US3882933A - Heat exchanger - Google Patents

Heat exchanger Download PDF

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Publication number
US3882933A
US3882933A US193371A US19337171A US3882933A US 3882933 A US3882933 A US 3882933A US 193371 A US193371 A US 193371A US 19337171 A US19337171 A US 19337171A US 3882933 A US3882933 A US 3882933A
Authority
US
United States
Prior art keywords
tubes
tube
heat exchanger
tube bundle
row
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.)
Expired - Lifetime
Application number
US193371A
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English (en)
Inventor
Leonard J Kube
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.)
General Atomics Corp
Original Assignee
General Atomics Corp
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 General Atomics Corp filed Critical General Atomics Corp
Priority to US193371A priority Critical patent/US3882933A/en
Priority to GB4664972A priority patent/GB1358336A/en
Priority to CA153,561A priority patent/CA973167A/en
Priority to DE2249811A priority patent/DE2249811A1/de
Priority to IT53431/72A priority patent/IT966382B/it
Priority to CH1555972A priority patent/CH557003A/xx
Priority to ES408014A priority patent/ES408014A1/es
Priority to FR7238139A priority patent/FR2165862A1/fr
Priority to JP47108380A priority patent/JPS4851102A/ja
Application granted granted Critical
Publication of US3882933A publication Critical patent/US3882933A/en
Assigned to GA TECHNOLOGIES INC., A CA CORP. reassignment GA TECHNOLOGIES INC., A CA CORP. ASSIGNS ENTIRE INTEREST. SUBJECT TO REORGANIZATION AGREEMENT DATED JUNE 14, 1982 Assignors: GENERAL ATOMIC COMPANY
Assigned to GENERAL ATOMICS reassignment GENERAL ATOMICS CHANGE OF NAME (SEE DOCUMENT FOR DETAILS). EFFECTIVE DATE: FEBRUARY 1, 1988. Assignors: GA TECHNOLOGIES, INC.,
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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Classifications

    • 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
    • F22B1/1823—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 for gas-cooled nuclear reactors
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S165/00—Heat exchange
    • Y10S165/355—Heat exchange having separate flow passage for two distinct fluids
    • Y10S165/40—Shell enclosed conduit assembly
    • Y10S165/427—Manifold for tube-side fluid, i.e. parallel
    • Y10S165/436—Bent conduit assemblies
    • Y10S165/437—Coiled
    • Y10S165/438—Helical

Definitions

  • Ducts are provided for directing a flow of UNITED STATES PATENTS heated fluid over the tubes, and the ends of respective 2,888,251 5/1959 Dalin 165 163 x Pairs ofthefubes are conneFted end Ofthe tube 3,071,119 1/1963 Ammon et al. 122/34 bundle Fluld be heated pp t0 the tubes and 3,130,779 4/1964 Huet 165 163 x received r th tubes at the opposite end of the 3,298,358 1/1967 Alden Jr. 122/34 tube bundle from the end at which the pairs of tubes 3,338,301 8/1967 Romanos-.. are connected. 3,379,244 4/1968 3,438,357 4/1969 4 Claims, 4 Drawing Figures PATENTEQ MAY 1 3W5 SHEET 10? 3 INVENTOR.
  • This invention relates to vapor generators such as are used in connection with the production of steam for driving steam turbines. More particularly, the invention relates to a steam generator which is especially suited for use with a gas cooled nuclear reactor in an electrical power generating facility.
  • nuclear power plants employing high temperature gas cooled reactors enclose the reactor in a pressure vessel through which a fluid coolant, such as gaseous helium or carbon dioxide, is circulated to withdraw thermal energy liberated by the reactor.
  • a fluid coolant such as gaseous helium or carbon dioxide
  • Steam for the operation of the turbines is normally obtained by the transfer of heat from the coolant to the fluid of a water/steam system.
  • heat transfer is accomplished in a steam generator wherein the thermal energy withdrawn from the reactor is utilized to produce superheated steam.
  • Another object of the invention is to provide a vapor generator in which tube bundle size within the vapor generator is maximized for a given available space.
  • FIG. 1 is a perspective cut-away view of a portion of a nuclear reactor incorporating the vapor generator of the invention
  • FIG. 2 is a schematic full section view of the lower portion of the vapor generator of FIG. 1;
  • FIG. 3 is a sectional view taken along the line 3-3 of FIG. 2;
  • FIG. 4 is a schematic view illustrating an alternative embodiment of the invention.
  • the heat exchanger of the invention comprises at least one tube bundle 1 1 having a plurality of heat exchanger tubes 13.
  • the tubes 13 are arranged in a plurality of coaxial annular rows 15, each row comprising a plurality of the tubes with the tubes in each row being wound helically at a common radius with respect to the axis of the annular rows.
  • Duct means 17 and 19 are provided for directing a flow of heated first fluid over the tubes for heating a second fluid in the tubes.
  • Means 21 connect the ends of respective pairs of the tubes at one end of the tube bundle.
  • means 23 supply the second fluid under pressure to one tube in each of the tube pairs and means 25 receive the .second fluid from the other tube in each of the tube pairs.
  • the nuclear reactor system includes a prestressed concrete pressure vessel 27, suitably supported by means not illustrated, within an appurtenant structure, also not illustrated.
  • Prestressing tendons 29 extend axially through the concrete of the pressure vessel 27, which is generally cylindrical in form, and a plurality of annular grooves 31 are formed in the outer surface of the pressure vessel for accommodating circumferential prestressing bands, not illustrated.
  • the interior of the pressure vessel 27 includes a main chamber 33 in which a reactor core, not illustrated, is supported.
  • the chamber 33 is provided with a liner 35 of suitable metal anchored to the concrete.
  • the core of the reactor may be of any suitable type, but the illustrated reactor system is of the so-called gas-cooled type. Provision is made for circulating a coolant gas, such as helium or carbon dioxide, over the reactor core, not shown, to raise the temperature of the gas. The gas is then circulated over one or more heat exchangers or vapor generators to produce steam or other vapor for operating machinery to generate electricity. Circulating gas is then returned to the core to be heated once again.
  • a coolant gas such as helium or carbon dioxide
  • the main chamber 33 is surrounded by a plurality of circumferentially spaced cylindrical chambers 37, only one of which is illustrated in the drawings.
  • the chambers 37 are cylindrical in shape and extend vertically within the reactor vessel, having their' axes parallel with the axis of the reactor vessel.
  • a vapor generator and a coolant circulator are disposed in each of the chambers 37.
  • the vapor generator in the drawings is shown generally at 39, and a portion of the coolant circulator is shown generally at 41.
  • Coolant gas is conducted from the main chamber 33 to each of the chambers 37 through horizontal ducts 43, one of which is illustrated in the drawings.
  • the coolant is returned to the chamber 33 for recirculation over the reactor core through a horizontal duct 45.
  • Suitable closures, not shown, are provided at the upper ends of the chambers 33 and 37.
  • the chamber 37 is accessible from the lower end of the pressure vessel 27 through penetrations 47.
  • Each penetration 47 is provided with a metal liner 49 which extends upward and is welded to a metal liner 51 for the chamber 37.
  • Each penetration 47 is closed and sealed by a concrete plug 53 having an outer metal cladding 55. Suitable penetrations are provided in the plug 53 for entry of the various steam pipes, explained below, into the chamber 37 for conducting water and steam to and from the vapor generator 39.
  • feed water for the vapor generator 39 is conducted from a feed water inlet pipe 57 to a feed water header 59.
  • the feed water is divided among a plurality of feed water inlet tubes 61, passing through a penetration in the plug 53 into the chamber 37.
  • the tubes 61 are then routed along the space between the double walled vapor generator duct means 17 to the region just above the duct 43.
  • Each of the tubes 61 becomes a helical coil to form a main steam bundle 63.
  • the tubes 61 are sub-headered by appropriate means, not shown, and tube lead-outs 65 from the subheaders and are passed down through a central tube 67 extending axially the full length of the vapor generator 39.
  • the tubes 65 are routed over to a suitable penetration in the lower access plug 53 to be passed therethrough out of the pressure vessel to a header 69. Steam entering the header 69 from the tubes 65 is then collected in the steam outlet pipe 71 and conducted to the turbines, not shown.
  • the tube bundle 63 constitutes an evaporator-economizer and a superheater, and therefore the steam emerging through the steam pipe 71 is superheated steam.
  • the invention is incorporated in only the reheater section, explained below. Accordingly, further structural details of the main evaporator-economizer and superheater section of the vapor generator will not be given.
  • the main steam bundle 63 may be of any suitable mechanical construction.
  • the main steam bundle may be supported by perforated plates, not shown, through which the tubes comprising the main steam bundle are coiled. These plates may be attached to any suitable portion of the vapor generator to provide support for the plates.
  • the tube bundle 11 in the illustrated embodiment comprises the reheater section of the vapor generator 39.
  • the tube bundle is contained within a plenum defined by the duct means 17 and 19.
  • the duct means 17 comprises an outer double cylindrical wall having an annular support rim 73 at its upper end which is provided with an annular mounting nel 79.
  • the main bundle 63 is surrounded by a cylinder or shroud 81 supported by the mounting flange 85 on the mounting flange affixed to the liner 51 of the chamber 37.
  • Hot helium from the reactor core of the reactor system in the chamber 33 is passed through the duct 43 and into the plenum defined between the walls or cylinders 17 and 19.
  • the hot helium then passes downwardly over the reheater tube bundle 11.
  • the lower end of the cylinder 17 is provided with a floor 87, and the lower end of the cylinder 19 terminates a distance above the floor 87. Accordingly, hot helium or other coolant gas, after passing downwardly over the tube bundle 11, enters the annular space between the inner cylinder 67 and the cylinder 19. It then passes upwardly, parallel with the axis of the vapor generator to the region above the main tube bundle 63.
  • the upper end of the cylinder 81 is closed off by a series of annular wall segments 89.
  • the hot helium emerges from the annular plenum between the cylinder 67 and the cylinder 19 and is then forced outwardly and once again downwardly through the tube bundle 63 in the space defined by the cylinder 19 and the outer cylinder 81.
  • the lower edge of the cylinder 81 terminates a distance above the flange 85, with suitable legs 91 extending downwardly to the flange to support the cylinder.
  • the hot helium gas after passing over the tube bundle 63, is forced annularly outward through the space between the lower edge of the cylinder 81 and the flange to enter the space between the cylinder 81 and the liner 51 of the chamber 37. In this region, another 180 change in direction results in the gas flow, such that the gas passes vertically upward outside of the cylinder 81.
  • the gas moving to the region above the vapor generator 39 is collected in a plenum defined by a cup-shaped structure 93.
  • the helium circulator 41 communicates with the space defined by the cup-shaped structure 93 and includes turbine blades 95 which are driven by a suitably powered shaft 97 to force the coolant gas through an annular duct 99.
  • the gas leaves the duct 99 in a region, not illustrated, and enters into the upper portion of the chamber 37, the upper portion being indicated at 101.
  • the upper portion of the chamber 37 above the cup-shaped structure 93 communicates with the duct 45, and thus the circulating gas is forced back through the duct to be returned over the reactor core for reheating.
  • the means which supply and collect the reheat steam to and from the reheater tube bundle 11 are disposed below the tube bundle.
  • the supply means 23 comprise a header supplied by a cold reheat steam inlet pipe 103.
  • Cold reheat steam is divided among a plurality of feeder tubes which then pass through the penetration plug 53 into the region below the vapor generator 39.
  • the tubes 105 are routed over to a suitable location below the tube bundle 11.
  • reheat steam first circulates helically upward through tubes in the reheat bundle 11 and then is returned helically downward.
  • Transfer tubes 107 convey the reheat steam, after its downward helical return flow, from locations distributed about the region below the tube bundle 11, to the region above an access penetration through the plug 53.
  • the tubes 107 are then bent downwardly to pass out of the chamber 37 through the plug 53 and into the header or collection means 25.
  • the hot reheat steam entering the header is then conveyed through a reheat steam outlet pipe 109 to be expanded once more in the turbines, not shown.
  • the particular construction of the reheater tube bundle 11 may be more clearly seen in FIGS. 2 and 3.
  • the tube bundle itself is comprised of a plurality of annular coaxial rows of tubes, each row comprising a plurality of tubes.
  • the tubes are wound helically about a common axis with the same radius. This means that when the reheat steam inlet tubes 105 are bent over beneath the vapor generator 39, they each extend to a different position spaced circumferentially around the bottom of each of the various annular rows of tubes. The same is true of the reheat steam outlet tubes 107.
  • Half of the tubes 13 in the tube bundle 11 are used to convey reheat steam helically upward in the tube bundle, and half of the tubes 13 in the tube bundle 11 are used to convey reheat steam downwardly through a helical path in the tube bundle.
  • the inlet tubes 105 connect to half of the tubes 13, and the outlet tubes 107 connect to the other half of the tubes 13.
  • the up-flow helical tubes and the down-flow helical tubes are positioned in separate ones of the vertical rows 15.
  • the innermost row of helical tubes in the tube bundle comprises an up-flow set of tubes so that the steam passes helically upward in the tube bundle, and the next adjacent row comprises a down-flow set of tubes.
  • Each of the tubes in the innermost annular row is connected to a respective one of the tubes in the next adjacent annular row, at the top of the tube bundle, by a U-shaped tube segment 21.
  • each helical tube which carries steam upwardly in the tube bundle is connected through a U-shaped segment 21 to a helical tube which carries the steam helically downward in the tube bundle.
  • the pairs of tubes are not immediately adjacent each other, but are spaced circumferentially relative to each other a slight distance, as viewed in FIG. 3.
  • the tube bundle 11 By constructing the tube bundle 11 in the manner described, all lead-ins and lead-outs are at the same end of the bundle. This eliminates heat losses as a result of having to transfer vapor around the bundle from one end to the other. Also, the space which would ordinarily be used for such routing may be utilized by an additional row or rows of tubes, increasing the capacity of the tube bundle. Alternatively, the size of the space required for a given tube bundle size is reduced.
  • FIG. 4 an alternative embodiment of the invention is illustrated.
  • alternate tubes in each row conduct the steam upwardly and downwardly.
  • the U-shaped tube segments 21 thus do not cross over between rows as shown in FIG. 3, but rather cross around to connect to the next adjacent tube in the same row.
  • One advantage of the construction of FIG. 4 is that an even number of tube rows 15 is not required, but only an even number of tubes in each row is required. Moreover, somewhat less height is required to make the cross-over connection between up-flow and down-flow tubes than in the case of the embodiment of FIGS. 2 and 3.
  • Cross-over connection between tubes can be accomplished at the same time the particular row of tubes is being constructed, rather than after assembly of two adjacent rows. This reduces manufacturing costs. Because of the intermixing of upflow and down-flow tubes in each row, a more diffused temperature distribution results than is the case when all of the tubes in a given row are either up-flow or down-flow. Finally, the embodiment of FIG. 4 may offer a more desirable layout for combating flow induced vibrations and may result in less of a steam side pressure drop due to less flow resistance.
  • the invention provides an improved heat exchanger or vapor generator particularly suitable for use in producing steam in a gascooled nuclear reactor.
  • the heat exchanger of the invention comprises a tube bundle incorporating helical coils and in which all the lead-in and lead-out tubes may connect at the same end of the tube bundle.
  • the design makes it possible to utilize a larger bundle size for a given available space, and fewer heat transfer losses result.
  • the invention has been described in connection with the generation of water vapor, it may be applicable to other types of liquid-vapor systems as well.
  • a heat exchanger comprising a plurality of tube bundles, at least one tube bundle comprising a reheater having a plurality of helical heat exchanger tubes, said tubes being arranged in a plurality of coaxial annular rows along a vertical axis with each tube being in a single row, each row comprising a plurality of said tubes with said tubes in each row being wound helically with respect to the axis of said annular rows.
  • duct means for directing a flow of a heated first fluid downwardly over said tubes along the axis of the helix toward the lower end of said tube bundle and then upwardly through the space defined by the inner one of said annular rows, means at the upper end of said tube bundle interconnecting the ends of respective pairs of said tubes, said interconnected ends being uniformly spaced circumferentially around the top of said annular rows, a first tube sheet and a plurality of interconnecting tubes extending from said first tube sheet, each to one tube in a respective one of said tube pairs, and a second tube sheet and a plurality of connecting tubes extending from said second tube sheet, each to the other tube in the respective ones of said tube pairs, said connecting tubes intersecting the respective tubes to which they extend at different positions uniformly spaced circumferentially around the bottom of said annular rows.

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  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Combustion & Propulsion (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Physics & Mathematics (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • General Engineering & Computer Science (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
US193371A 1971-10-28 1971-10-28 Heat exchanger Expired - Lifetime US3882933A (en)

Priority Applications (9)

Application Number Priority Date Filing Date Title
US193371A US3882933A (en) 1971-10-28 1971-10-28 Heat exchanger
GB4664972A GB1358336A (en) 1971-10-28 1972-10-10 Heat exchanger
CA153,561A CA973167A (en) 1971-10-28 1972-10-10 Heat exchanger
DE2249811A DE2249811A1 (de) 1971-10-28 1972-10-11 Waermeaustauscher
IT53431/72A IT966382B (it) 1971-10-28 1972-10-17 Perfezionamento nei generatori di vapore
CH1555972A CH557003A (de) 1971-10-28 1972-10-25 Dampferzeuger mit einem zwischenueberhitzer.
ES408014A ES408014A1 (es) 1971-10-28 1972-10-26 Un dispositivo intercambiador de calor.
FR7238139A FR2165862A1 (enrdf_load_stackoverflow) 1971-10-28 1972-10-27
JP47108380A JPS4851102A (enrdf_load_stackoverflow) 1971-10-28 1972-10-28

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US193371A US3882933A (en) 1971-10-28 1971-10-28 Heat exchanger

Publications (1)

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US3882933A true US3882933A (en) 1975-05-13

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US193371A Expired - Lifetime US3882933A (en) 1971-10-28 1971-10-28 Heat exchanger

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Country Link
US (1) US3882933A (enrdf_load_stackoverflow)
JP (1) JPS4851102A (enrdf_load_stackoverflow)
CA (1) CA973167A (enrdf_load_stackoverflow)
CH (1) CH557003A (enrdf_load_stackoverflow)
DE (1) DE2249811A1 (enrdf_load_stackoverflow)
ES (1) ES408014A1 (enrdf_load_stackoverflow)
FR (1) FR2165862A1 (enrdf_load_stackoverflow)
GB (1) GB1358336A (enrdf_load_stackoverflow)
IT (1) IT966382B (enrdf_load_stackoverflow)

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4047506A (en) * 1974-12-06 1977-09-13 Sulzer Brothers Limited Gas heated steam generator
US4098329A (en) * 1976-07-29 1978-07-04 The United States Of America As Represented By The United States Department Of Energy Modular heat exchanger
US4182413A (en) * 1976-12-23 1980-01-08 General Atomic Company Radial flow heat exchanger
US4284134A (en) * 1978-09-05 1981-08-18 General Atomic Company Helically coiled tube heat exchanger
US4905757A (en) * 1987-11-06 1990-03-06 General Electric Company Compact intermediate heat transport system for sodium cooled reactor
WO2019133080A1 (en) * 2017-12-28 2019-07-04 Ge-Hitachi Nuclear Energy Americas Llc Systems and methods for steam reheat in power plants

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4005681A (en) * 1975-07-23 1977-02-01 General Atomic Company Vapor generator
FR2326657A1 (fr) * 1975-10-03 1977-04-29 Gen Atomic Co Chaudiere a vapeur avec faisceaux haute et basse temperature a tubes respectivement droits et en spirale
US4303475A (en) * 1978-12-11 1981-12-01 General Atomic Company Nuclear reactor system with aligned feedwater and superheater penetrations

Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2888251A (en) * 1956-10-10 1959-05-26 Dalin Nils Algot Apparatus for effecting heat exchange between two fluid media
US3071119A (en) * 1956-02-23 1963-01-01 Babcock & Wilcox Co Vapor generating unit
US3130779A (en) * 1958-05-05 1964-04-28 Huet Andre Light boiler for nuclear energy installation
US3298358A (en) * 1964-12-30 1967-01-17 Combustion Eng Vertical steam generator with a central downcomer
US3338301A (en) * 1965-05-24 1967-08-29 Combustion Eng Once-through steam generator having a pair of tube bundles of spiral tube construction
US3379244A (en) * 1964-04-06 1968-04-23 Waagner Biro Ag Heat exchanger
US3438357A (en) * 1965-02-16 1969-04-15 Sulzer Ag Apparatus and method for cooling a recirculating coolant medium

Patent Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3071119A (en) * 1956-02-23 1963-01-01 Babcock & Wilcox Co Vapor generating unit
US2888251A (en) * 1956-10-10 1959-05-26 Dalin Nils Algot Apparatus for effecting heat exchange between two fluid media
US3130779A (en) * 1958-05-05 1964-04-28 Huet Andre Light boiler for nuclear energy installation
US3379244A (en) * 1964-04-06 1968-04-23 Waagner Biro Ag Heat exchanger
US3298358A (en) * 1964-12-30 1967-01-17 Combustion Eng Vertical steam generator with a central downcomer
US3438357A (en) * 1965-02-16 1969-04-15 Sulzer Ag Apparatus and method for cooling a recirculating coolant medium
US3338301A (en) * 1965-05-24 1967-08-29 Combustion Eng Once-through steam generator having a pair of tube bundles of spiral tube construction

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4047506A (en) * 1974-12-06 1977-09-13 Sulzer Brothers Limited Gas heated steam generator
US4098329A (en) * 1976-07-29 1978-07-04 The United States Of America As Represented By The United States Department Of Energy Modular heat exchanger
US4182413A (en) * 1976-12-23 1980-01-08 General Atomic Company Radial flow heat exchanger
US4284134A (en) * 1978-09-05 1981-08-18 General Atomic Company Helically coiled tube heat exchanger
US4905757A (en) * 1987-11-06 1990-03-06 General Electric Company Compact intermediate heat transport system for sodium cooled reactor
WO2019133080A1 (en) * 2017-12-28 2019-07-04 Ge-Hitachi Nuclear Energy Americas Llc Systems and methods for steam reheat in power plants
US11525374B2 (en) * 2017-12-28 2022-12-13 Ge-Hitachi Nuclear Energy Americas Llc Systems and methods for steam reheat in power plants
US20230096162A1 (en) * 2017-12-28 2023-03-30 Ge-Hitachi Nuclear Energy Americas Llc Systems and methods for steam reheat in power plants
US11828204B2 (en) * 2017-12-28 2023-11-28 Ge-Hitachi Nuclear Energy Americas Llc Systems and methods for steam reheat in power plants

Also Published As

Publication number Publication date
ES408014A1 (es) 1975-11-01
CH557003A (de) 1974-12-13
GB1358336A (en) 1974-07-03
DE2249811A1 (de) 1973-05-03
FR2165862A1 (enrdf_load_stackoverflow) 1973-08-10
JPS4851102A (enrdf_load_stackoverflow) 1973-07-18
CA973167A (en) 1975-08-19
IT966382B (it) 1974-02-11

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