GB785050A - Improvements in or relating to nuclear reactor heated boiler systems - Google Patents

Improvements in or relating to nuclear reactor heated boiler systems

Info

Publication number
GB785050A
GB785050A GB759/55A GB75955A GB785050A GB 785050 A GB785050 A GB 785050A GB 759/55 A GB759/55 A GB 759/55A GB 75955 A GB75955 A GB 75955A GB 785050 A GB785050 A GB 785050A
Authority
GB
United Kingdom
Prior art keywords
pressure
boiler
reactor
varying
heat
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
GB759/55A
Inventor
Richard Valentine Moore
William Robert Wootton
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
Babcock and Wilcox Co
Original Assignee
Babcock and Wilcox Ltd
Babcock and Wilcox Co
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, Babcock and Wilcox Co filed Critical Babcock and Wilcox Ltd
Priority to GB759/55A priority Critical patent/GB785050A/en
Publication of GB785050A publication Critical patent/GB785050A/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
    • F22B1/18—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
    • F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
    • F01K7/00—Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating
    • F01K7/16—Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines being only of turbine type
    • F01K7/18—Steam engine plants characterised by the use of specific types of engine; Plants or engines characterised by their use of special steam systems, cycles or processes; Control means specially adapted for such systems, cycles or processes; Use of withdrawn or exhaust steam for feed-water heating the engines being only of turbine type the turbine being of multiple-inlet-pressure type
    • F01K7/20—Control means specially adapted therefor
    • 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
    • G21D3/10—Regulation of any parameters in the plant by a combination of a variable derived from neutron flux with other controlling variables, e.g. derived from temperature, cooling flow, pressure
    • 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
    • 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)
  • Mechanical Engineering (AREA)
  • Chemical & Material Sciences (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Thermal Sciences (AREA)
  • Engine Equipment That Uses Special Cycles (AREA)

Abstract

785,050. Composite steam boilers. BABCOCK & WILCOX, Ltd.,.and MOORE, R. V. Jan. 10, 1956 [Jan. 10, 1955], No. 759/55. Class 123(2) [Also in Group XXVI] A nuclear reactor 250 heating a boiler system through a heat transfer fluid is controlled as the load on the boiler system varies by varying the mass flow of heat transfer fluid to maintain constant the reactor outlet temperature and by varying the pressure in the boiler to maintain constant the reactor inlet temperature. Heat is transferred by carbon dioxide gas under pressure from the reactor to four double pressure heat exchangers 254. High pressure steam generated at 296 is supplied to a turbine 264. Low pressure steam generated at 297 is also supplied to the turbine, through a spillover valve 269 which is partially closed when the plant is not on full load. thereby raising the boiler pressure on the low pressure side to maintain the reactor inlet temperature. The mass flow is controlled by varying the speed of motors 256 driving circulators 287. On full load gas at temperature T1, is cooled in the boiler along curve Q, to T2, Fig. 4, whereas. on 10 per cent load with reduced flow it is cooled along curve R to T3, with less 'heat loss in the low pressure sections due to the increased boiler pressure. The valve 269 and motors 256 may be automatically controlled by fluid-pressure servomotors 313, 306, Fig. 5. During circulation. about 2 per cent of the coolant is dried and filtered at 295,
GB759/55A 1955-01-10 1955-01-10 Improvements in or relating to nuclear reactor heated boiler systems Expired GB785050A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB759/55A GB785050A (en) 1955-01-10 1955-01-10 Improvements in or relating to nuclear reactor heated boiler systems

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB759/55A GB785050A (en) 1955-01-10 1955-01-10 Improvements in or relating to nuclear reactor heated boiler systems

Publications (1)

Publication Number Publication Date
GB785050A true GB785050A (en) 1957-10-23

Family

ID=9710025

Family Applications (1)

Application Number Title Priority Date Filing Date
GB759/55A Expired GB785050A (en) 1955-01-10 1955-01-10 Improvements in or relating to nuclear reactor heated boiler systems

Country Status (1)

Country Link
GB (1) GB785050A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1228352B (en) * 1958-04-04 1966-11-10 Atomic Energy Commission Nuclear reactor
DE1247503B (en) * 1962-09-10 1967-08-17 Sulzer Ag Process for regulating a nuclear reactor plant and nuclear reactor plant for carrying out the process

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1228352B (en) * 1958-04-04 1966-11-10 Atomic Energy Commission Nuclear reactor
DE1247503B (en) * 1962-09-10 1967-08-17 Sulzer Ag Process for regulating a nuclear reactor plant and nuclear reactor plant for carrying out the process

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