JP2007248268A - Nuclear power plant, its remodeling method, and operation method - Google Patents

Nuclear power plant, its remodeling method, and operation method Download PDF

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JP2007248268A
JP2007248268A JP2006072248A JP2006072248A JP2007248268A JP 2007248268 A JP2007248268 A JP 2007248268A JP 2006072248 A JP2006072248 A JP 2006072248A JP 2006072248 A JP2006072248 A JP 2006072248A JP 2007248268 A JP2007248268 A JP 2007248268A
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Satoshi Mimura
聡 三村
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Toshiba Corp
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    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
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Abstract

<P>PROBLEM TO BE SOLVED: To reduce expense for remodeling or replacement of a turbine in a nuclear power plant having possibility of increasing a rated heat output in future. <P>SOLUTION: In this nuclear power plant having a nuclear steam supply system for generating steam by fission, and the turbine for recovering energy of steam supplied from the nuclear steam supply system, when steam generated with a higher heat output than the rated heat output by the nuclear steam supply system such as the first turbine efficiency curve 1 is supplied, operation is performed at the rated heat output by using the turbine wherein an energy recovery efficiency is heightened furthermore than the operation time at the rated heat output (point C in figure 1). Thereafter, when the rated heat output of the nuclear steam supply system is increased by 7%, an electric output can be increased by operating at the increased rated heat output after remodeling (point A in figure 1) without remodeling of the turbine or the like. <P>COPYRIGHT: (C)2007,JPO&INPIT

Description

本発明は、原子力発電プラントとその改造方法および運転方法に関する。   The present invention relates to a nuclear power plant and a method for remodeling and operating the same.

従来、既設の原子力プラントにおいて定格熱出力を変えずに高圧タービンまたは低圧タービンの改造または取替えを行う場合には、定格熱出力においてタービン効率が最高となるよう設計した高圧タービンまたは低圧タービンに改造または取替えて運転していた。   Conventionally, when remodeling or replacing a high-pressure turbine or low-pressure turbine without changing the rated heat output in an existing nuclear power plant, remodeling or replacing the high-pressure turbine or low-pressure turbine designed to maximize the turbine efficiency at the rated heat output I was driving by replacing.

また、特許文献１には、原子炉の熱出力を増加させた場合に、高圧タービンと低圧タービンの間に機器を追加して、原子炉の電気出力を増加させる方法が開示されている。
特開２００５−２９９６４４号公報 Patent Document 1 discloses a method of increasing the electrical output of a nuclear reactor by adding equipment between the high-pressure turbine and the low-pressure turbine when the thermal output of the nuclear reactor is increased.
JP 2005-299644 A

上述のように、定格熱出力を増加させ電気出力の増加をする場合には、高圧タービンは設計余裕が小さいため、機器寿命前であっても、主蒸気流量の増大に応じた改造または取替えが必要である。また、高圧タービンの改造などを行わない場合であっても、機器の追加などが必要となる。また、定格熱出力の増加幅が大きい場合は、比較的設計余裕の大きい低圧タービンについても高圧タービンと同様に改造または取替が必要となる。このため、プラントライフサイクルにおける設備改造量が増大するという問題がある。   As described above, when the rated heat output is increased and the electrical output is increased, the high pressure turbine has a small design margin, and therefore, even before the life of the equipment, modification or replacement according to the increase in the main steam flow rate is required. is necessary. Even if the high-pressure turbine is not modified, it is necessary to add equipment. When the increase in the rated heat output is large, the low pressure turbine having a relatively large design margin needs to be modified or replaced in the same manner as the high pressure turbine. For this reason, there exists a problem that the amount of equipment remodeling in a plant life cycle increases.

そこで、本発明は、将来、定格熱出力を増加させる可能性がある原子力発電プラントにおいて、タービンの改造または取替えの費用を低減することを目的とする。   Therefore, the present invention aims to reduce the cost of modification or replacement of a turbine in a nuclear power plant that may increase the rated heat output in the future.

上述の目的を達成するため、本発明は、原子力発電プラントにおいて、核分裂によって蒸気を発生させる原子力蒸気供給システムと、前記原子力蒸気供給システムから供給される蒸気のエネルギーを回収する前記原子力蒸気供給システムが、定格熱出力よりも高い熱出力で発生させた蒸気が供給されたときに前記定格熱出力運転時よりもエネルギーの回収効率が高くなるタービンと、を有することを特徴とする。   In order to achieve the above object, the present invention provides a nuclear steam supply system that generates steam by nuclear fission in a nuclear power plant, and the nuclear steam supply system that recovers energy of steam supplied from the nuclear steam supply system. And a turbine whose energy recovery efficiency is higher than that during the rated heat output operation when steam generated at a heat output higher than the rated heat output is supplied.

また、本発明は、核分裂によって蒸気を発生させる既設の原子力蒸気供給システムと、前記原子力蒸気供給システムから供給される蒸気のエネルギーを回収する既設のタービンを備えた原子力発電プラントの改造方法において、前記既設のタービンを、前記原子力蒸気供給システムが既設の（改造前の）定格熱出力よりも高い熱出力で発生させた蒸気が供給されたときに前記改造前の定格熱出力運転時よりもエネルギーの回収効率が高くなるようにするタービン改造工程、を有することを特徴とする。   Further, the present invention provides an existing nuclear steam supply system that generates steam by nuclear fission, and a method for remodeling a nuclear power plant including an existing turbine that recovers steam energy supplied from the nuclear steam supply system, When the steam generated by the nuclear steam supply system at a heat output higher than the rated heat output of the existing steam supply system (before modification) is supplied, the energy of the existing turbine is higher than that at the rated heat output operation before the modification. A turbine remodeling step for increasing the recovery efficiency.

また、本発明は、核分裂によって蒸気を発生させる原子力蒸気供給システムと、前記原子力蒸気供給システムから供給される蒸気のエネルギーを回収する、前記原子力蒸気供給システムが定格熱出力よりも高い熱出力で発生させた蒸気が供給されたときに前記定格熱出力運転時よりもエネルギーの回収効率が高くなるタービンを備えた原子力発電プラントの運転方法において、前記原子力蒸気供給システムに定格熱出力で蒸気を発生させる定格出力運転工程、を有することを特徴とする。   Further, the present invention provides a nuclear steam supply system that generates steam by fission, and recovers energy of steam supplied from the nuclear steam supply system. The nuclear steam supply system is generated at a heat output higher than a rated heat output. In a method for operating a nuclear power plant having a turbine that has higher energy recovery efficiency than when operating at the rated heat output when supplied steam is generated, the nuclear steam supply system generates steam at the rated heat output A rated output operation step.

本発明によれば、将来、定格熱出力を増加させる可能性がある原子力発電プラントにおいて、タービンの改造または取替えの費用を低減することができる。   According to the present invention, it is possible to reduce the cost of turbine modification or replacement in a nuclear power plant that may increase the rated heat output in the future.

本発明に係る原子力発電プラントの実施の形態を、図面を参照して説明する。また、沸騰水型原子炉を例に説明するが、他の形式の原子力発電プラントにも適用可能である。   An embodiment of a nuclear power plant according to the present invention will be described with reference to the drawings. Although a boiling water reactor will be described as an example, the present invention can be applied to other types of nuclear power plants.

［第１の実施の形態］
図２は、本発明に係る一実施の形態の原子力発電プラントの系統図である。 [First Embodiment]
FIG. 2 is a system diagram of a nuclear power plant according to an embodiment of the present invention.

原子力発電プラントは、炉心４を収めた原子炉容器３、高圧，低圧タービン５，６、復水器７および発電機９を有している。原子炉容器３と高圧タービン５の間は主蒸気配管８で、復水器７と原子炉容器３の間は給水配管１０で接続されている。   The nuclear power plant has a reactor vessel 3 containing a core 4, high-pressure and low-pressure turbines 5 and 6, a condenser 7 and a generator 9. A main steam pipe 8 is connected between the reactor vessel 3 and the high-pressure turbine 5, and a water supply pipe 10 is connected between the condenser 7 and the reactor vessel 3.

炉心４において、核分裂によって発生した熱によって、炉心４を流れる冷却材は加熱され、原子炉容器３の内部で蒸気が発生する。炉心４で発生した熱で冷却材を加熱し高温高圧の蒸気に変えて、高圧，低圧タービン５，６に供給するシステムは、原子力蒸気供給システムと呼ばれる。   In the core 4, the coolant flowing through the core 4 is heated by heat generated by fission, and steam is generated inside the reactor vessel 3. A system in which the coolant is heated by the heat generated in the core 4 to be converted into high-temperature and high-pressure steam and supplied to the high-pressure and low-pressure turbines 5 and 6 is called a nuclear steam supply system.

発生した蒸気は高圧タービン５および低圧タービン６に送られ、高圧タービン５および低圧タービン６でエネルギーを回収して、発電機９での発電に供される。   The generated steam is sent to the high-pressure turbine 5 and the low-pressure turbine 6, and energy is recovered by the high-pressure turbine 5 and the low-pressure turbine 6 to be used for power generation by the generator 9.

低圧タービン６でエネルギーを回収された蒸気は、復水器７で凝縮された後、再び原子炉容器３に戻る。   The steam whose energy has been recovered by the low-pressure turbine 6 is condensed by the condenser 7 and then returns to the reactor vessel 3 again.

このような既設の原子力発電プラントにおいて、高圧タービン５を改造する。   In such an existing nuclear power plant, the high-pressure turbine 5 is modified.

図１は、本実施の形態におけるタービン効率曲線を示すグラフである。   FIG. 1 is a graph showing a turbine efficiency curve in the present embodiment.

図１において、第１の効率曲線１は、改造後の高圧タービン５の蒸気流量に対するタービン効率を示している。また、第２の効率曲線２は、改造前の高圧タービン５の蒸気流量に対するタービン効率を示している。   In FIG. 1, a first efficiency curve 1 indicates the turbine efficiency with respect to the steam flow rate of the high-pressure turbine 5 after modification. Further, the second efficiency curve 2 shows the turbine efficiency with respect to the steam flow rate of the high-pressure turbine 5 before the modification.

図１においてＡ点として示される改造後の高圧タービン５の効率が既設の（改造前の）定格熱出力運転時よりも高く、たとえば最高になる最高効率点は、図１においてＢ点として示される改造前の高圧タービン５の最高効率点よりも主蒸気流量が大きい。改造前の定格熱出力における主蒸気流量（定格主蒸気流量）を主蒸気流量の１００％とした場合、Ｂ点の主蒸気流量は１００％であり、Ａ点の主蒸気流量はたとえば１０７％である。   The efficiency of the high-pressure turbine 5 after remodeling shown as point A in FIG. 1 is higher than that of the existing (before remodeling) rated heat output operation, for example, the highest efficiency point that becomes the highest is shown as point B in FIG. The main steam flow rate is larger than the highest efficiency point of the high-pressure turbine 5 before remodeling. When the main steam flow rate (rated main steam flow rate) at the rated heat output before modification is 100% of the main steam flow rate, the main steam flow rate at point B is 100%, and the main steam flow rate at point A is 107%, for example. is there.

原子力プラントの蒸気タービンのタービン効率は、最高効率となる主蒸気流量を超えると急激に低下するため、最高効率点を越えた主蒸気流量では一般に使用できない。このため、タービン効率が第１のタービン効率曲線１で示される高圧タービン５は、定格主蒸気流量の１０７％まで使用できるが、タービン効率が第２のタービン効率曲線２で示される高圧タービン５は、定格主蒸気流量の１００％までしか使用できない。   The turbine efficiency of a steam turbine in a nuclear power plant decreases rapidly when it exceeds the main steam flow rate at which the maximum efficiency is reached, so that it cannot generally be used at a main steam flow rate exceeding the maximum efficiency point. Therefore, the high-pressure turbine 5 whose turbine efficiency is indicated by the first turbine efficiency curve 1 can be used up to 107% of the rated main steam flow rate, but the high-pressure turbine 5 whose turbine efficiency is indicated by the second turbine efficiency curve 2 is Only 100% of the rated main steam flow rate can be used.

そこで、タービン効率が第１のタービン効率曲線１で示される高圧タービン５に改造する。改造した原子力発電プラントで、原子力蒸気供給システムの定格熱出力を増加させずに運転（図１のＣ点）する。   Therefore, the turbine efficiency is modified to the high-pressure turbine 5 indicated by the first turbine efficiency curve 1. The modified nuclear power plant is operated without increasing the rated heat output of the nuclear steam supply system (point C in FIG. 1).

このような原子力発電プラントでは、将来、主蒸気流量が定格主蒸気流量の１０７％以下までしか増加しない範囲で熱出力を増加する場合には、高圧タービン５をそのまま使用して、発電機９の電気出力を増加させることができる。   In such a nuclear power plant, when the heat output is increased in the range where the main steam flow rate only increases to 107% or less of the rated main steam flow rate in the future, the high-pressure turbine 5 is used as it is, and the generator 9 The electrical output can be increased.

したがって、一旦、タービン効率曲線２の高圧タービン５に改造して、定格熱出力を増加させずに運転（図１のＢ点）した後、再び高圧タービン５を改造する場合に比べ、プラントライフサイクルにおける設備改造量を減らすことができる。このため、プラントライフサイクルにおけるコストを低減することができる。   Therefore, the plant life cycle is compared with the case where the high pressure turbine 5 having the turbine efficiency curve 2 is once modified and operated without increasing the rated heat output (point B in FIG. 1), and then the high pressure turbine 5 is modified again. The amount of equipment remodeling can be reduced. For this reason, the cost in a plant life cycle can be reduced.

また、以上の実施の形態においては高圧タービンを例として示したが、低圧タービンについても同様の形で交換し、電気出力を増加させてもよいのはもちろんである。   In the above embodiment, the high-pressure turbine is shown as an example. However, the low-pressure turbine may be replaced in the same manner to increase the electric output.

なお、ここでは、タービンを改造する場合について説明したが、タービンを取り替える場合であっても同様である。また、新規の原子力発電プラントを建設する際に、将来、原子力蒸気供給システムの定格熱出力を増加させる可能性がある場合などにも適用できる。   Here, the case where the turbine is modified has been described, but the same applies to the case where the turbine is replaced. Moreover, when constructing a new nuclear power plant, it can be applied to the case where there is a possibility of increasing the rated heat output of the nuclear steam supply system in the future.

以上の説明は単なる例示であり、本発明は上述の実施形態に限定されず、様々な形態で実施することができる。   The above description is merely an example, and the present invention is not limited to the above-described embodiment, and can be implemented in various forms.

たとえば、炉心で発生した熱で冷却材を加熱し、蒸気発生器を介して高温高圧の蒸気に変えてタービンに供給する原子力蒸気供給システムを有する、加圧水型原子力発電プラントや高速増殖炉を用いた発電プラントなどにも適用可能である。この場合には、炉心の熱出力の増大に伴って蒸気発生器の改造も必要となる可能性はあるが、タービンは改造などを施すことなく利用可能であり、プラントライフサイクルにおけるコストを低減することができる。   For example, a pressurized water nuclear power plant or fast breeder reactor that has a nuclear steam supply system that heats the coolant with the heat generated in the core and converts it into high-temperature and high-pressure steam via a steam generator and supplies it to the turbine was used. It can also be applied to power plants. In this case, it may be necessary to modify the steam generator as the thermal output of the core increases, but the turbine can be used without modification, reducing the cost in the plant life cycle. be able to.

本発明に係る一実施の形態におけるタービン効率曲線を示すグラフである。It is a graph which shows the turbine efficiency curve in one embodiment concerning the present invention. 本発明に係る一実施の形態における原子力発電プラントの系統図である。It is a systematic diagram of the nuclear power plant in one embodiment concerning the present invention.

符号の説明Explanation of symbols

３…原子炉容器、４…炉心、５…高圧タービン、６…低圧タービン、７…復水器、８…主蒸気配管、９…発電機、１０…給水配管。 DESCRIPTION OF SYMBOLS 3 ... Reactor vessel, 4 ... Core, 5 ... High pressure turbine, 6 ... Low pressure turbine, 7 ... Condenser, 8 ... Main steam piping, 9 ... Generator, 10 ... Feed water piping.

Claims (6)

核分裂によって蒸気を発生させる原子力蒸気供給システムと、
前記原子力蒸気供給システムから供給される蒸気のエネルギーを回収する前記原子力蒸気供給システムが、定格熱出力よりも高い熱出力で発生させた蒸気が供給されたときに前記定格熱出力運転時よりもエネルギーの回収効率が高くなるタービンと、
を有することを特徴とする原子力発電プラント。 A nuclear steam supply system that generates steam by fission,
When the steam generated from the nuclear steam supply system that recovers the energy of the steam supplied from the nuclear steam supply system is supplied with steam generated at a heat output higher than the rated heat output, the energy is higher than that during the rated heat output operation. Turbines with higher recovery efficiency,
A nuclear power plant characterized by comprising: 核分裂によって蒸気を発生させる既設の原子力蒸気供給システムと、前記原子力蒸気供給システムから供給される蒸気のエネルギーを回収する既設のタービンを備えた原子力発電プラントの改造方法において、
前記既設のタービンを、前記原子力蒸気供給システムが改造前の定格熱出力よりも高い熱出力で発生させた蒸気が供給されたときに前記改造前の定格熱出力運転時よりもエネルギーの回収効率が高くなるようにするタービン改造工程、
を有することを特徴とする原子力発電プラントの改造方法。 In an existing nuclear steam supply system that generates steam by nuclear fission, and a nuclear power plant remodeling method that includes an existing turbine that recovers steam energy supplied from the nuclear steam supply system,
When the steam generated by the nuclear steam supply system at a heat output higher than the rated heat output before the remodeling is supplied to the existing turbine, the energy recovery efficiency is higher than that at the rated heat output operation before the remodeling. Turbine modification process to make it higher,
A method for remodeling a nuclear power plant characterized by comprising: 前記タービン改造工程は、前記既設のタービンを新たなタービンと取替えるものであることを特徴とする請求項２記載の原子力発電プラントの改造方法。   The method for remodeling a nuclear power plant according to claim 2, wherein the turbine remodeling step replaces the existing turbine with a new turbine. 前記タービン改造工程の後に、前記原子力蒸気供給システムの定格熱出力を高める改造工程を有することを特徴とする請求項２または請求項３記載の原子力発電プラントの改造方法。   The method for remodeling a nuclear power plant according to claim 2 or 3, further comprising a remodeling step for increasing a rated heat output of the nuclear steam supply system after the turbine remodeling step. 核分裂によって蒸気を発生させる原子力蒸気供給システムと、前記原子力蒸気供給システムから供給される蒸気のエネルギーを回収する、前記原子力蒸気供給システムが定格熱出力よりも高い熱出力で発生させた蒸気が供給されたときに前記定格熱出力運転時よりもエネルギーの回収効率が高くなるタービンを備えた原子力発電プラントの運転方法において、
前記原子力蒸気供給システムに定格熱出力で蒸気を発生させる定格出力運転工程、
を有することを特徴とする原子力発電プラントの運転方法。 A nuclear steam supply system that generates steam by nuclear fission, and steam generated by the nuclear steam supply system that recovers energy of steam supplied from the nuclear steam supply system and that has a heat output higher than a rated heat output is supplied. In a method of operating a nuclear power plant equipped with a turbine having a higher energy recovery efficiency than during the rated heat output operation,
A rated output operation process for generating steam at a rated heat output in the nuclear steam supply system,
A method for operating a nuclear power plant, comprising: 前記定格出力運転工程の後に、前記原子力蒸気供給システムの定格熱出力を高める改造工程と、
前記改造工程の後に、前記原子力蒸気供給システムに前記タービンのエネルギーの回収効率が最も高くなる熱出力で蒸気を発生させる増出力運転工程と、
を有することを特徴とする請求項５記載の原子力発電プラントの運転方法。 After the rated power operation process, a modification process for increasing the rated heat output of the nuclear steam supply system,
After the remodeling step, the nuclear power steam supply system generates steam at a heat output at which the energy recovery efficiency of the turbine is highest,
The method of operating a nuclear power plant according to claim 5, wherein:
JP2006072248A 2006-03-16 2006-03-16 Nuclear power plant, its remodeling method, and operation method Withdrawn JP2007248268A (en)

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Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009150763A (en) * 2007-12-20 2009-07-09 Hitachi-Ge Nuclear Energy Ltd Nuclear power plant and method of operating the same
JP2009162666A (en) * 2008-01-08 2009-07-23 Hitachi High-Technologies Corp Sample processing method and apparatus using focused ion beam

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2009150763A (en) * 2007-12-20 2009-07-09 Hitachi-Ge Nuclear Energy Ltd Nuclear power plant and method of operating the same
JP2009162666A (en) * 2008-01-08 2009-07-23 Hitachi High-Technologies Corp Sample processing method and apparatus using focused ion beam

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