EP2551475A2 - Retrofitting of a nuclear power plant - Google Patents

Retrofitting of a nuclear power plant Download PDF

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Publication number
EP2551475A2
EP2551475A2 EP20120005081 EP12005081A EP2551475A2 EP 2551475 A2 EP2551475 A2 EP 2551475A2 EP 20120005081 EP20120005081 EP 20120005081 EP 12005081 A EP12005081 A EP 12005081A EP 2551475 A2 EP2551475 A2 EP 2551475A2
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EP
European Patent Office
Prior art keywords
steam
pressure
medium
turbine
steam generator
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Withdrawn
Application number
EP20120005081
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German (de)
English (en)
Inventor
Karl-Friedrich Dr. Schröder
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Babcock Borsig Steinmueller GmbH
Original Assignee
Babcock Borsig Steinmueller GmbH
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Babcock Borsig Steinmueller GmbH filed Critical Babcock Borsig Steinmueller GmbH
Publication of EP2551475A2 publication Critical patent/EP2551475A2/fr
Withdrawn legal-status Critical Current

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Classifications

    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
    • F01K13/00—General layout or general methods of operation of complete plants
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
    • F01K23/00—Plants characterised by more than one engine delivering power external to the plant, the engines being driven by different fluids
    • F01K23/02—Plants characterised by more than one engine delivering power external to the plant, the engines being driven by different fluids the engine cycles being thermally coupled
    • F01K23/06—Plants characterised by more than one engine delivering power external to the plant, the engines being driven by different fluids the engine cycles being thermally coupled combustion heat from one cycle heating the fluid in another cycle
    • F01K23/10—Plants characterised by more than one engine delivering power external to the plant, the engines being driven by different fluids the engine cycles being thermally coupled combustion heat from one cycle heating the fluid in another cycle with exhaust fluid of one cycle heating the fluid in another cycle
    • F01K23/106—Plants characterised by more than one engine delivering power external to the plant, the engines being driven by different fluids the engine cycles being thermally coupled combustion heat from one cycle heating the fluid in another cycle with exhaust fluid of one cycle heating the fluid in another cycle with water evaporated or preheated at different pressures in exhaust boiler
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
    • F01K7/00—Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating
    • F01K7/16—Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines being only of turbine type
    • F01K7/22—Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines being only of turbine type the turbines having inter-stage steam heating
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00—Methods of steam generation characterised by form of heating method
    • F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F22B1/18—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being a hot gas, e.g. waste gas such as exhaust gas of internal-combustion engines
    • F22B1/1807—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being a hot gas, e.g. waste gas such as exhaust gas of internal-combustion engines using the exhaust gases of combustion engines
    • F22B1/1815—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being a hot gas, e.g. waste gas such as exhaust gas of internal-combustion engines using the exhaust gases of combustion engines using the exhaust gases of gas-turbines

Definitions

  • the invention relates to a method for retrofitting a nuclear power plant having a nuclear steam generating unit, the steam is fed to at least one steam turbine group having at least one steam turbine with a medium pressure level and at least one steam turbine with a low pressure level, wherein the nuclear steam generating unit by at least one gas turbine plant and at least one heat recovery steam generator is replaced and at least one Vorschaltdampfturbine is reinstalled, wherein the heat recovery steam generator has a high-pressure steam generator, the steam is supplied to the Vorschaltdampfturbine, wherein exhaust steam is supplied to the Vorschaltdampfturbine the steam turbine group.
  • Nuclear power generation is politically contentious. For example, no operating licenses have been issued for nuclear power plants that have already been completely completed. There are also governments that have basically decided to phase out nuclear power.
  • nuclear power plants with a pressure reactor are suitable for retrofitting because the secondary circuit is not radioactively loaded and thus the existing steam turbine groups can continue to be used after a changeover.
  • the gas turbine plants include a compressor, a combustion chamber and a gas turbine.
  • the hot flue gas leaves the gas turbine and is directed into a heat recovery steam generator.
  • a particular challenge is the integration of existing steam turbine groups in the conversion of a nuclear power plant.
  • An optimal integration of the existing steam turbine groups is crucial for the efficiency of the converted power plant.
  • Steam turbines of nuclear power plants include steam turbines with a higher pressure level and steam turbines with a lower pressure level. Compared to modern power plant processes, however, the steam turbines with the higher pressure stage work only at a medium pressure level. Therefore, the steam turbines of the steam turbine group of nuclear power plants are hereinafter referred to as medium-pressure steam turbines and low-pressure steam turbines.
  • the DE 199 62 403 A1 describes a method of retrofitting a nuclear power plant, which also replaces the nuclear steam generation system with gas turbine plants with heat recovery steam generators.
  • steam is produced by means of a high pressure steam generator.
  • a high-pressure steam turbine is connected in front of the existing steam turbine group, which is referred to as Vorschaltdampfturbine.
  • the high pressure steam produced in the heat recovery steam generator is fed to this newly installed upstream steam turbine.
  • the existing steam turbine group is supplied with the exhaust steam of the upstream steam turbine.
  • the object of the invention is to provide a method for retrofitting a nuclear power plant with the features described above, achieved by the application of the converted nuclear power plant the highest possible efficiency and in which the largest possible proportion of the existing components of the nuclear power plant is used.
  • the heat recovery steam generator has at least one medium-pressure steam generator, the steam of the steam turbine is supplied to the average pressure level.
  • the heat recovery steam generator thus comprises not only a high pressure steam generator but additionally a medium pressure steam generator.
  • the medium-pressure steam turbine is thus not only exhaust steam fed to the feed steam turbine but additionally or alternatively live steam, which is produced in the medium-pressure steam generator.
  • the proportions of the exhaust steam of the ballast turbine and of the live steam produced in the medium-pressure steam generator can be varied. This makes it possible to optimally set the steam parameters for the medium-pressure steam turbine. Thus, the efficiency of the overall process is increased.
  • the conversion of the nuclear power plant according to the invention also makes it possible, if necessary, to use the already existing feedwater preheaters.
  • the medium-pressure steam generator comprises a medium-pressure evaporator, which is arranged in the heat recovery steam generator.
  • the medium-pressure evaporator is preferably fed by a medium-pressure steam drum, which is arranged outside of the heat recovery steam generator.
  • the steam produced is passed through a medium-pressure superheater, which is also arranged in the heat recovery steam generator before it is fed to the medium-pressure steam turbine.
  • the live steam produced in the medium-pressure steam generator is combined with the exhaust steam of the upstream steam turbine and then passed through a reheater before it is fed to the medium-pressure steam turbine.
  • the heat recovery steam generator additionally has a low-pressure steam generator.
  • high pressure evaporator, medium pressure evaporator and low pressure evaporator are thus arranged together in the heat recovery steam generator.
  • the pressure level of the high-pressure steam is preferably in a range of 110 to 200 bar.
  • the pressure level of the medium pressure steam is preferably in a range of 35 to 75 bar.
  • the pressure level of the low-pressure steam is preferably in a range of 4 to 10 bar.
  • the low pressure evaporator is fed by a low pressure steam drum located outside the heat recovery steam generator. If necessary, the steam produced in the low-pressure evaporator can additionally be passed through a low-pressure superheater, which is likewise arranged in the heat recovery steam generator.
  • the low-pressure steam turbines are supplied both with the exhaust steam of the medium-pressure steam turbine and with fresh steam from the low-pressure steam generator, their proportions being adapted such that the existing low-pressure steam turbines are optimally utilized after the conversion. This additionally increases the overall efficiency of the converted power plant.
  • each gas turbine is followed by a separate heat recovery steam generator, so that this flue gas is supplied by only one gas turbine. It is also possible that waste heat steam generators the flue gas is fed to a group of gas turbines, so that, for example, always two gas turbines share a heat recovery steam generator.
  • the nuclear steam generation system usually generates saturated steam. This saturated steam is fed to medium pressure steam turbines, which are designed as saturated steam medium pressure steam turbines.
  • the nuclear power plant is converted so that the Abdampfzubine the Vorschaltdampfturbine and produced in the medium pressure steam generator live steam to the steam parameters of the existing nuclear power plant at the entrance of the existing steam turbine.
  • the entire steam turbine group is retained in this variant in its previous form.
  • the water separator used between medium-pressure steam turbine and low-pressure steam turbine which are also referred to as separators, continue to be used after the conversion, as well as existing reheaters.
  • the Vorschaltdampfturbine and the medium-pressure steam generator is designed so that the steam parameters of the exhaust steam of the Vorschaltdampfturbine and produced in the medium-pressure steam generator fresh steam in the medium pressure turbine still permissible areas, are shifted to higher temperatures and lower pressures such that at the outlet the medium-pressure steam turbine lower vapor levels are present.
  • the Abdampfzu coincides the medium-pressure steam turbine in the superheated area.
  • water separators and / or reheaters are removed between the steam turbines of the steam turbine group during conversion of the nuclear power plant.
  • the existing saturated steam medium pressure turbine is replaced by a new medium pressure steam turbine, which is designed for other steam parameters.
  • the exhaust steam of the feed steam turbine and the live steam produced in the medium-pressure steam generator are guided in this variant via a reheater in the heat recovery steam generator.
  • the superheated steam is fed to the new medium pressure steam turbine.
  • the new medium-pressure steam turbine is designed so that the parameters of its exhaust steam correspond to the steam parameters at the inlet to the low-pressure steam turbines, the original steam turbine group.
  • the water separator and possibly also the original reheater before the low-pressure steam turbines can also be omitted.
  • a new building is erected on the site of the nuclear power plant during refitting.
  • the gas turbine plants are arranged.
  • the Vorschaltdampfturbinen are arranged in the newly built building. It proves to be particularly advantageous if at least one gas turbine plant forms a single-shaft unit with a Vorschaltdampfturbine.
  • the feed turbine with the gas turbine, the compressor and the generator is arranged on a shaft.
  • the Vorschaltdampfturbinen also each drive a separate generator. Such a concept is called a multi-shaft system.
  • At least one ballast turbine is arranged in the existing turbine house of the steam turbine group.
  • the nuclear steam generating unit ie the entire primary circuit comprising a pressurized water reactor with steam generator, has been replaced by several gas turbine units 1 with heat recovery steam generators 2.
  • gas turbine units 1 with heat recovery steam generators 2 In Fig. 1 By way of example, three gas turbine plants 1 with heat recovery steam generators 2 are shown.
  • Each gas turbine plant 1 comprises a compressor 3, a combustion chamber 4, a gas turbine 5 and a generator 6.
  • the compressor 3, the gas turbine 5 and the generator 6 are arranged on a common shaft 7.
  • each gas turbine 5 is followed by a separate heat recovery steam generator 2.
  • the flue gas of each gas turbine 5 is supplied to the respective heat recovery steam generator 2.
  • Each heat recovery steam generator 2 comprises a high pressure steam generator 8, a medium pressure steam generator 9 and a low pressure steam generator 10.
  • the steam produced in the high-pressure steam generators 8 is conducted into a high-pressure bus 11, which leads the high-pressure steam to a newly installed upstream steam turbine 12 during conversion.
  • the Vorschaltdampfturbine 12 is designed as a high-pressure steam turbine with its own shaft 13 and a separate generator 14. At the in Fig. 1 variant shown, the high pressure steam is supplied to a common feed steam turbine 12.
  • the steam produced in the medium-pressure steam generators 9 is conducted into a medium-pressure manifold 15. Together with the exhaust steam 18 of the Vorschaltdampfturbine 12 of the medium-pressure steam of the existing medium-pressure steam turbine 16 of the existing steam turbine 17 is supplied.
  • the steam turbine group 17 includes low-pressure steam turbines 19.
  • low-pressure steam turbines 19 are shown by way of example. All sub-turbines of the steam turbo group 17 are arranged on a common shaft 20 and drive a generator 21 at.
  • the low-pressure steam turbines 19 are supplied with the exhaust steam 22 of the medium-pressure steam turbine 16 and live steam, which is produced in the low-pressure steam generators 10.
  • the steam produced in the low-pressure steam generators 10 is first brought together in a low-pressure manifold 23 before it is fed to the low-pressure steam turbine 19.
  • the exhaust steam 24 of the low-pressure steam turbine 19 is condensed in capacitors 25.
  • the condensate is discharged via a condensate pump 26.
  • high-pressure feedwater pumps 27, medium pressure feedwater pumps 28 and low-pressure feedwater pumps 29 provide the respective steam generators with feedwater.
  • Fig. 2 shows a flow chart of a used for the conversion of a nuclear power plant heat recovery steam generator 2 without reheating.
  • the flue gas 30 of one of the gas turbines 5 is fed to the heat recovery steam generator 2 on the input side.
  • the flue gas 30 first flows past the high-pressure steam generator 8, then past the medium-pressure steam generator 9 and finally past the low-pressure steam generator 10, and then leaves the waste-heat steam generator 2 on the output side.
  • the high pressure steam generator 8 has a high pressure evaporator 31 to which feed water from a high pressure steam drum 32 is supplied.
  • the resulting high-pressure steam first flows back into the high-pressure steam drum 32 and is then fed to a high-pressure superheater 33, in order then to be fed into the high-pressure bus 11.
  • the high-pressure steam is expanded in the Vorschaltdampfturbine 12 to a medium pressure level.
  • medium-pressure steam generator 9 live steam is produced at a medium pressure level.
  • the medium pressure steam generator 9 has a medium pressure evaporator 34, the feed water from a medium pressure steam drum 35 is supplied.
  • the medium-pressure steam produced in the medium pressure evaporator 34 first flows back into the medium pressure steam drum 35, through a medium pressure superheater 36 in the medium pressure manifold 15.
  • the produced in the medium pressure steam generator 9 live steam and the exhaust steam 18 of the Vorschaltdampfturbine 12 of the medium pressure steam turbine 16 of the steam turbine 17 are supplied.
  • Low-pressure steam generator 10 produces low-pressure steam.
  • feedwater is supplied to a low-pressure evaporator 38 from a low-pressure steam drum 37.
  • the generated low-pressure steam flows back into the low-pressure steam drum 37 and then into a low-pressure superheater 39. Thereafter, the low-pressure steam is fed into the low-pressure bus bar 23.
  • the steam produced in the low-pressure steam generator 10 is supplied to the low-pressure steam turbines 19 together with the exhaust steam 22 of the medium-pressure steam turbine 16.
  • the exhaust steam 24 of the low pressure steam turbine 19 is liquefied in the condensers 25.
  • the condensate pump 26 conveys the condensate into a condensate preheater 40, which is arranged in the heat recovery steam generator. A portion of the condensate is fed to the low pressure steam drum 37 after the condensate preheater 40. The remaining part of the condensate flows into a feedwater pump 41.
  • the feedwater pump 41 is designed in the embodiment as a high-pressure feed pump with medium pressure extraction.
  • Feedwater is discharged via the medium pressure removal, which first flows through a feedwater preheater 42 before it enters the medium pressure steam drum 35.
  • High-pressure side feed water flows from the feedwater pump 41 via a first high pressure economizer 43 and a second high pressure economizer 44 in the high pressure steam drum 32nd
  • a heat recovery steam generator 2 is used for the conversion of the nuclear power plant, in which over the previously described variant, a reheating takes place.
  • the exhaust steam 18 of the upstream steam turbine 12 is combined with the fresh steam produced in the medium-pressure steam generator 9 and passed through a reheater 45, which is also arranged in the heat recovery steam generator 2. Thereafter, the steam of the medium-pressure steam turbine 16 flows to.

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  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Combustion & Propulsion (AREA)
  • Mechanical Engineering (AREA)
  • General Engineering & Computer Science (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Physics & Mathematics (AREA)
  • Thermal Sciences (AREA)
  • Engine Equipment That Uses Special Cycles (AREA)
EP20120005081 2011-07-28 2012-07-09 Retrofitting of a nuclear power plant Withdrawn EP2551475A2 (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE102011108711A DE102011108711A1 (de) 2011-07-28 2011-07-28 Umrüstung eines Kernkraftwerks

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EP2551475A2 true EP2551475A2 (fr) 2013-01-30

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EP20120005081 Withdrawn EP2551475A2 (fr) 2011-07-28 2012-07-09 Retrofitting of a nuclear power plant

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EP (1) EP2551475A2 (fr)
DE (1) DE102011108711A1 (fr)
EA (1) EA201200957A1 (fr)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2021160367A1 (fr) * 2020-02-11 2021-08-19 Siemens Aktiengesellschaft Renouvellement d'installation de turbine à vapeur, et installation associée

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1997018386A1 (fr) 1995-11-14 1997-05-22 Westinghouse Electric Corporation Systeme et procede de realimentation par turbine a combustion de turbines existantes a vapeur faiblement surchauffee
DE19962403A1 (de) 1999-12-23 2001-06-28 Alstom Power Schweiz Ag Baden Verfahren zum Umrüsten eines Sattdampf erzeugenden Systems mit mindestens einer Dampfturbogruppe sowie nach dem Verfahren umgerüstetes Kraftwerk

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3742876A1 (de) * 1987-12-17 1989-06-29 Siemens Ag Verfahren und anordnung zur erneuerung eines senkrecht angeordneten dampferzeugers, insbesondere in kernkraftwerken
CH678987A5 (fr) * 1989-10-24 1991-11-29 Asea Brown Boveri
DE19805119A1 (de) * 1998-02-09 1999-08-12 Werner Foppe Verfahren zur alternativ-energietechnischen Weiternutzung von Dampfkraftwerkseinheiten nach Stillegung von Atommeilern oder Feuerungsanlagen von Brennstoffkraftwerken
DE19939141A1 (de) * 1999-07-21 2000-07-13 Heinz Berthold Verfahren zur Umwandlung von KKW in fossilbeheizte Normal-KW (reversibel)

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1997018386A1 (fr) 1995-11-14 1997-05-22 Westinghouse Electric Corporation Systeme et procede de realimentation par turbine a combustion de turbines existantes a vapeur faiblement surchauffee
DE19962403A1 (de) 1999-12-23 2001-06-28 Alstom Power Schweiz Ag Baden Verfahren zum Umrüsten eines Sattdampf erzeugenden Systems mit mindestens einer Dampfturbogruppe sowie nach dem Verfahren umgerüstetes Kraftwerk

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2021160367A1 (fr) * 2020-02-11 2021-08-19 Siemens Aktiengesellschaft Renouvellement d'installation de turbine à vapeur, et installation associée

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Publication number Publication date
DE102011108711A1 (de) 2013-01-31
EA201200957A1 (ru) 2013-03-29

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