GB924137A - Improvements in or relating to heat exchangers particularly for nuclear reactors - Google Patents

Improvements in or relating to heat exchangers particularly for nuclear reactors

Info

Publication number
GB924137A
GB924137A GB19683/58A GB1968358A GB924137A GB 924137 A GB924137 A GB 924137A GB 19683/58 A GB19683/58 A GB 19683/58A GB 1968358 A GB1968358 A GB 1968358A GB 924137 A GB924137 A GB 924137A
Authority
GB
United Kingdom
Prior art keywords
steam
baffle
casing
water
tube
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
Application number
GB19683/58A
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.)
JOHN MACKINTOSH SUTHERLAND
MITCHELL ENGINEERING Ltd
Original Assignee
JOHN MACKINTOSH SUTHERLAND
MITCHELL ENGINEERING Ltd
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 JOHN MACKINTOSH SUTHERLAND, MITCHELL ENGINEERING Ltd filed Critical JOHN MACKINTOSH SUTHERLAND
Priority to GB19683/58A priority Critical patent/GB924137A/en
Priority to US820941A priority patent/US3076443A/en
Priority to DEM41874A priority patent/DE1196667B/en
Publication of GB924137A publication Critical patent/GB924137A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/16Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants comprising means for separating liquid and steam
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00Methods of steam generation characterised by form of heating method
    • F22B1/02Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F22B1/08Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being steam
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00Methods of steam generation characterised by form of heating method
    • F22B1/02Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F22B1/08Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being steam
    • F22B1/12Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being steam produced by an indirect cyclic process
    • F22B1/123Steam generators downstream of a nuclear boiling water reactor
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00Component parts or details of steam boilers
    • F22B37/02Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/26Steam-separating arrangements
    • F22B37/32Steam-separating arrangements using centrifugal force
    • F22B37/327Steam-separating arrangements using centrifugal force specially adapted for steam generators of nuclear power plants
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22DPREHEATING, OR ACCUMULATING PREHEATED, FEED-WATER FOR STEAM GENERATION; FEED-WATER SUPPLY FOR STEAM GENERATION; CONTROLLING WATER LEVEL FOR STEAM GENERATION; AUXILIARY DEVICES FOR PROMOTING WATER CIRCULATION WITHIN STEAM BOILERS
    • F22D1/00Feed-water heaters, i.e. economisers or like preheaters
    • F22D1/02Feed-water heaters, i.e. economisers or like preheaters with water tubes arranged in the boiler furnace, fire tubes, or flue ways
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Plasma & Fusion (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Vaporization, Distillation, Condensation, Sublimation, And Cold Traps (AREA)
  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)

Abstract

924,137. Heating water-tube steam boilers, combined with nuclear reactors, by steam. MITCHELL ENGINEERING Ltd., H. J. COLES, and J. W. SUTHERLAND. June 15, 1959 [June 19, 1958], No. 19683/58. Classes 123 (2) and 123 (3). A steam generator which is adapted to be heated by radio-active steam produced in a boiling water nuclear reactor is formed of interconnected upper and lower casings 12, 10, so that the lower casing 10, which is lined internally with stainless steel and which receives the radio-active heating steam, can be located within a shielding wall, not shown, surrounding the reactor. A plurality of stainless steel tubes 17 with closed lower ends have their open upper ends flush with the upper face of a tube plate 14 which is sandwiched between the casings 10, 12, flanges 10c, 12c of which are secured together by a ring of studs 15 and nuts 16. The bores of the tubes 17 in this manner only communicate with the interior of the casing 12. A cylindrical baffle 18, surrounding the tubes 17, is secured concentrically within the casing 10 with its ends spaced respectively from a domed-end part 10a and the tube plate 14 by means of a ring 19. Steam from the reactor, entering an inlet pipe 20 located in the casing 10 immediately above the ring 19, rises through an annular space 21 which locates catalyst beds 22 to recombine any dissociated oxygen and hydrogen into steam. The heating steam then flows downwardly within the baffle 18 over the external surfaces of the tubes 17, condensate being passed through an outlet pipe 23. A cylindrical baffle 24, extending upwardly within and for part of the length of the casing 12 from the tube plate 14, has mounted therein, a short distance from its lower end, an upper tube plate 25. Tubes 26, open at each end, are fitted into openings in the tube plate 25 each tube 26 extending into, to adjacent the bottom of a corresponding tube 17. Feed water is fed through a pipe 30 to a well 28 within the baffle 24, the water being maintained at a level above the outlet end of the pipe 29 but below shrouded openings 33 in the upper end of the baffle 24. The water is heated and vaporized as it flows downwardly through the pipes 26 and then upwardly through the annular spaces between the pipes 26, 17. The generated steam rises and passes out of slots 40 in the lower end of the baffle 24 and into an annular space 31 between the baffle 24 and the casing 12. The steam then flows inwardly through the shrouded openings 33, which act as water separators, and through a ring 36 of swirl vanes located between an outlet pipe 35 and a funnel 37 which has a narrow condensate tube 37a leading to a point below the level of the water in the well 28. An annular steam baffle 32 secured within the casing 12 has its inner edge turned down to project into the upper end of the baffle 24.
GB19683/58A 1958-06-19 1958-06-19 Improvements in or relating to heat exchangers particularly for nuclear reactors Expired GB924137A (en)

Priority Applications (3)

Application Number Priority Date Filing Date Title
GB19683/58A GB924137A (en) 1958-06-19 1958-06-19 Improvements in or relating to heat exchangers particularly for nuclear reactors
US820941A US3076443A (en) 1958-06-19 1959-06-17 Heat exchanger
DEM41874A DE1196667B (en) 1958-06-19 1959-06-19 Vertical waste heat saturated steam generator with field pipes

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB19683/58A GB924137A (en) 1958-06-19 1958-06-19 Improvements in or relating to heat exchangers particularly for nuclear reactors

Publications (1)

Publication Number Publication Date
GB924137A true GB924137A (en) 1963-04-24

Family

ID=10133446

Family Applications (1)

Application Number Title Priority Date Filing Date
GB19683/58A Expired GB924137A (en) 1958-06-19 1958-06-19 Improvements in or relating to heat exchangers particularly for nuclear reactors

Country Status (3)

Country Link
US (1) US3076443A (en)
DE (1) DE1196667B (en)
GB (1) GB924137A (en)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3662718A (en) * 1971-03-02 1972-05-16 Atomic Energy Commission Sodium heated steam generator
US3888212A (en) * 1972-10-24 1975-06-10 Foster Wheeler Corp Liquid metal steam generator
US3939804A (en) * 1974-07-08 1976-02-24 Foster Wheeler Energy Corporation Helium heated bayonet tube steam generator
DE2735450A1 (en) * 1977-08-05 1979-02-15 Kraftwerk Union Ag STEAM GENERATORS FOR NUCLEAR POWER PLANTS, IN PARTICULAR FOR PRESSURE WATER REACTORS
CN115341278B (en) * 2022-07-28 2023-10-10 陕西斯瑞新材料股份有限公司 Single crystal furnace water-cooling heat shield prepared from copper or copper alloy and preparation method thereof

Family Cites Families (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE62911C (en) * A. COLLMANN in Wien, Beatrixgasse 18 Inlay for steam boilers with hanging field tubes
US163100A (en) * 1875-05-11 Improvement in feed-water heaters
DE141250C (en) * 1901-10-29 1903-05-18
FR392428A (en) * 1908-06-27 1908-11-26 Emile Louis Alfred Savy Apparatus intended to operate the cooling or heating of any liquids, creams, beer, wine, milk
US1067010A (en) * 1909-05-26 1913-07-08 American Evaporator Company Evaporator.
US2064317A (en) * 1931-09-24 1936-12-15 Celanese Corp Process for performing chemical reactions
FR797552A (en) * 1935-05-07 1936-04-29 accelerated circulation vertical evaporator for cold production
US2871108A (en) * 1955-11-18 1959-01-27 Diamond Alkali Co Apparatus for separating solid-liquidgas mixtures

Also Published As

Publication number Publication date
US3076443A (en) 1963-02-05
DE1196667B (en) 1965-07-15

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