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GB1432663A - Nuclear reactor plants including evaporators - Google Patents

Nuclear reactor plants including evaporators

Info

Publication number
GB1432663A
GB1432663A GB1524173A GB1524173A GB1432663A GB 1432663 A GB1432663 A GB 1432663A GB 1524173 A GB1524173 A GB 1524173A GB 1524173 A GB1524173 A GB 1524173A GB 1432663 A GB1432663 A GB 1432663A
Authority
GB
United Kingdom
Prior art keywords
tubes
centre
plate
nuclear reactor
flow
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
GB1524173A
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.)
Sulzer AG
Original Assignee
Sulzer AG
Gebrueder Sulzer AG
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 Sulzer AG, Gebrueder Sulzer AG filed Critical Sulzer AG
Publication of GB1432663A publication Critical patent/GB1432663A/en
Expired legal-status Critical Current

Links

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
    • F22B1/023—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 long as they are not classified according to a specified heating fluid, in another group
    • F22B1/025—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 long as they are not classified according to a specified heating fluid, in another group with vertical U shaped tubes carried on a horizontal tube sheet
    • 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
    • F22B37/48—Devices or arrangements for removing water, minerals or sludge from boilers ; Arrangement of cleaning apparatus in boilers; Combinations thereof with boilers
    • F22B37/483—Devices or arrangements for removing water, minerals or sludge from boilers ; Arrangement of cleaning apparatus in boilers; Combinations thereof with boilers specially adapted for nuclear steam generators

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

1432663 Steam generators SULZER BROS Ltd 29 March 1973 [7 April 1972] 15241/73 Heading F4A A steam generator in a nuclear reactor plant comprises inverted U-tubes 9, Fig. 1, which are connected in the reactor cooling circuit via ports 6 and 7, and an apertured baffle arrangement 12, which may be alternatively in the form of rods or bars, arranged to ensure flow, e.g. substantially uniform, across tube plate 3 of feed water from 11 before passing through baffle 12 to flow upwardly between tubes 9, to thus prevent stagnant areas forming on plate 3. The apertures may or may not have tubes passing through them. Sludge is removed at the centre of plate 3 (through conduits 15, 16, Fig. 3, not shown) and dummy tubes (20, Fig. 3) may be provided in the centre of the tube bundle to create even flow up the centre of the bundle. The hot reactor coolant may be water under pressure.
GB1524173A 1972-04-07 1973-03-29 Nuclear reactor plants including evaporators Expired GB1432663A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CH510972A CH527390A (en) 1972-04-07 1972-04-07 Evaporator

Publications (1)

Publication Number Publication Date
GB1432663A true GB1432663A (en) 1976-04-22

Family

ID=4288072

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1524173A Expired GB1432663A (en) 1972-04-07 1973-03-29 Nuclear reactor plants including evaporators

Country Status (8)

Country Link
JP (1) JPS4935944A (en)
BE (1) BE797860A (en)
CH (1) CH527390A (en)
DE (1) DE2217575B1 (en)
ES (1) ES414363A1 (en)
FR (1) FR2179003B1 (en)
GB (1) GB1432663A (en)
IT (1) IT983683B (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107170491A (en) * 2017-07-14 2017-09-15 四川大学 Flow distribution device in a kind of pressurized water type reactor based on dome structure
CN113237044A (en) * 2021-06-16 2021-08-10 中国人民解放军海军工程大学 Asymmetric inverted U-shaped tube bundle steam generator for reactor

Families Citing this family (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS563941Y2 (en) * 1975-12-24 1981-01-28
JPS53145146U (en) * 1977-04-22 1978-11-15
US4131085A (en) * 1977-05-04 1978-12-26 The Babcock & Wilcox Company Vapor generating unit blowdown arrangement
JPS54120449A (en) * 1978-03-10 1979-09-19 Mitsubishi Heavy Ind Ltd Method and apparatus for cleansing minute gaps
JPS5584913U (en) * 1978-12-05 1980-06-11
FR2487043A1 (en) * 1980-07-18 1982-01-22 Framatome Sa DEVICE FOR DECOLMAGING AND RECOVERING SLUDGE ON THE TUBULAR PLATE OF A STEAM GENERATOR
JPS60144210U (en) * 1984-03-05 1985-09-25 東北金属工業株式会社 Fixed support for toroidal coils
US4704994A (en) * 1986-04-16 1987-11-10 Westinghouse Electric Corp. Flow boosting and sludge managing system for steam generator tube sheet
EP0315870B1 (en) * 1987-11-11 1990-09-12 Siemens Aktiengesellschaft Steam generator
US4972804A (en) * 1989-04-25 1990-11-27 Alexander T. Kindling Method and apparatus for organizing the flow of fluid in a vertical steam generator
JPH03124613U (en) * 1990-03-30 1991-12-17
US9897308B2 (en) 2013-12-26 2018-02-20 Nuscale Power, Llc Steam generator with tube aligning orifice
US9997262B2 (en) 2013-12-26 2018-06-12 Nuscale Power, Llc Integral reactor pressure vessel tube sheet

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS42882Y1 (en) * 1964-09-29 1967-01-19
CH493811A (en) * 1967-09-06 1970-07-15 Basf Ag Heat exchange device
DE1675501C3 (en) * 1968-03-12 1975-10-23 Deggendorfer Werft Und Eisenbau Gmbh, 8360 Deggendorf Device for the even distribution of heat exchange media in reaction apparatus with a tube bundle

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107170491A (en) * 2017-07-14 2017-09-15 四川大学 Flow distribution device in a kind of pressurized water type reactor based on dome structure
CN107170491B (en) * 2017-07-14 2023-07-04 中国核动力研究设计院 Pressurized water reactor flow distribution device based on dome structure
CN113237044A (en) * 2021-06-16 2021-08-10 中国人民解放军海军工程大学 Asymmetric inverted U-shaped tube bundle steam generator for reactor

Also Published As

Publication number Publication date
FR2179003B1 (en) 1977-04-29
ES414363A1 (en) 1976-10-01
IT983683B (en) 1974-11-11
DE2217575B1 (en) 1973-09-27
BE797860A (en) 1973-10-08
FR2179003A1 (en) 1973-11-16
CH527390A (en) 1972-08-31
JPS4935944A (en) 1974-04-03

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Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee