US20170321879A1 - Horizontal Steam Generator for a Reactor Plant with a Water-Cooled Water-Moderated Power Reactor and a Reactor Plant with the said Steam Generator - Google Patents

Horizontal Steam Generator for a Reactor Plant with a Water-Cooled Water-Moderated Power Reactor and a Reactor Plant with the said Steam Generator Download PDF

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US20170321879A1
US20170321879A1 US15/535,360 US201515535360A US2017321879A1 US 20170321879 A1 US20170321879 A1 US 20170321879A1 US 201515535360 A US201515535360 A US 201515535360A US 2017321879 A1 US2017321879 A1 US 2017321879A1
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heat
steam generator
reactor
exchange
coolant
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US15/535,360
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Dmitriy Aleksandrovich LAKHOV
Aleksey Vladimirovich SAFRONOV
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Aktsyonernoe Obshchestivo "ordena Trudovogo Krasnogo Znameni I Ordena Truda Chssr Opytnoe
Gidropress OKB
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Aktsyonernoe Obshchestivo "ordena Trudovogo Krasnogo Znameni I Ordena Truda Chssr Opytnoe
Gidropress OKB
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Assigned to AKTSYONERNOE OBSHCHESTVO "ORDENA TRUDOVOGO KRASNOGO ZNAMENI I ORDENA TRUDA CHSSR OPYTNOE KONSTRUCTORSKOE BYURO "GIDROPRESS" (AO OKB "GIDROPRESS") reassignment AKTSYONERNOE OBSHCHESTVO "ORDENA TRUDOVOGO KRASNOGO ZNAMENI I ORDENA TRUDA CHSSR OPYTNOE KONSTRUCTORSKOE BYURO "GIDROPRESS" (AO OKB "GIDROPRESS") ASSIGNMENT OF ASSIGNORS INTEREST (SEE DOCUMENT FOR DETAILS). Assignors: LACHOV, Dmitriy Aleksandrovich, SAFRONOV, ALEKSEY VALDIMIROVICH
Publication of US20170321879A1 publication Critical patent/US20170321879A1/en
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    • 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
    • F22B1/023—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers with heating tubes, for nuclear reactors as far as they are not classified, according to a specified heating fluid, in another group
    • 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
    • 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
    • F22B1/16—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour
    • F22B1/162—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour in combination with a nuclear installation
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B29/00—Steam boilers of forced-flow type
    • F22B29/06—Steam boilers of forced-flow type of once-through type, i.e. built-up from tubes receiving water at one end and delivering superheated steam at the other end of the tubes
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/002—Component parts or details of steam boilers specially adapted for nuclear steam generators, e.g. maintenance, repairing or inspecting equipment not otherwise provided for
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/22—Drums; Headers; Accessories therefor
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/22—Drums; Headers; Accessories therefor
    • F22B37/228—Headers for distributing feedwater into steam generator vessels; Accessories therefor
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28D—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
    • F28D7/00—Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall
    • F28D7/16—Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall the conduits being arranged in parallel spaced relation
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F9/00—Casings; Header boxes; Auxiliary supports for elements; Auxiliary members within casings
    • F28F9/007—Auxiliary supports for elements
    • F28F9/013—Auxiliary supports for elements for tubes or tube-assemblies
    • F28F9/0132—Auxiliary supports for elements for tubes or tube-assemblies formed by slats, tie-rods, articulated or expandable rods
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28D—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
    • F28D21/00—Heat-exchange apparatus not covered by any of the groups F28D1/00 - F28D20/00
    • F28D2021/0019—Other heat exchangers for particular applications; Heat exchange systems not otherwise provided for
    • F28D2021/0061—Other heat exchangers for particular applications; Heat exchange systems not otherwise provided for for phase-change applications
    • F28D2021/0064—Vaporizers, e.g. evaporators
    • 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • This invention relates to electric power industry, and more particularly to horizontal steam generators for nuclear power plants with a water-cooled water-moderated power reactor (VVER) and to reactor plants with a VVER reactor and a horizontal steam generator.
  • VVER water-cooled water-moderated power reactor
  • a steam generator is the most important element of the reactor plant (RP) primary circuit of VVER nuclear power plants (NPP). Steam is generated in it due to the heat produced in the reactor, the steam is used as the turbine working medium for power generation. In addition to steam generation, steam generators must ensure reliable and continuous cooling of the reactor core in all NPP operation modes.
  • NPP steam generators are installed inside the reactor building containment and the containment dimensions are greatly influenced by the steam generator dimensions.
  • a steam generator has a vertical pressure vessel and vertical U-shaped heat-exchange tubes embedded in a horizontal tube sheet.
  • a steam generator has a horizontal pressure vessel and horizontal heat-exchange tubes embedded in vertical inlet and outlet headers of the primary circuit coolant.
  • the claimed invention relates to the horizontal steam generator concept, to its application in reactor plants in combination with VVER type reactors.
  • the steam generator disclosed in International Application WO9320386 issued on Oct. 14, 1993, IPC F22B1/02 has a horizontal pressure vessel and a horizontal heat-exchange tube bundle installed in the same, the tubes are embedded in vertical inlet and outlet headers of the primary circuit coolant.
  • a feed water supply device is located in the center of the heat-exchange tube bundle, which results in a significant horizontal break in the steam generator vessel filling with the heat-exchange surface.
  • Low power, increased specific amount of metal per structure and lower durability of the reactor plant steam generator are the consequences of insufficient steam generator pressure vessel filling with heat-exchange tubes.
  • a horizontal steam generator is disclosed in Russian Utility Model Patent No. 100590 issued on Dec. 20, 2010, IPC: F22B37/00.
  • the horizontal steam generator comprises a vessel with an elliptical bottom welded to each end of the same, the bottom comprises a ferrule with a flat lid with, according to the claimed utility model, the ratio between the average ferrule height and ferrule bore is between 0.1 and 0.9.
  • This technical solution is designed to reduce steam generator dimensions for facilitating its delivery from the manufacturing plant to its place of assembly and increasing the free space in the steam generator box.
  • the longitudinal dimension is reduced due to a shorter ferrule, but not a change in the steam generator pressure vessel length, i.e. the device does not reduce specific amount of metal per structure.
  • PWR type reactors pressurized water reactor
  • Reactor plants with PWR type reactors are usually equipped with vertical steam generators.
  • moderate steam load allows to apply a simple separation scheme while reliably ensuring the required water content of steam
  • moderate medium flow rate in the secondary circuit eliminates the vibration hazard in the heat-exchange tubes and other elements of the steam generator
  • the vertical cylindrical inlet and outlet headers of the primary circuit prevents accumulation of sludge deposits on their surfaces and thus reducing the hazard of corrosive damage of heat-exchange tubes in areas of their insertion in the said headers
  • increased supply of water in the secondary circuit increases reliability of reactor cooldown through the steam generator in case the emergency feed water system is used, and the accumulating capacity of such steam generator mitigates reactor plant transient modes
  • the horizontal position of the heat-exchange surface provides reliable natural medium circulation in the primary circuit even when the water level is below the upper rows of heat-exchange tubes, favorable conditions for primary circuit coolant natural circulation in emergency conditions are provided, convenient access to the heat-exchange tube bundle is provided for maintenance and control both from the primary and secondary circuit sides.
  • a tube sheet in a horizontal steam generator design has disadvantages due to high specific amount of metal per structure, manufacturing complexity, complexity of provision of leaktightness of the heat-exchange tube connection to the tube sheet.
  • Application of a tube sheet does not allow to install a large number of tubes in such steam generator, as a result, they are quite long.
  • the design of the above steam generator is approximately the same as the vertical steam generator design that is positioned horizontally in the reactor plant.
  • a special aspect of the reactor plant is a small number of tubes in its steam generators resulting from the fact that one tube sheet is installed in the distribution chamber, i.e. the entire heat-exchange surface is formed by single U-shaped tube loop.
  • heat-exchange tubes are long and their side walls are thin. This reduces the operation reliability of the reactor plant as its steam generators have a lower heat-exchange tube plugging margin and a higher hydraulic resistance of the heat-exchange tubes on the primary circuit side, which has an adverse effect on accident propagation.
  • VVER-1000 reactors are well-proven at the existing nuclear power plants in Russia and abroad. Naturally, reactor plant assemblies and parts that require improvement are identified periodically in the course of operation.
  • Russian Utility Model Patent No. 143541 issued on Jul. 27, 2014, IPC: G21C1/03 discloses a VVER-1000 reactor plant (RP) with four primary circuit coolant circulation loops, each containing a PGV-1000 steam generator and reactor coolant pump (RCP).
  • the RP primary circuit coolant circulation loop consists of two parts. The first part is a hot circulation pipeline connecting the RP and the steam generator, and the second part is a cold circulation pipeline used to pump the primary circuit coolant from the steam generator to the reactor with the RCP.
  • the function of each RP circulation loop is unconstrained transfer of the primary circuit coolant through the steam generator and RCP from and to the reactor.
  • the main function of the steam generator is generation of dry saturated steam due to heat transferred to the steam generator from the nuclear reactor core by the primary circuit coolant.
  • the RP, steam generator and RCP are interconnected by means of a welded pipeline with an inner diameter of 850 mm (DN850).
  • the RP is connected to the steam generator by the main circulation pipeline with a vertical pipe bend with a radius of 1340 mm.
  • Thermal expansion and vibration of all primary circuit systems occurs under the primary circuit water head.
  • High temperatures and pressure of the coolant affect pipeline bends and welded connections, which may lead to their damage to the extent of cracking.
  • the utility model is designed to prevent a damage to weld No. 111 on the circulation pipeline.
  • this utility model proposes connecting the steam generator hot header and the hot circulation pipeline via a small header such that the length of the hot circulation pipeline from the lower end of the small header to the hot circulation pipeline bend does not exceed 0.25 m and the length of the cold circulation pipeline is designed to match the hot circulation pipeline length.
  • the purpose of the claimed invention is to improve the performance of the reactor plant due to an increased number of heat-exchange tubes in the steam generator pressure vessel without a significant increase in its dimensions, with its possible installation in the reactor building boxes with no increase in the capital construction scope.
  • the steam generator heat-exchange tube number is important for increasing the steam generator power to improve steam parameters, in particular, pressure, which in its turn allows to improve the reactor plant efficiency.
  • Increase in the number of heat-exchange tubes in the steam generator pressure vessel also improves its durability, as in the event of a failure of one or more tubes they may be plugged an the device operation may be continued due to availability of additional heat-exchange tubes.
  • the number of heat-exchange tubes in the steam generator pressure vessel functioning as part of a reactor plant is increased, the latter is cooled down more efficiently, i.e. the critical heat flux ratio in the reactor core increases.
  • Increase in the number of heat-exchange tubes in the steam generator pressure vessel also reduces the specific amount of metal per structure of the vessel as the device capacity is increased in a smaller vessel.
  • the technical result of the claimed invention application consists in the increased heat transfer rate, reliability and durability of the steam generator due an increased number of heat-exchange tubes installed in the vessel with of serviceability and ease of manufacturing of U-shaped tubes, and reduced specific amount of metal per structure of the steam generator pressure vessel provided at the same time.
  • the technical result of the claimed invention application also includes increased reliability, durability and efficiency of the reactor plant, reduced specific amount of metal per structure of the reactor plant steam generators, and their ease of manufacturing.
  • a horizontal steam generator for a reactor plant with a water-cooled water-moderated power reactor comprising a cylindrical pressure vessel equipped at least with one feed water supply connection pipe and one steam removal connection pipe, and two elliptical bottoms, internals, primary circuit coolant inlet and outlet headers connected to a heat-exchange tube bundle forming a steam-generator heat-exchange surface, the heat-exchange tube bundle being divided into banks by intertubular tunnels, wherein distance S between the primary circuit coolant header centerlines in the transverse direction of the steam generator pressure vessel has been selected based on the following ratio:
  • D vess is the steam generator pressure vessel inner diameter
  • steam generator length L v along the inner surfaces of the elliptical bottoms has been selected based on the following ratio:
  • D head is the coolant header outer diameter in the drilled part, mm
  • ⁇ is the heat-exchange tube central bend angle, deg.,
  • B 1 is the width of the heat-exchange tube central intertubular tunnel, mm,
  • B 2 is the width of the heat-exchange tube intertubular tunnel opposite to the coolant header, mm,
  • S head is the heat-exchange tube circumferential spacing on the outer surface of the coolant header, mm,
  • Sh is the spacing between heat-exchange tubes in the horizontal heat-exchange bundle row, mm,
  • H hes is the steam generator heat-exchange surface area, m 2 ,
  • N tb is the number of steam generator heat-exchange tubes, pcs.
  • d is the outer heat-exchange tube diameter, mm
  • ⁇ is the distance from the outer heat-exchange bundle tube to the steam generator bottom inner surface along the longitudinal steam generator axis, wherein central heat-exchange tube bend angle ⁇ and distance ⁇ have been selected from the following ranges: 90° ⁇ 150° and 300 ⁇ 1000 mm.
  • Possibility to install the maximum number of heat-exchange tubes in the steam generator while ensuring serviceability, reliability and heat transfer efficiency depends on selection of the S distance between the centerlines of the primary circuit coolant headers in the transverse direction of the steam generator pressure vessel from the above empirical relation.
  • the reactor plant layout in the reactor building depends on selection of the L v length as four large steam generators are difficult to install within the limited containment space.
  • steam generator pressure vessel length L v selected according to the claimed invention guarantees ease of manufacturing of U-shaped tubes of the heat-exchange bundle making up the heat-exchange surface of the steam generator, which is essential for reactor plant integrity ad reliable operation.
  • the steam generator heat-exchange tubes bundle is filled with heat-exchange tubes from bottom upwards continuously with vertical gaps between adjacent tubes not exceeding the vertical spacing of tubes in the bundle.
  • the bundle is divided into banks by means of intertubular tunnels.
  • the vertical intertubular tunnel width is between 100 mm and 250 mm.
  • Horizontal heat-exchange tubes are inserted in holes in vertical headers of the primary circuit coolant.
  • the heat-exchange tube bend shall have a radius of at least 60 mm and, preferably, at least 100 mm.
  • its drilling area on the outer surface shall exceed the area of holes drilled in it for heat-exchange tube connection by at least 20%.
  • the steam generator may include at least the following internals: a feed water supply and distribution device located above the heat-exchange tube bundle, an emergency feed water supply and distribution device located in the steam space, device for chemical reagent supply during steam generator flushing, a submerged perforated sheet and an overhead perforated sheet.
  • the second object of the claimed invention is a reactor plant with a water-cooled water-moderated power reactor and a horizontal seam generator, including a nuclear reactor with four circulation loops, each comprising a steam generator with a horizontal bundle of heat-exchange tubes divided into banks by means of intertubular tunnels and connected to primary circuit coolant headers inside a cylindrical pressure vessel with elliptical bottoms, a reactor coolant pump, and a primary circuit coolant main circulation pipeline, wherein pressure vessel bore D vess , distance S between the centerlines of the primary circuit coolant headers in the transverse direction and steam generator length L v along the inner surfaces of the elliptical bottoms have been respectively selected based on the following ratios:
  • D is the rated steam generator capacity, t/h
  • N tb is the number of steam generator vessel heat-exchange tubes, pcs.
  • Sv, Sh is the spacing between heat-exchange tubes in vertical and horizontal rows of heat-exchange bundle, respectively, mm,
  • H is the steam generator vessel tube filling height, mm
  • D head is the primary circuit header outer diameter in the drilled area, mm,
  • ⁇ is the heat-exchange tube central bend angle, deg.,
  • B 1 is the width of the heat-exchange tube central tunnel, mm,
  • B 2 is the width of the heat-exchange tube tunnel opposite to the coolant header, mm,
  • D head is the heat-exchange tube circumferential spacing on the outer surface of the coolant header, mm,
  • H hes is the steam generator heat-exchange surface area, m 2 ,
  • d is the outer heat-exchange tube diameter, mm
  • ⁇ is the distance from the outer heat-exchange bundle tube to the steam generator bottom inner surface along the longitudinal steam generator axis, wherein heat-exchange tube bend angle ⁇ and distance ⁇ have been selected from the following ranges:
  • the steam generator and reactor coolant pump may be attached to the reactor building walls by means of hydraulic snubbers.
  • the reactor coolant pump may be installed downstream the steam generator along the primary circuit coolant flow in the circulation loop.
  • reactor coolant pumps may be installed in each loop. That is, a reactor coolant pump may be installed on both the hot and cold legs of the main circulation pipeline in a circulation loop. Reliability is increased by means of possibility of pump redundancy.
  • two reactor coolant pumps of lower capacity may be installed in parallel on the cold leg of the main circulation pipeline. This will allow to reduce the pump dimensions, increasing the reliability margin and improving reactor plant technical and economic performance.
  • provision may be made for gate valves on the main circulation pipeline legs of the reactor plant. This would allow to enhance the operation reliability of the reactor plant making it possible to isolate the steam generator from the reactor and perform repairs without shutting down the reactor plant.
  • FIG. 1 shows a horizontal section of the containment with a reactor plant installed in it.
  • FIG. 2 shows a horizontal section of the steam generator pressure vessel.
  • FIG. 3 shows a horizontal section detail of the steam generator pressure vessel at the point of heat-exchange tube connection to the primary circuit coolant header.
  • FIG. 4 shows a cross-section of the steam generator along the centerline of the primary circuit coolant inlet header.
  • FIG. 5 shows the heat-exchange tube staggered arrangement.
  • FIG. 6 shows the heat-exchange tube in-line arrangement.
  • FIG. 7 shows a reactor plant (RP) primary circuit coolant circulation loop with a reactor coolant pump (RCP) installed on the cold leg of the main circulation pipeline (MCP).
  • RP reactor plant
  • RCP reactor coolant pump
  • FIG. 8 shows an RP primary circuit coolant circulation loop with an RCP installed on the MCP cold leg and hot leg.
  • FIG. 9 shows an RP primary circuit coolant circulation loop with two RCPs installed on the MCP cold leg.
  • FIG. 10 shows an RP primary circuit coolant circulation loop with gate valves installed on the MCP cold leg and hot leg.
  • the reactor plant equipment including steam generators, and its safety systems shall be installed in the NPP reactor compartment.
  • the reactor compartment consists of a pressurized part and unpressurized part.
  • the primary circuit equipment and the reactor are typically installed in the pressurized part.
  • FIG. 1 shows a horizontal section of containment 1 with a reactor plant installed in it.
  • the containment is designed as a cylinder of prestressed reinforced concrete, its thickness, for instance, for the VVER-1000 project, is 1.2 m, its inner diameter is 45 m and height is 52 m.
  • a reactor 2 connected to steam generators 4 by means of a main circulation pipeline (MCP) 3 is located in the central part of the containment 1 .
  • Reactor coolant pumps (RCP) 5 are used to pump the primary circuit coolant (pressurized water) from the steam generators 4 to the reactor 2 and back through the MCP.
  • pressurizers 6 are additionally applied in the reactor plant.
  • the steam generators 4 occupy a larger area than any other reactor plant equipment in the containment.
  • society development requires increased power generation and increased reactor plant power from NPPs and, therefore, increased an heat-exchange surface and dimensions of steam generators, which can hardly be fit in reactor building boxes already at this moment. Further increase of the area and size of containments is uneconomical due to significant increase of the scope and costs of NPP capital construction.
  • the claimed invention allows to increase heat transfer intensity, reliably and durability of a steam generator by increasing the number of heat-exchange tubes in its pressure vessel, which allows to improve performance of the reactor plant without any considerable increase in dimensions, making it possible to fit steam generators in containment boxes of the specified size.
  • the claimed horizontal steam generator 4 for a reactor plant with a VVER reactor comprises a cylindrical vessel 7 equipped with at least a feed water supply connection pipe 8 and a steam removal connection pipe 9 , two elliptical bottoms 10 , internals, an inlet header 11 and an outlet header 12 of the primary circuit coolant connected to a heat-exchange tube bundle 13 making up a heat-exchange surface of the steam generator, wherein the heat-exchange tube bundle is divided into banks 14 and 15 by means of intertubular tunnels 16 .
  • distance S FIG. 2
  • distance S between the centerlines of the headers 11 and 12 of the primary circuit coolant in the transverse direction of the steam generator pressure vessel 7 has been selected based on the following ratio:
  • D vess is the steam generator pressure vessel inner diameter
  • steam generator length L v measured along the inner surfaces of the elliptical bottoms has been selected based on the following ratio:
  • L ⁇ D head + 2 ⁇ [ ( ctg ⁇ ( ⁇ 2 ) - 1 sin ⁇ ( ⁇ 2 ) ) ⁇ ( B 1 2 + B 2 + ( ⁇ ⁇ D head 4 ⁇ S head - 1 ) ⁇ S h ) + ( ⁇ ⁇ D head 4 ⁇ S head - 1 ) ⁇ S h ⁇ 1 sin ⁇ ( ⁇ 2 ) + ⁇ ] + H hes ⁇ 10 6 ⁇ ⁇ d ⁇ N tb ,
  • D head is the coolant header outer diameter in the drilled part, mm
  • ⁇ is the heat-exchange tube central bend angle, deg.,
  • B 1 is the width of the heat-exchange tube central intertubular tunnel, mm,
  • B 2 is the width of the heat-exchange tube intertubular tunnel opposite to the coolant header, mm,
  • S head is the heat-exchange tube circumferential spacing on the outer surface of the coolant header, mm.
  • the above spacing is measured as a distance from the center of one heat-exchange tube to the center of its adjacent heat-exchange tube in a horizontal row on the outer surface of the coolant header.
  • Sh is the spacing between heat-exchange tubes in the horizontal heat-exchange bundle row, mm.
  • the above spacing is measured as a distance from the center of one heat-exchange tube to the center of its adjacent heat-exchange tube in a horizontal row on the outer surface of the coolant header as is shown in FIGS. 5 and 6 .
  • H hes is the steam generator heat-exchange surface area, m 2 .
  • the steam generator heat-exchange surface area is measured as a sum total of surface areas of the heat-exchange bundle tubes.
  • N tb is the number of steam generator heat-exchange tubes, pcs.
  • d is the outer heat-exchange tube diameter, mm.
  • ⁇ is the distance from the outer heat-exchange bundle tube 17 to the steam generator bottom 10 inner surface along the longitudinal steam generator axis, in mm, wherein central heat-exchange tube bend angle ⁇ and distance 4 have been selected from the following ranges: 90° ⁇ 150° and 300 ⁇ 1000 mm.
  • the steam generator heat-exchange tubes bundle 13 is filled with heat-exchange tubes from bottom upwards continuously with vertical gaps b between adjacent tubes not exceeding the vertical spacing of tubes in the bundle, as is shown in FIGS. 5 and 6 .
  • Horizontal heat-exchange tubes are inserted in holes in vertical headers 11 and 12 of the primary circuit coolant.
  • the heat-exchange tube bend shall have radius Rh of at least 60 mm and, preferably, at least 100 mm.
  • the steam generator may include at least the following internals: a feed water supply and distribution device 18 located above the heat-exchange tube bundle 13 , an emergency feed water supply and distribution device 19 located in the steam space, device 20 for chemical reagent supply during steam generator flushing, a submerged perforated sheet 21 and an overhead perforated sheet 22 .
  • the primary circuit coolant is supplied from the reactor 2 to the steam generator inlet header 11 , distributed among the heat-exchange bundle 13 tubes and flows through the same to the outlet header 12 transferring its heat to the boiler water, i.e. the secondary circuit coolant (medium) through the heat-exchange surface wall.
  • Feed water is supplied to the steam generator through the connection pipe 8 and the feed water supply and distribution device 18 connected to the same, making up the boiler water in the steam generator, and is heated up by mixing with the steam-water mixture in it. Water heated up to saturation is drawn into the steam generator circulation circuit (secondary circuit).
  • the secondary circuit coolant boils on the steam generator heat-exchange surface and moves up the circulation circuit riser sections.
  • a single-stage gravitation settling separation is applied to separate water from steam in the steam generator. Steam is removed from the steam generator through steam tubes 9 in the upper part of the vessel 7 .
  • the empirical formula ratio proposed for calculation of the steam generator length Lv is based on the process requirements for the heat-exchange surface tube bend near the steam generator bottoms.
  • the heat-exchange bundle tubes shall be U-shaped in three bends.
  • the angle of the central bend is between 90° and 150°, and the distance between the heat-exchange bundle outer tube and the inner bottom surface between 300 mm and 1000 mm, which is essential in terms of the process and technical and economic considerations.
  • the preferable heat-exchange tube central bend angle is 120°.
  • a steam generator may be assembled with a distance between the headers in the transverse direction outside the specified range, but the number of tubes in such steam generator will be less than required for its efficient operation due to the fact that the inner space of the vessel is not effectively used. Namely, if distance S between the centerlines of the coolant headers in the transverse direction is S ⁇ 0.4 ⁇ D vess , a considerable space in the central part of the steam generator adjacent to the longitudinal section plane in the heat-exchange bundle area will remain unfilled with heat-exchange tubes due to the reason described below.
  • To insert heat-exchange tubes in the coolant header holes they shall have specified bend radius Rh ( FIG. 3 ), and the length of a straight section at the end shall exceed the depth of a hole in the header wall the tube is inserted in.
  • heat-exchange tube bend radii shall be at least 60 mm, and preferably at least 100 mm to be inserted in the header holes.
  • the reactor plant comprising the claimed steam generator is shown in FIG. 1 . It comprises a nuclear reactor 2 with four circulation loops, each comprising a steam generator 4 with a horizontal bundle 13 of heat-exchange tubes divided into banks 14 and 15 by intertubular tunnels 16 and connected to primary circuit coolant headers 11 and 12 inside a cylindrical vessel 7 with elliptical bottoms 10 , a reactor coolant pump 5 , and a main circulation pipeline 3 of the primary circuit coolant, wherein vessel 7 inner diameter D vess , distance S between the centerlines of the primary circuit coolant headers 11 and 12 in the transverse direction, and steam generator length Lv along the inner surfaces of the elliptical bottoms 10 are selected, respectively, by the following ratios:
  • D is the rated steam generator capacity, t/h
  • N tb is the number of steam generator vessel heat-exchange tubes, pcs.
  • Sv, Sh is the spacing between heat-exchange tubes in vertical and horizontal rows of heat-exchange bundle, respectively, mm, as is shown in FIGS. 5 and 6 ,
  • H is the steam generator vessel tube filling height, mm, as is shown in FIG. 4 ,
  • D head is the primary circuit header outer diameter in the drilled area, mm,
  • ⁇ is the heat-exchange tube central bend angle, deg.,
  • B 1 is the width of the heat-exchange tube central tunnel, mm,
  • B 2 is the width of the heat-exchange tube tunnel opposite to the coolant header, mm,
  • S head is the heat-exchange tube circumferential spacing on the outer surface of the coolant header, mm,
  • H hes is the steam generator heat-exchange surface area, m 2 ,
  • d is the outer heat-exchange tube diameter, mm
  • ⁇ is the distance from the outer heat-exchange bundle tube to the steam generator bottom inner surface along the longitudinal steam generator axis, wherein heat-exchange tube bend angle ⁇ and distance ⁇ have been selected from the following ranges:
  • the steam generator and reactor coolant pump may be attached to the reactor building walls by means of hydraulic snubbers 24 .
  • FIGS. 7-9 show arrangement options of the proposed reactor plant as exemplified by one of the four circulation loops, with the MCP cold leg designated as item 25 and the hot leg as 26 .
  • the reactor plant 2 coolant pump 5 may be installed downstream the steam generator 4 along the primary circuit coolant flow in the circulation loop on the MCP 3 cold leg 25 .
  • reactor coolant pumps 5 may be installed in each circulation loop. That is, a reactor coolant pump 5 may be installed on both the hot leg 26 and cold leg 25 of the main circulation pipeline in a circulation loop. Reliability is increased by means of possibility of pump redundancy.
  • two reactor coolant pumps 5 of lower capacity may be installed in parallel on the cold leg 25 of the main circulation pipeline as shown in FIG. 9 . This will allow to reduce the pump dimensions, increasing the reliability margin and improving reactor plant technical and economic performance.
  • gate valves 27 on the main circulation pipeline legs 25 and 26 of the reactor plant as shown in FIG. 10 . This would allow to enhance the operation reliability of the reactor plant making it possible to isolate the steam generator from the reactor and perform repairs without shutting down the reactor plant.
  • the reactor plant functions as follows.
  • the process flow diagram of the reactor plant is double-circuit.
  • the primary circuit is radioactive and located in a containment 1 , comprising a VVER water-cooled water-moderated power reactor 2 and four circulation loops of the MCP 3 , through which the primary circuit coolant, pressurized water (160 kgf/cm 2 ), is pumped to a reactor core 2 by means of reactor coolant pumps 5 .
  • Water temperature at the reactor inlet is approximately 289° C., and 322° C. at the outlet.
  • the water heated in the reactor 2 is supplied to steam generators 4 through four MCP pipelines 3 .
  • a steam pressurizer 6 maintains the pressure and level of the primary circuit coolant.
  • the secondary circuit is non-radioactive, consists of an evaporator and a feed water plant, a unit demineralization plant and a turbine generator (not shown).
  • the primary circuit coolant is cooled down in the steam generators 4 transferring heat to the secondary circuit water.
  • the saturated steam produced in the steam generators 4 is supplied to the turbine generator rotating the power generator by steam removal connection pipes 9 and the steam header.
  • a steam generator with the following parameters has been manufactured for the reactor plant:
  • steam generator pressure vessel inner diameter D vess is selected from the range based on the following ratio:
  • Distance S between the centerlines of the coolant headers in the transverse direction is selected from a range based on the following ratio:
  • Steam generator length Lv (along the inner surfaces of the elliptical bottoms) is selected from a range based on the following ratio:
  • L ⁇ D head + 2 ⁇ [ ( ctg ⁇ ( ⁇ 2 ) - 1 sin ⁇ ( ⁇ 2 ) ) ⁇ ( B 1 2 + B 2 + ( ⁇ ⁇ D head 4 ⁇ S head - 1 ) ⁇ S h ) + ( ⁇ ⁇ D head 4 ⁇ S head - 1 ) ⁇ S h ⁇ 1 sin ⁇ ( ⁇ 2 ) + ⁇ ] + H hes ⁇ 10 6 ⁇ ⁇ d ⁇ N tb ,
  • steam generator pressure vessel inner diameter D vess is less than 2825 mm, then it will not be possible to securely mount heat-exchange tubes in such seam generator by means of spacing elements, therefore, there will be no space left for the same, and thus the steam generator design reliability requirement will not be met.
  • a steam generator pressure vessel with an inner diameter exceeding 4202 mm is uneconomical to install in a reactor plant as it increases its specific amount of metal per structure, while the water content of the steam generated and plant efficiency are not improved, but the containment size is increased.
  • the steam generator contains the same heat-exchange surface, therefore, the coolant remains within the same temperature range in the reactor plant MCP. As a result, the critical heat flux ratio does not increase in the core.
  • Steam generator length Lv (along the inner surfaces of the elliptical bottoms) of less than 13,790 mm does not provide the best performance of bending and fastening of U-shaped tubes in a bundle as the tube bending angle exceeds 150°, and the distance between the outer tubes of the bundle and the vessel bottom is less than 300 mm, which prevents installation of a bundle support.
  • the central part of the heat-exchange bundle of the steam generator will not be filled with tubes.
  • its end shall have a straight section with a length exceeding the depth of such hole. If the condition is not fulfilled, then such heat-exchange tube cannot be placed and fastened in the coolant header side wall hole. Therefore, if the central part of the steam generator heat-exchange bundle is not filled with tubes, it will not allow to provide the specified number of heat-exchange tubes in the steam generator or the specified dimensions of the heat-exchange surface, which will compromise the performance indicators of the reactor plant.
US15/535,360 2014-12-12 2015-12-09 Horizontal Steam Generator for a Reactor Plant with a Water-Cooled Water-Moderated Power Reactor and a Reactor Plant with the said Steam Generator Abandoned US20170321879A1 (en)

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RU2014150427/06A RU2583324C1 (ru) 2014-12-12 2014-12-12 Горизонтальный парогенератор для реакторной установки с водо-водяным энергетическим реактором и реакторная установка с указанным парогенератором
RU2014150427 2014-12-12
PCT/RU2015/000785 WO2016093736A2 (ru) 2014-12-12 2015-12-09 Горизонтальный парогенератор для реакторной установки с водо-водяным энергетическим реактором и реакторная установка с указанным парогенератором

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RU2583324C1 (ru) * 2014-12-12 2016-05-10 Открытое акционерное общество "Ордена Трудового Красного Знамени и ордена труда ЧССР опытное конструкторское бюро "ГИДРОПРЕСС" (ОАО ОКБ "ГИДРОПРЕСС") Горизонтальный парогенератор для реакторной установки с водо-водяным энергетическим реактором и реакторная установка с указанным парогенератором
CN106340328B (zh) * 2016-09-09 2022-05-20 中国核工业二三建设有限公司 核电站压力容器筒体和蒸汽发生器的找正、调平方法
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