における発電量を変化させることで前記発電機から前記電力系統への電気出力を変化させ、かつ、前記原子力発電システムの短周期の需要変動に対応するために、前記蓄電池から前記電力系統への電気出力を変化させるように前記制御装置で制御することを特徴とする原子力発電システムの制御方法。 A method for controlling a nuclear power generation system according to claim 13,
In order to respond to long-term demand fluctuations in the nuclear power generation system, the electrical output from the generator for storing electricity in the storage battery is changed, and the amount of electricity stored in the storage battery is changed, thereby reducing the electricity from the generator. In addition to changing the electric output to the grid, the amount of steam generated in a part of the steam generated in the nuclear reactor used for hydrogen production in the hydrogen production machine is changed, and the steam introduced from the nuclear reactor is used to rotate the turbine. In order to change the electric output from the generator to the power grid by changing the amount of steam generated in the generator to change the amount of power generated in the generator, and to respond to short-term demand fluctuations of the nuclear power generation system. . A method of controlling a nuclear power generation system, characterized in that the control device performs control to change the electrical output from the storage battery to the power system. - 請求項１４に記載の原子力発電システムの制御方法であって、
前記水素貯蔵器に貯蔵した水素の需要が高い場合には、前記水素製造機での水素製造に用いる前記原子炉で発生した蒸気の一部の蒸気量を増加させて前記水素製造機での水素製造を増加させると共に前記発電機からの前記蓄電池の蓄電のための電気出力を減少させ、かつ、
前記水素貯蔵器に貯蔵した水素の需要が低い場合には、前記水素製造機での水素製造に用いる前記原子炉で発生した蒸気の一部の蒸気量を減少させて前記水素製造機での水素製造を減少させると共に、前記発電機からの前記蓄電池の蓄電のための電気出力を増加させるように前記制御装置で制御することを特徴とする原子力発電システムの制御方法。 15. The method for controlling a nuclear power generation system according to claim 14,
When the demand for hydrogen stored in the hydrogen storage device is high, the amount of steam generated in a part of the steam generated in the nuclear reactor used for hydrogen production in the hydrogen production machine is increased, and the hydrogen production in the hydrogen production machine is increased. increasing production and decreasing electrical output from the generator for storage of the battery; and
When the demand for hydrogen stored in the hydrogen storage device is low, the amount of steam generated in a part of the steam generated in the nuclear reactor used for hydrogen production in the hydrogen production machine is reduced, and the hydrogen production in the hydrogen production machine is reduced. A method for controlling a nuclear power generation system, comprising controlling the control device to reduce production and increase electrical output from the generator for storing electricity in the storage battery. - 請求項１４又は１５に記載の原子力発電システムの制御方法であって、
前記蓄電池の蓄電量が必要な場合には、前記水素製造機での水素製造に用いる前記原子炉で発生した蒸気の一部の蒸気量を減少させて前記水素製造機での水素製造を減少させると共に、前記発電機からの前記蓄電池の蓄電のための電気出力を増加させ、かつ、
前記蓄電池の蓄電量が不要な場合には、前記水素製造機での水素製造に用いる前記原子炉で発生した蒸気の一部の蒸気量を増加させて前記水素製造機での水素製造を増加させると共に、前記発電機からの前記蓄電池の蓄電のための電気出力を減少させるように前記制御装置で制御することを特徴とする原子力発電システムの制御方法。 A method for controlling a nuclear power generation system according to claim 14 or 15,
When the amount of electricity stored in the storage battery is required, the amount of steam generated in part of the steam generated in the nuclear reactor used for hydrogen production in the hydrogen production machine is reduced to reduce hydrogen production in the hydrogen production machine. At the same time, increasing the electrical output from the generator for storing electricity in the storage battery, and
When the amount of electricity stored in the storage battery is not required, increasing the amount of some of the steam generated in the nuclear reactor used for hydrogen production in the hydrogen production machine to increase hydrogen production in the hydrogen production machine. A method for controlling a nuclear power generation system, characterized in that the control device performs control to reduce an electrical output from the generator for storing electricity in the storage battery.
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