EP2711508A1 - Energieumwandlungszyklus für durch einen natriumgekühlten schnellen Neutronenreaktor erzeugten Dampf - Google Patents

Energieumwandlungszyklus für durch einen natriumgekühlten schnellen Neutronenreaktor erzeugten Dampf Download PDF

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Publication number
EP2711508A1
EP2711508A1 EP13184602.4A EP13184602A EP2711508A1 EP 2711508 A1 EP2711508 A1 EP 2711508A1 EP 13184602 A EP13184602 A EP 13184602A EP 2711508 A1 EP2711508 A1 EP 2711508A1
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EP
European Patent Office
Prior art keywords
steam
pressure
turbine
state
temperature
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.)
Granted
Application number
EP13184602.4A
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English (en)
French (fr)
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EP2711508B1 (de
Inventor
Frederic Lamarque
Bruno Renard
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General Electric Technology GmbH
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Alstom Technology AG
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    • 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steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating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steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines being only of turbine type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steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines being only of turbine type the turbines having inter-stage steam heating
    • F01K7/223—Inter-stage moisture separation
    • 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
    • F22B1/06—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium
    • F22B1/063—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium for metal cooled nuclear reactors

Definitions

  • the present invention relates to an energy conversion cycle for converting energy supplied by a sodium-cooled fast neutron reactor (so-called Sodium Fast Neutron Reactor - FNR).
  • the invention relates to a nuclear installation which comprises at least a nuclear reactor, a steam generator, steam turbines and a dryer and/or a super-heater.
  • Gaseous or liquid water circulates in a closed circuit through the unit and is subject to variations of temperature and of pressure.
  • cycle refers to changes of temperature and pressure of the gaseous or liquid water between the outlet of the steam generator and the return of same into the steam generator.
  • a "nuclear cycle" corresponds to changes of temperature and pressure generally encountered in a nuclear installation which usually operates with steam coming from the outlet of the steam generator, said steam being close to the saturation curve.
  • a "fossil fuel cycle” corresponds to changes of temperature and pressure generally encountered in a thermal power station using fossil fuel-fired boilers.
  • the sodium-cooled fast neutron reactor of the French Phenix FNR power station employs steam turbine technology enabling operation with steam working at temperature and pressure conditions close to those encountered in a "fossil fuel cycle" thereby allowing the steam to expand when it passes through a high-pressure turbine and a medium-pressure turbine in conditions of dry steam.
  • the temperature and pressure conditions in the different components of the installation namely the turbines and the super-heater, must not be too high so as to have working lives of the order of 60 years.
  • the subject of the present invention is an energy conversion cycle for the steam produced by a sodium-cooled fast neutron reactor, which improves the lifetime of the equipment.
  • the cycle of the sodium-cooled fast neutron reactor as claimed in the invention is more situated in the zone of saturated steam than the cycles of sodium-cooled fast neutron reactors of the prior art, while working with the same temperature and pressure conditions directly at the outlet of the steam generator, which conditions are close to those encountered in thermal power stations.
  • the cycle as claimed in the invention allows efficiency to be increased compared with that currently obtained with the sodium-cooled fast neutron reactor of the French Phenix FNR power station.
  • This cycle can be used for high electrical power reactors to classes above 1500 MWe.
  • the invention allows a sodium-cooled fast neutron reactor to be used with standard components currently used for fossil fuel or nuclear power stations.
  • the invention thus makes it possible to avoid the implementation of super-heaters, such as those used for the sodium-cooled fast neutron reactor in French FNR power stations, these super-heaters being difficult to design and costly to fabricate.
  • the steam in its "fossil fuel cycle" initial state thereof, is at a pressure comprised between 150 and 200 bars and at a temperature comprised between 450 and 570°C.
  • the intermediate state is defined for a pressure comprised between 30 and 50 bars and a temperature comprised between 234 and 300°C.
  • the steam in the first wet state thereof is at a temperature comprised between 152 and 188°C and at a pressure comprised between 5 and 12 bars after the second expansion.
  • the steam in the drying and super-heating state thereof is at a temperature comprised between 215 and 255°C and a pressure comprised between 5 and 12 bars.
  • the steam in the final state thereof is condensed at a temperature which depends on the cold source used.
  • the present invention also relates to a steam turbine installation comprising a sodium-cooled fast neutron reactor, for the implementation of the cycle defined previously, and:
  • a pipe connecting the outlet from the very high-pressure turbine and the super-heater allows heated steam to be drawn off downstream of the very high-pressure turbine, said steam being used by the super-heater.
  • the intermediate turbine is a high-pressure turbine and the outlet turbines are either medium and low-pressure turbines or only low-pressure turbines.
  • the low-pressure turbines are supplied in parallel.
  • the high-pressure and the medium-pressure turbine (when this exists in the second embodiment) are arranged in a combined unit.
  • the very high-pressure/high temperature and the intermediate turbine are arranged so as to expand the steam from a fossil fuel cycle initial state at a pressure comprised between 150 and 200 bars and at a temperature comprised between 450 and 570°C, to a wet steam state the temperature of which is comprised between 152 and 188°C and the pressure of which is comprised between 5 and 12 bars after the first expansion and the second expansion.
  • the dryer and the super-heater allow the steam to pass from an initial wet steam state the temperature of which is comprised between 152 and 188°C and the pressure of which is comprised between 5 and 12 bars after the second expansion, to a drying and super-heating state, the pressure of which is comprised between 5 and 12 bars and the temperature of which is comprised between 215 and 255°C.
  • the very high-pressure/high-temperature turbine, the intermediate turbine and the outlet turbines (without a medium-pressure turbine) turn, at the network frequency, e.g. at 3000 rpm, an alternator input shaft that produces electrical power of less than 1200 MWe.
  • the very high-pressure/high-temperature turbine, the intermediate turbine and the outlet turbines turn, at half the network frequency, e.g. at 1500 rpm, an alternator input shaft that produces electrical power of greater than 1200 MWe.
  • the cycle as claimed in the invention as shown in figure 3 can be implemented by two different steam turbine installations that each present a sodium-cooled fast neutron nuclear reactor 1, 1' which allows energy to be liberated to produce steam in a steam generator 2, 2', a very high-pressure/high-temperature turbine 3, 3', an intermediate turbine 4, 3", and outlet turbines 5, 4', 5', these turbines being suitable for turning an input shaft 6a, 6a' of an alternator 6, 6' which produces electricity.
  • the very high-pressure/high-temperature turbine 3, 3' is connected to one or a plurality of steam generators 2, 2' of the nuclear reactor 1, 1', by one or a plurality of pipes, and allows a first expansion of the steam to be made, to bring it from a "fossil fuel cycle" initial state at the outlet from the steam generator 2, 2' of the reactor 1, 1' to an intermediate state of temperature and pressure of the steam, characteristic of a "nuclear cycle" initial state.
  • valves V, V' allow the flow-rate of steam coming from the steam generator(s) 2, 2' to be adjusted.
  • the intermediate turbine is a high-pressure turbine 4 connected by a pipe to the very high-pressure/high-temperature turbine 3, operating mainly with saturated steam.
  • the high-pressure turbine 4 allows a second expansion of steam to be performed from the intermediate state corresponding to a "nuclear cycle" initial state until steam in a first wet state under the saturation curve S is obtained.
  • the drying and super-heating of the steam are then performed by successively passing into a dryer 7, physically separating liquid water and steam, then into a super-heater 8, these devices being situated in a pipe 12 between the high-pressure turbine 4 and the low-pressure turbines 5.
  • the two low-pressure turbines 5 supplied in parallel and connected to the dryer 7 and to the super-heater 8 by a pipe 12 allow a third expansion of steam to be performed from its super-heated state to a final state. More than two low-pressure turbines 5 can be used to perform this third expansion.
  • Water recovered from the dryer 7 and from the super-heater 8 is sent back into the cycle by pipes 11.
  • a system 9, 10 of a condenser, re-heaters and pumps is used to bring condensed steam into the steam generator 2, but is not described here and is known from the prior art.
  • This installation can produce electrical power of the order of 600 to 1200 Mwe.
  • the intermediate turbine is a high-pressure turbine 3" connected by a pipe to the very high-pressure/high-temperature turbine 3', operating mainly with saturated steam.
  • the high-pressure turbine 3" allows a second expansion of steam to be performed from the intermediate state corresponding to a "nuclear cycle" initial state until steam in a first wet state under the saturation curve S is obtained.
  • the drying and super-heating of the steam are then performed by successively passing said steam into a dryer 7 physically separating liquid water and steam, then into a super-heater 8, these devices being situated in pipes between the high-pressure turbine 3" and a medium-pressure turbine 4'.
  • a pipe 13' connecting the outlet from the very high pressure turbine 3' and the super-heater 8' allows heated steam to be drawn off downstream of the very high-pressure turbine 3' used by the super-heater 8'.
  • the medium-pressure turbine 4' and the two low-pressure turbines 5' supplied in parallel and connected to the medium-pressure turbine 4' by a pipe 12' allow a third expansion of steam to be performed from the super-heated state thereof to a final state. More than two low-pressure turbines 5' can be used to produce this third expansion.
  • Water recovered at the level of the dryer 7' and from the super-heater 8' is sent back into the cycle by pipes 11'.
  • a system 9', 10' of a condenser, re-heaters and pumps is used to bring condensed steam into the steam generator 2', but is not described here and is known from the prior art.
  • a Mollier diagram represents the entropy on the abscissa and the enthalpy of a fluid on the ordinate.
  • the fluid is water and a saturation curve S of water is shown in this diagram.
  • the saturation curve S corresponds to the limit between two domains, the water takes, for a given entropy, the form of dry steam for enthalpies greater than the enthalpy of the saturation curve S, and the form of saturated steam (or wet steam) for enthalpies less than the enthalpy of the saturation curve S.
  • the name of dry saturated steam is given to the state of water just on the saturation curve S.
  • the water content of wet steam increases as the enthalpy decreases, until attaining a water content of 1 when all of the steam phase is condensed into liquid water.
  • the saturation curve S delimits a domain of saturated wet steam S2, with respect to a gaseous domain of dry, super-heated steam S1.
  • Curve A represents a cycle similar to that used in a sodium-cooled fast neutron reactor of the French Phenix power station FNR.
  • Curve B represents a cycle used in a sodium-cooled fast neutron reactor FNR as claimed in the invention.
  • the steam coming from one or a plurality of steam generators of the reactor is at a temperature of around 500°C and at a pressure of the order of 180 bars.
  • the steam After a first expansion in a very high-pressure turbine between points 11 and 12, the steam is at a temperature of the order of 250°C and at a pressure of the order of 30 bars.
  • the steam is then expanded up to point 14 by a medium-pressure turbine. Between points 13 and 14, the pressure decreases from 30 bars to 5 bars and the temperature decreases from 380°C to 180°C.
  • the steam is then expanded up to point 15 by low-pressure turbines.
  • a condenser and systems of heat exchangers and pumps then allow the condensed steam to be re-injected into the steam generator or generators of the reactor.
  • a first expansion therefore brings the steam which is at a temperature of 500°C and at a pressure of 180 bars at point 21 to an intermediate state with temperature and pressure corresponding to point 22, properties close to the initial point of a "traditional nuclear cycle".
  • the first expansion thus brings the steam from point 21 to point 22 corresponding to the "nuclear cycle" initial state, situated above the saturation curve S.
  • the steam is substantially at a temperature of 280°C and at a pressure of 40 bars, in figure 3 .
  • the steam is expanded between point 22 and point 23 where same is in a first wet state.
  • the steam is substantially at a temperature of 170°C and at a pressure of 7 bars.
  • the steam is dried and super-heated from the first wet state thereof at point 23, to a first dried and super-heated state represented by point 24, the pressure remaining substantially constant.
  • the steam is substantially at a temperature of 240°C and at a pressure of 7 bars.
  • the steam is then expanded between point 24 and a final point 25.
  • the steam is substantially at a temperature of 35°C and at a pressure of 60 mbars.
  • the steam is at a temperature comprised between 450 and 570°C and at a pressure comprised between 150 and 200 bars in the "fossil fuel cycle" initial state.
  • the steam is at a temperature comprised between 234 and 300°C and at a pressure comprised between 30 and 50 bars after the second expansion.
  • the steam, in the first wet state is at a temperature comprised between 152 and 188°C and a pressure comprised between 5 and 12 bars after the second expansion.
  • the steam can be at a temperature comprised between 215 and 255°C and a pressure comprised between 5 and 12 bars.

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  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Mechanical Engineering (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Combustion & Propulsion (AREA)
  • Chemical & Material Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Thermal Sciences (AREA)
  • Engine Equipment That Uses Special Cycles (AREA)
  • Control Of Eletrric Generators (AREA)
EP13184602.4A 2012-09-19 2013-09-16 Verfahren zur Umwandlung von Energie in einem Energieumwandlungszyklus für durch einen natriumgekühlten schnellen Neutronenreaktor erzeugten Dampf, und entsprechende Dampfturbineanordnung Active EP2711508B1 (de)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR1258804A FR2995628A1 (fr) 2012-09-19 2012-09-19 Cycle de conversion d'energie par vapeur produite par un reacteur a neutrons rapides refroidi au sodium

Publications (2)

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EP2711508A1 true EP2711508A1 (de) 2014-03-26
EP2711508B1 EP2711508B1 (de) 2017-07-05

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EP13184602.4A Active EP2711508B1 (de) 2012-09-19 2013-09-16 Verfahren zur Umwandlung von Energie in einem Energieumwandlungszyklus für durch einen natriumgekühlten schnellen Neutronenreaktor erzeugten Dampf, und entsprechende Dampfturbineanordnung

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EP (1) EP2711508B1 (de)
KR (1) KR101548142B1 (de)
CN (1) CN103670552B (de)
FR (1) FR2995628A1 (de)
RU (1) RU2561839C2 (de)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2024130919A1 (zh) * 2022-12-20 2024-06-27 西安热工研究院有限公司 一种化石燃料锅炉-高温气冷堆联合动力发电系统及方法

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0147304A2 (de) * 1983-12-21 1985-07-03 Commissariat A L'energie Atomique Natrium-Wasser-Dampferzeuger mit geraden konzentrischen Rohren und Gaszirkulation in dem ringförmigen Raum
EP0163564A1 (de) * 1984-05-11 1985-12-04 Commissariat A L'energie Atomique Schneller Neutronenkernreaktor mit Dampferzeuger, integriert im Behälter

Family Cites Families (7)

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Publication number Priority date Publication date Assignee Title
SU486593A1 (ru) * 1972-05-10 1976-08-25 Предприятие П/Я В-2679 Атомна электростанци с несколькими дерными раеакторами
JPS607161B2 (ja) * 1977-11-08 1985-02-22 日本原子力事業株式会社 原子力プラントの給水供給方法と装置
DE3822056C1 (en) * 1988-06-30 1989-09-14 Asea Brown Boveri Ag, 6800 Mannheim, De Nuclear reactor installation for the generation of electrical current utilising high-temperature heat
WO2004012205A1 (de) * 2002-07-26 2004-02-05 Alstom Technology Ltd Verfahren zum betrieb eines kernkraftwerkes sowie vorrichtung zur durchführung des verfahrens
RU2253917C2 (ru) * 2003-01-27 2005-06-10 Закрытое акционерное общество "Агентство регионального развития" Способ эксплуатации атомной паротурбинной энергетической установки и установка для его осуществления
RU2394291C2 (ru) * 2007-08-15 2010-07-10 Селиванов Николай Павлович Атомная электростанция и тепловыделяющий элемент ядерного реактора
US8091369B2 (en) * 2008-07-11 2012-01-10 Air Products And Chemicals, Inc. Method and apparatus for generating electrical power

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0147304A2 (de) * 1983-12-21 1985-07-03 Commissariat A L'energie Atomique Natrium-Wasser-Dampferzeuger mit geraden konzentrischen Rohren und Gaszirkulation in dem ringförmigen Raum
EP0163564A1 (de) * 1984-05-11 1985-12-04 Commissariat A L'energie Atomique Schneller Neutronenkernreaktor mit Dampferzeuger, integriert im Behälter

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2024130919A1 (zh) * 2022-12-20 2024-06-27 西安热工研究院有限公司 一种化石燃料锅炉-高温气冷堆联合动力发电系统及方法

Also Published As

Publication number Publication date
RU2561839C2 (ru) 2015-09-10
FR2995628A1 (fr) 2014-03-21
KR101548142B1 (ko) 2015-08-28
CN103670552A (zh) 2014-03-26
EP2711508B1 (de) 2017-07-05
KR20140037778A (ko) 2014-03-27
RU2013142429A (ru) 2015-03-27
CN103670552B (zh) 2016-03-16

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