US3662718A - Sodium heated steam generator - Google Patents

Sodium heated steam generator Download PDF

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Publication number
US3662718A
US3662718A US120151A US3662718DA US3662718A US 3662718 A US3662718 A US 3662718A US 120151 A US120151 A US 120151A US 3662718D A US3662718D A US 3662718DA US 3662718 A US3662718 A US 3662718A
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United States
Prior art keywords
steam
tube sheet
pressure region
liquid metal
vessel
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
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US120151A
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English (en)
Inventor
Ronald B Creek
Karl A Gardner
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US Atomic Energy Commission (AEC)
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US Atomic Energy Commission (AEC)
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Publication of US3662718A publication Critical patent/US3662718A/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
    • F22B1/06—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

  • liquid metal having been heated as the result of the fission process within the reactor, may be employed within a heat exchanger to generate steam.
  • the present invention provides for a liquid metal heated steam generator in which the various aforementioned difficulties are effectively overcome with greater reliability, efficiency, and economy.
  • the steam, generator is divided into a high pressure steam/water side and a low pressure liquid metal side divided by a tube sheet which is maintained at saturated steam temperature for normal full load operating conditions.
  • the entire high pressure steam/water inlet-outlet plenum is likewise maintained at saturated steam temperatures.
  • This isothermal structure is obtained by a so-called split bundle bayonet tubing which provides appropriate flow routes for the sodium, water and steam. Hence, the tube sheet is not exposed to high inlet temperature sodium and exit steam.
  • Another important feature of the heat exchanger of this invention is that it can operate both as a once-through or a recirculating unit.
  • steam generator consists of an elongated cylindrical vessel 12 having a lower section 14 with a hemispherical bottom 15, an intermediate section 16, and an 'upper hemispherical closure section 18.
  • Intermediate section 16 carries high pressure tube sheet 22 which divides vessel 12 into a high pressure region above sheet 22 and a low pressure region below.
  • Section 16 has steam outlet nozzle 23 above tube sheet 22 for a purpose to be later described.
  • Lower section 14 is provided with a bottom inlet nozzle 24 for liquid metal and a side liquid metal outlet nozzle 26 located adjacent to the lower end of section 14.
  • Intermediate section 16 has a sodium-water reaction product vent nozzle 28 below tube sheet 22 but above the level of liquid metal 32.
  • Tube supports 43a 43h provide suitable spacing elements for the tubes making up bundle 34 the details of which are not a part of this invention.
  • Bafile 42 is connected at the bottom to the sodium inlet nozzle and separates the upward flow of liquid metal from the downward flow shown by arrows A.
  • Baffle 42 terminates'at the upper end at 44 and is supported from tube sheet 22 by a plurality of support bars 45. It will be seen that an annular funnel shaped seal 46 just above inlet 24 between the wall of the lower section 12 and baffle 42 maintains separation between incoming and exhausting liquid metal 32. Between baffle 42 and the wall of vessel 12 is a cylindrical thermal shield 47.
  • evaporator bundle 38 terminates in an annular feedwater chest 48 whereas superheater bundle 36 terminates in-a low pressure tube sheet 52 which is supported within a cylindrical shell 54 having a hemispherical head 56 located above tube sheet 52.
  • Tube sheet 52 separates a lower evaporator chamber. 55a within shell 54 from an upper superheater chamber 55b within head 56.
  • Feedwater chest 48 which admits feedwater through inlet nozzle 57, surrounds and is mounted on shell 54.
  • a ring of openings 58 is located in shell 54 below tube sheet 52 and 7 above feedwater chest 48.
  • An annular seal 59 above steam chest 48, divides the space around shell 54 into upper and lower regions, for reasons to be later described.
  • Spherical head 56 has a superheater outlet tube 62 which extends out of closure section 18. The latter is also provided with saturated steam inlet nozzle 64 and an access port 66. Spherical head 56 is provided with a normally closed access port 68.
  • a typical evaporator tube assembly 78 consists of a tube 82 extending down from chest 48 where feedwater enters as illustrated by arrow C from feedwater chest 48. Tube 82 passes through and opens below tube sheet 22 into a closed tube 77 which extends down to the bottom of baffle 42.
  • Tubes 77 and 82 are spaced from each other so that as indicated by arrows C the feedwater passes down through tube 82 for the length of evaporator bundle 38, reverses after exiting into tube 77 and passes up through the annular space between tubes 77 and 82, passing once again through tube sheet 22, emptying into the space surrounding shell 54 below seal 59.
  • the feedwater becomes saturated steam which then passes out of steam generator 10 by way of nozzle 23.
  • the saturated steam is carried from nozzle 23 through either a bypass line 83 or a steam drum S, to inlet nozzle 64.
  • Valves V1, V2, and V3 control the flow path of the steam which upon re-entering exchanger 10 passes into lower superheater chamber 55a by way of openings 58 in shell 54.
  • the saturated steam enters a tube assembly 76 by way of an annular space within an outer tube 72 whose entrance is in tube sheet 22, and terminates below above sodium inlet nozzle 24.
  • the steam flow reverses and passes up within a tube 74 which extends up through and spaced from tube sheet 22 to superheated steam chamber 55b where the superheated steam is combined from all of the tubes in superheater bundle 36 and then exits from generator 10 by way of superheated steam outlet nozzle 62, shown in FIG. 1.
  • the arrangement of tubes just described wherein a first tube exits into a second tube in which the flow is reversed for flow in the annular space is referred to as a bayonet tube configuration.
  • Vessel 12 is supported by a cylindrical skirt 86 and integral base plate 88 attached at the junction of the lower hemispherical head 15 and the cylindrical portion of lower section 14.
  • tubes 74,76, 78, and 82, and that of chamber 55b and feedwater chest 48 are illustrated as being solid it is understood that they may each comprise a double, thin wall construction with annular gaps, or dead space, between the double thin walls.
  • This annular gap, or dead space would serve in the case of evaporator tube assembly 78 as an insulator to minimize heat transfer to the feedwater as it flows to the bottom of the evaporator heat transfer tubing.
  • This construction well known in the art, provides a similar function in the bayonet tubes of the superheater bundle 36, and that of feedwater chest 48 and steam chamber 55b.
  • liquid sodium which is heated directly or indirectly in a separate heat source such as in a nuclear reactor, enters steam generator by way of inlet nozzle 24.
  • the hot sodium flows upwardly (shown by arrows A) in the central region within baffle 42, passing in the spaces between the tubes forming superheater bundle 36.
  • the sodium flows over the top edge 44 of baffle 42 and then down through the annular space formed by baffle 42 and thermal shield 47 filling the spaces between the tubes forming evaporator bundle 38.
  • the liquid sodium leaves generator 10 by way of outlet nozzle 26.
  • valve V3 is open and valves V1 and V2 are closed. When it is desired to operate heat exchanger in a recirculating mode, valve V3 is closed and valves V1 and V2 opened to permit the saturated steam to pass through steam drum S where separation of water from steam takes place. Then only dry steam is piped back into the superheater section.
  • the space above liquid metal 32 is provided to absorb the expansion due to any sodium-water reaction and to permit these products to be vented through nozzle 28.
  • Liquid metal steam generation apparatus comprising:
  • a.apressure vessel b. lower tube sheet means within said vessel dlVldUlg the latter into high pressure and low pressure regions;
  • evaporative means including tube assemblies of annularly arranged inner and outer tubes extending from said high pressure region through said lower tube sheet means into said hot liquid metal within the low pressure region for carrying said feedwater within the inner tubes into said low pressure region, said tube assemblies carrying within the annular spaces said feedwater during evaporation back through said lower tube sheet means for discharge into the high pressure region as saturated steam;
  • superheater means for receiving said saturated steam from said evaporative means in said high pressure region for producing superheated steam, consisting of tube assemblies of annularly arranged inner and outer tubes extending into said hot liquid metal within said low pressure region for carrying within annular spaces said saturated steam which is superheated during passage therethrough and returning the superheated steam in the inner tubes through said lower tube sheet means, the latter thereby being subject only to saturated steam temperatures within said vessel;
  • upper tube sheet means in said high pressure region spaced above said lower tube sheet means for receiving said superheated steam and delivering same from said steam generator.
  • the steam generator of claim 2 having means formed within said low pressure region for collecting and delivering out of said vessel the products of any water-liquid metal reaction.
  • said upper tube sheet means includes a tube sheet with an upper chamber fonned above said tube sheet to receive said superheated steam and a lower chamber extending between said tube sheet and said lower tube sheet means for receiving the saturated steam from said evaporative means, and manifold means above said lower tube sheet means annularly arranged around said lower chamber for receiving feedwater and passing same into said evaporative means.
  • the steam generator of claim 4 having means external of said pressure vessel for receiving said saturated steam from said evaporative means and returning the saturated steam to said pressure vessel, the latter having further means to direct the saturated steam into said lower chamber.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • General Engineering & Computer Science (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
US120151A 1971-03-02 1971-03-02 Sodium heated steam generator Expired - Lifetime US3662718A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US12015171A 1971-03-02 1971-03-02

Publications (1)

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US3662718A true US3662718A (en) 1972-05-16

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US120151A Expired - Lifetime US3662718A (en) 1971-03-02 1971-03-02 Sodium heated steam generator

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US (1) US3662718A (enExample)
AU (1) AU446056B2 (enExample)
BE (1) BE779846A (enExample)
CA (1) CA933057A (enExample)
DE (1) DE2208397A1 (enExample)
FR (1) FR2127845A5 (enExample)
GB (1) GB1313636A (enExample)
IT (1) IT949777B (enExample)

Cited By (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3939804A (en) * 1974-07-08 1976-02-24 Foster Wheeler Energy Corporation Helium heated bayonet tube steam generator
US4010797A (en) * 1974-03-04 1977-03-08 C F Braun & Co Heat exchanger
US4414923A (en) * 1982-03-01 1983-11-15 Deltak Corporation Heat recovery boiler for high pressure gas
US4644906A (en) * 1985-05-09 1987-02-24 Stone & Webster Engineering Corp. Double tube helical coil steam generator
US4737337A (en) * 1985-05-09 1988-04-12 Stone & Webster Engineering Corporation Nuclear reactor having double tube helical coil heat exchanger
US4753773A (en) * 1985-05-09 1988-06-28 Stone & Webster Engineering Corporation Double tube steam generator
CN101862917A (zh) * 2010-06-11 2010-10-20 鲁西工业装备有限公司 双管板换热器设备的焊制工艺
US20120247404A1 (en) * 2011-04-04 2012-10-04 Mitsubishi Heavy Industries, Ltd. Steam generator
CN104112481A (zh) * 2014-07-01 2014-10-22 中科华核电技术研究院有限公司 减少事故源项释放装置
US10401022B2 (en) * 2015-04-21 2019-09-03 General Electric Technology Gmbh Molten salt once-through steam generator

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2514119A1 (fr) * 1981-10-06 1983-04-08 Struthers Wells Sa Echangeur de chaleur tubulaire pour gaz a pression et temperature elevees
RU2135888C1 (ru) * 1997-11-25 1999-08-27 Государственный научный центр физико-энергетический институт им.акад.Лейпунского А.И. Парогенератор
RU2258176C1 (ru) * 2004-03-04 2005-08-10 ЗАО "Научно-производственное объединение "Гидропресс" Парогенератор с жидкометаллическим теплоносителем

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3076443A (en) * 1958-06-19 1963-02-05 Mitchell Engineering Ltd Heat exchanger
US3097630A (en) * 1961-02-24 1963-07-16 Brice W Kinyon Steam generator
US3267907A (en) * 1963-08-27 1966-08-23 Braun & Co C F Steam generator
US3357409A (en) * 1964-10-07 1967-12-12 Atomic Energy Authority Uk Vertical tube module once-through steam generator

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3076443A (en) * 1958-06-19 1963-02-05 Mitchell Engineering Ltd Heat exchanger
US3097630A (en) * 1961-02-24 1963-07-16 Brice W Kinyon Steam generator
US3267907A (en) * 1963-08-27 1966-08-23 Braun & Co C F Steam generator
US3357409A (en) * 1964-10-07 1967-12-12 Atomic Energy Authority Uk Vertical tube module once-through steam generator

Cited By (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4010797A (en) * 1974-03-04 1977-03-08 C F Braun & Co Heat exchanger
US3939804A (en) * 1974-07-08 1976-02-24 Foster Wheeler Energy Corporation Helium heated bayonet tube steam generator
US4414923A (en) * 1982-03-01 1983-11-15 Deltak Corporation Heat recovery boiler for high pressure gas
US4644906A (en) * 1985-05-09 1987-02-24 Stone & Webster Engineering Corp. Double tube helical coil steam generator
US4737337A (en) * 1985-05-09 1988-04-12 Stone & Webster Engineering Corporation Nuclear reactor having double tube helical coil heat exchanger
US4753773A (en) * 1985-05-09 1988-06-28 Stone & Webster Engineering Corporation Double tube steam generator
CN101862917A (zh) * 2010-06-11 2010-10-20 鲁西工业装备有限公司 双管板换热器设备的焊制工艺
CN101862917B (zh) * 2010-06-11 2012-07-18 鲁西工业装备有限公司 双管板换热器设备的焊制工艺
US20120247404A1 (en) * 2011-04-04 2012-10-04 Mitsubishi Heavy Industries, Ltd. Steam generator
US9182113B2 (en) * 2011-04-04 2015-11-10 Mitsubishi Heavy Industries, Ltd. Steam generator
CN104112481A (zh) * 2014-07-01 2014-10-22 中科华核电技术研究院有限公司 减少事故源项释放装置
US10401022B2 (en) * 2015-04-21 2019-09-03 General Electric Technology Gmbh Molten salt once-through steam generator

Also Published As

Publication number Publication date
BE779846A (fr) 1972-06-16
DE2208397A1 (de) 1972-09-14
CA933057A (en) 1973-09-04
AU446056B2 (en) 1974-02-14
GB1313636A (en) 1973-04-18
FR2127845A5 (enExample) 1972-10-13
IT949777B (it) 1973-06-11
AU3952372A (en) 1973-09-06

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