GB806068A - An improved method of operating nuclear power plant and improvements in such plant - Google Patents

An improved method of operating nuclear power plant and improvements in such plant

Info

Publication number
GB806068A
GB806068A GB512/56A GB51256A GB806068A GB 806068 A GB806068 A GB 806068A GB 512/56 A GB512/56 A GB 512/56A GB 51256 A GB51256 A GB 51256A GB 806068 A GB806068 A GB 806068A
Authority
GB
United Kingdom
Prior art keywords
vapour
turbine
port
heat exchanger
reheated
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
GB512/56A
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 GB512/56A priority Critical patent/GB806068A/en
Publication of GB806068A publication Critical patent/GB806068A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • F01K3/00—Plants characterised by the use of steam or heat accumulators, or intermediate steam heaters, therein
    • F01K3/18—Plants characterised by the use of steam or heat accumulators, or intermediate steam heaters, therein having heaters
    • F01K3/26—Plants characterised by the use of steam or heat accumulators, or intermediate steam heaters, therein having heaters with heating by steam
    • F01K3/262—Plants characterised by the use of steam or heat accumulators, or intermediate steam heaters, therein having heaters with heating by steam by means of heat exchangers
    • 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
    • G21D5/06—Reactor and engine not structurally combined with engine working medium circulating through reactor core
    • 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)
  • General Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Chemical & Material Sciences (AREA)
  • Combustion & Propulsion (AREA)
  • Mechanical Engineering (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Control Of Turbines (AREA)

Abstract

806,068. Turbines. BABCOCK & WILCOX Ltd. Jan. 4, 1957 [Jan. 6, 1956], No. 512/56. Class 110 (3). [Also in Group XL (a)] A nuclear power plant having a vapour generator supplying vapour to a turbine has the vapour between the turbine stages dried in a moisture separator and then reheated by vapour bled from the turbine at a higher pressure than that at the point of reheating. Dry saturated vapour or substantially saturated vapour is supplied from a boiling water reactor to a two-stage turbine 1, 2 through a conduit 4. The vapour is reheated between the stages 1, 2 in a head exchanger 3. Vapour bled from the turbine 1 before the conduit 5 is passed through a stop or control valve 9 to the coils 11 of the heat exchanger. The coils 11 discharge through a stop or control valve 13 to a condensate drain for supply to the feedwater system of the vapour generator. The valves 9, 13 may be used to isolate the reheater or either one or both of the valves may be automatically controlled to regulate the degree of reheat in the heat exchanger. A separator 14 is provided to separate the larger moisture particles from the exhaust vapour. The separator 14 may be integral with the heat exchanger 3. An arrangement of this kind is shown in Fig. 2. The pressure vessel 21 has two headers 34, 35 connected by port 36 to the bleed point on the turbine and by the port 30 to the drain outlet. A tube bundle 23 connects the two headers. The vapour to be reheated enters through the port 25 and then passes around the outside of an arcuate baffle plate 33. At the lower edges of this plate the flow of vapour is suddenly reversed causing the larger particles of liquid to be separated and drained away through the port 29. The vapour then flows over the tube bundle as indicated by the arrows 42 to the outlet 26 which leads to the low pressure turbine stages. The heat exchanger is inclined to facilitate drainage of the separated water and condensed bleed-vapour. The reactor may be of the pressurized water or gas-cooled type.
GB512/56A 1956-01-06 1956-01-06 An improved method of operating nuclear power plant and improvements in such plant Expired GB806068A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB512/56A GB806068A (en) 1956-01-06 1956-01-06 An improved method of operating nuclear power plant and improvements in such plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB512/56A GB806068A (en) 1956-01-06 1956-01-06 An improved method of operating nuclear power plant and improvements in such plant

Publications (1)

Publication Number Publication Date
GB806068A true GB806068A (en) 1958-12-17

Family

ID=9705660

Family Applications (1)

Application Number Title Priority Date Filing Date
GB512/56A Expired GB806068A (en) 1956-01-06 1956-01-06 An improved method of operating nuclear power plant and improvements in such plant

Country Status (1)

Country Link
GB (1) GB806068A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3140588A (en) * 1960-12-29 1964-07-14 Gen Electric Reactor-turbine control system
US3153618A (en) * 1960-03-03 1964-10-20 Sulzer Ag Cooling system for a nuclear reactor
EP0193184A1 (en) * 1985-02-26 1986-09-03 Alexander I. Kalina Method and apparatus for implementing a thermodynamic cycle with intercooling

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3153618A (en) * 1960-03-03 1964-10-20 Sulzer Ag Cooling system for a nuclear reactor
US3140588A (en) * 1960-12-29 1964-07-14 Gen Electric Reactor-turbine control system
EP0193184A1 (en) * 1985-02-26 1986-09-03 Alexander I. Kalina Method and apparatus for implementing a thermodynamic cycle with intercooling
AU581054B2 (en) * 1985-02-26 1989-02-09 Alexander I. Kalina Method and apparatus for implementing a thermodynamic cycle with intercooling

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