GB897447A - Improvements in or relating to nuclear reactor systems for producing a superheated working fluid - Google Patents

Improvements in or relating to nuclear reactor systems for producing a superheated working fluid

Info

Publication number
GB897447A
GB897447A GB34412/58A GB3441258A GB897447A GB 897447 A GB897447 A GB 897447A GB 34412/58 A GB34412/58 A GB 34412/58A GB 3441258 A GB3441258 A GB 3441258A GB 897447 A GB897447 A GB 897447A
Authority
GB
United Kingdom
Prior art keywords
reactor
superheated steam
turbine
superheated
steam
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
GB34412/58A
Inventor
Norman Bradley
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB34412/58A priority Critical patent/GB897447A/en
Priority to FR808624A priority patent/FR1239164A/en
Publication of GB897447A publication Critical patent/GB897447A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/08Regulation of any parameters in the plant
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D5/00Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04Reactor and engine not structurally combined
    • G21D5/06Reactor and engine not structurally combined with engine working medium circulating through reactor core
    • 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

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Control Of Turbines (AREA)

Abstract

897,447. Nuclear power plant. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Oct. 21, 1959 [Oct. 28, 1958; June 4, 1959], Nos. 34412/58 and 19146/59. Class 39(4). In a heavy water moderated, steam-cooled, nuclear reactor power plant, water is vaporized in heat exchangers heated by superheated steam from the reactor, which is supplied with vapour from the exchangers. The reactor superheated steam outlet temperature is maintained constant by a control rod positioned automatically in correspondence with a temperature error signal. The moderator water is temperature controlled by circulation through a cooler. The heat supply to an auxiliary feedwater heater is automatically raised as the turbine pressure falls. As shown in the Figure accompanying the Provisional Specification, the reactor 1 supplies superheated steam to the turbine 6. The condensate from condenser 7 is transferred, by pumps 8, 10, to the evaporators 2, 3, 4, 5 the saturated steam output from which passes to the reactor where it is superheated. From the reactor the superheated steam passes cyclically through 2, 3, 4 and the reactor before flowing through 5 to the turbine.
GB34412/58A 1958-10-28 1958-10-28 Improvements in or relating to nuclear reactor systems for producing a superheated working fluid Expired GB897447A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
GB34412/58A GB897447A (en) 1958-10-28 1958-10-28 Improvements in or relating to nuclear reactor systems for producing a superheated working fluid
FR808624A FR1239164A (en) 1958-10-28 1959-10-27 Nuclear reactor system to produce superheated working fluid

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB34412/58A GB897447A (en) 1958-10-28 1958-10-28 Improvements in or relating to nuclear reactor systems for producing a superheated working fluid

Publications (1)

Publication Number Publication Date
GB897447A true GB897447A (en) 1962-05-30

Family

ID=10365315

Family Applications (1)

Application Number Title Priority Date Filing Date
GB34412/58A Expired GB897447A (en) 1958-10-28 1958-10-28 Improvements in or relating to nuclear reactor systems for producing a superheated working fluid

Country Status (2)

Country Link
FR (1) FR1239164A (en)
GB (1) GB897447A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1250458B (en) * 1961-08-23

Also Published As

Publication number Publication date
FR1239164A (en) 1960-08-19

Similar Documents

Publication Publication Date Title
GB1140485A (en) Method of power generation and thermal power plant for the application of said method
GB906096A (en) Improvements in or relating to nuclear reactor powered steam generating systems
GB906079A (en) Improvements in boiling coolant nuclear reactor systems and methods of operating such systems
US3242053A (en) Nuclear power plant system
GB989593A (en) Improvements in and relating to nuclear reactor plants
US3421978A (en) Thermal power plant and method of operation
GB897447A (en) Improvements in or relating to nuclear reactor systems for producing a superheated working fluid
GB963351A (en) Method of starting a steam power plant
US3301762A (en) Method of superheating steam originating from a steam generator of a pressurized water nuclear reactor
GB841920A (en) Improvements in or relating to thermal power plants
GB1161654A (en) Process for Sodium Heated Modules
GB1153075A (en) Improvements in Nuclear Reactor Power Plants
GB797725A (en) Improvements relating to power plant including a nuclear reactor
JPS5231251A (en) Solar-thermal power generation system
GB839125A (en) Method and means for the recovery of heat
JPS54121346A (en) Steam generator for solar power plant
GB1297939A (en)
GB829676A (en) Atomic power plants having heterogeneous nuclear reactors
US3715272A (en) Method of operating a nuclear reactor facility with a steam cooled fast breeder reactor as the heat source
GB806068A (en) An improved method of operating nuclear power plant and improvements in such plant
GB888713A (en) Vapour generating plant
GB915718A (en) Improvements in and relating to feedwater temperature control systems of turbine plants
GB823429A (en) Improvements in or relating to control systems for nuclear power plants
GB832877A (en) Improvements in power plant for nuclear reactors
GB503072A (en) Improvements in or relating to steam power plants employing steam generators of the flow-through type