GB902182A - Improvements in nuclear reactor heat generating and utilising plant - Google Patents

Improvements in nuclear reactor heat generating and utilising plant

Info

Publication number
GB902182A
GB902182A GB35281/57A GB3528157A GB902182A GB 902182 A GB902182 A GB 902182A GB 35281/57 A GB35281/57 A GB 35281/57A GB 3528157 A GB3528157 A GB 3528157A GB 902182 A GB902182 A GB 902182A
Authority
GB
United Kingdom
Prior art keywords
pressure vessel
reactor
gas
conduit
heat exchange
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
GB35281/57A
Inventor
Anthony James Taylor
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.)
Babcock International Ltd
Original Assignee
Babcock and Wilcox 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 Babcock and Wilcox Ltd filed Critical Babcock and Wilcox Ltd
Priority to GB35281/57A priority Critical patent/GB902182A/en
Priority to NL233132A priority patent/NL233132A/xx
Priority to FR1214344D priority patent/FR1214344A/en
Publication of GB902182A publication Critical patent/GB902182A/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
    • F22B1/22—Methods of steam generation characterised by form of heating method using combustion under pressure substantially exceeding atmospheric pressure
    • 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
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B35/00—Control systems for steam boilers
    • F22B35/004—Control systems for steam generators of nuclear power plants
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/08—Regulation of any parameters in the plant
    • G21D3/12—Regulation of any parameters in the plant by adjustment of the reactor in response only to changes in engine demand
    • G21D3/14—Varying flow of coolant
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04—Reactor and engine not structurally combined
    • G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
    • 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

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Combustion & Propulsion (AREA)
  • Chemical & Material Sciences (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

902,182. Steam generators. BABCOCK & WILCOX Ltd. Nov. 12, 1958 [Nov. 12, 1957], No. 35281/57. Class 123 (2). [Also in Groups XXIX and XL (a)] A power plant comprises a gas-cooled nuclear reactor, coolant circulating means for circulating coolant under super-atmospheric pressure through the reactor and through a pressure vessel containing heat exchange means, and regulating means for regulating the coolant temperature at the inlet to the reactor, the regulating means including means within the pressure vessel for by-passing at least part of the heat exchange means and valve means for controlling the flow of coolant through the by-pass. In Fig. 1, the cylindrical pressure vessel 11 contains a casing 21 of square crosssection forming a gas duct and containing eight heat exchange units 23-30. Units 23-26 together with an external steam and water drum 31 form the high pressure boiler, unit 26 being a secondary economizer, units 25 and 24 the vapour generators, and unit 23 the superheater. Similarly, units 27-30 together with an external drum 33 form a low pressure boiler, unit 30 being in two parts, one of which forms the primary economizer for the high pressure boiler and the other of which forms the economizer of the low pressure boiler. A by-pass 52 controlled by a valve 53 is fitted in the segmental spaces between the square casing 21 and the cylindrical pressure vessel 11 and allows some of the gas to by-pass the heat exchange units 29, 30. Coolant from the reactor 2 is fed to the top of the pressure vessel and back from the bottom of the pressure vessel through a compressor 8 to the inlet of the reactor. Compressor 8 is controlled to keep the outlet temperature of the reactor coolant constant and valve 53 is controlled to keep the inlet temperature constant. In another arrangement, Fig. 7, the pressure vessel contains a gas conduit 110 of generally square cross-section to which gas is fed from the reactor (not shown) through conduit 108 and valve 112. The conduit 110 contains three heat exchange units 114, 115, 129 forming the superheater, evaporator and economizer and suitably connected to a boiler drum 144 mounted on top of the pressure vessel. After passing through conduit 110 the gas flows back along the outside of the conduit to the inlet of a centrifugal compressor 104 and then through valve 142 and conduit 143 and back to the reactor. A by-pass 164 controlled by valve 163 allows some of the gas to by-pass all the heat exchange surfaces in the pressure vessel.
GB35281/57A 1957-11-12 1957-11-12 Improvements in nuclear reactor heat generating and utilising plant Expired GB902182A (en)

Priority Applications (3)

Application Number Priority Date Filing Date Title
GB35281/57A GB902182A (en) 1957-11-12 1957-11-12 Improvements in nuclear reactor heat generating and utilising plant
NL233132A NL233132A (en) 1957-11-12 1958-11-12
FR1214344D FR1214344A (en) 1957-11-12 1958-11-12 Improvements to heat production and use installations

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB35281/57A GB902182A (en) 1957-11-12 1957-11-12 Improvements in nuclear reactor heat generating and utilising plant

Publications (1)

Publication Number Publication Date
GB902182A true GB902182A (en) 1962-07-25

Family

ID=10375944

Family Applications (1)

Application Number Title Priority Date Filing Date
GB35281/57A Expired GB902182A (en) 1957-11-12 1957-11-12 Improvements in nuclear reactor heat generating and utilising plant

Country Status (3)

Country Link
FR (1) FR1214344A (en)
GB (1) GB902182A (en)
NL (1) NL233132A (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3193468A (en) * 1960-07-12 1965-07-06 Babcock & Wilcox Co Boiling coolant nuclear reactor system
BE759016A (en) * 1969-12-18 1971-04-30 Deggendorfer Werft Eisenbau COOLER FOR THE PASSAGE OF AN ADJUSTABLE PART OF A HEAT VEHICLE KEEPED IN CIRCULATION IN A REACTOR

Also Published As

Publication number Publication date
NL233132A (en) 1965-11-15
FR1214344A (en) 1960-04-07

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