GB926615A - Improvements in or relating to steam generating plant - Google Patents
Improvements in or relating to steam generating plantInfo
- Publication number
- GB926615A GB926615A GB15052/59A GB1505259A GB926615A GB 926615 A GB926615 A GB 926615A GB 15052/59 A GB15052/59 A GB 15052/59A GB 1505259 A GB1505259 A GB 1505259A GB 926615 A GB926615 A GB 926615A
- Authority
- GB
- United Kingdom
- Prior art keywords
- steam
- reactor
- generators
- pump
- water
- 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
Links
Classifications
-
- 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
-
- 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 far as they are not classified, according to a specified heating fluid, in another group
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22D—PREHEATING, OR ACCUMULATING PREHEATED, FEED-WATER FOR STEAM GENERATION; FEED-WATER SUPPLY FOR STEAM GENERATION; CONTROLLING WATER LEVEL FOR STEAM GENERATION; AUXILIARY DEVICES FOR PROMOTING WATER CIRCULATION WITHIN STEAM BOILERS
- F22D11/00—Feed-water supply not provided for in other main groups
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22D—PREHEATING, OR ACCUMULATING PREHEATED, FEED-WATER FOR STEAM GENERATION; FEED-WATER SUPPLY FOR STEAM GENERATION; CONTROLLING WATER LEVEL FOR STEAM GENERATION; AUXILIARY DEVICES FOR PROMOTING WATER CIRCULATION WITHIN STEAM BOILERS
- F22D5/00—Controlling water feed or water level; Automatic water feeding or water-level regulators
- F22D5/14—Controlling water feed or water level; Automatic water feeding or water-level regulators responsive to thermal expansion and contraction, e.g. of solid elements
- F22D5/16—Controlling water feed or water level; Automatic water feeding or water-level regulators responsive to thermal expansion and contraction, e.g. of solid elements of fluids
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
- G21C1/09—Pressure regulating arrangements, i.e. pressurisers
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/04—Pumping arrangements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
-
- 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
-
- 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
-
- 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
- Y02E30/30—Nuclear fission reactors
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- High Energy & Nuclear Physics (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- Water Supply & Treatment (AREA)
- Life Sciences & Earth Sciences (AREA)
- Sustainable Development (AREA)
- Sustainable Energy (AREA)
- Business, Economics & Management (AREA)
- Emergency Management (AREA)
- Engine Equipment That Uses Special Cycles (AREA)
Abstract
926,615. Nuclear power plant. ROLLS-ROYCE Ltd. June 2, 1960 [May 1, 1959], No. 15052/59. Class 39 (4). [Also in Group XIII] A nuclear reactor is used to superheat steam, of which a first part is fed from the reactor to two parallel steam generators where it is used to generate and superheat steam which is supplied to the reactor, and of which a second part is fed to a location of use, for example, in turbines where it is condensed, the condensate being returned to the steam generators by a single feed-water pump. The Figure shows a reactor 10 which supplies steam to steam generators 13; the generated steam is expanded through a nozzle and mixed with the steam from the reactor in a thermopump 17, and the mixture is returned to the reactor. The rest of the steam from the reactor is used in secondary steam generators 29, from which condensate is returned by way of heaters 51 and a pump 50 to the generators 13. The pressure at the pump inlet is held constant by means of a mixing chamber 73 connected to a pressurizing tank 76 to which are fed controlled amounts of steam and water. The pump is driven by steam from generators 29. In an emergency, water is forced from tank 130 into the reactor, after which coolant is allowed to flow by convection through tanks 131. Various auxiliary and emergency pumps 60, 65, 115 are provided, and so is a start-up steam generator 100. The pump 50 is driven by steam from generators 29. There is a water treatment plant 90 and a make-up water tank 83 which acts as an emergency condenser. Specifications 907,708 and 926,616 are referred to.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB15052/59A GB926615A (en) | 1959-05-01 | 1959-05-01 | Improvements in or relating to steam generating plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB15052/59A GB926615A (en) | 1959-05-01 | 1959-05-01 | Improvements in or relating to steam generating plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB926615A true GB926615A (en) | 1963-05-22 |
Family
ID=10052192
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB15052/59A Expired GB926615A (en) | 1959-05-01 | 1959-05-01 | Improvements in or relating to steam generating plant |
Country Status (1)
| Country | Link |
|---|---|
| GB (1) | GB926615A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2514933A1 (en) * | 1981-10-16 | 1983-04-22 | Framatome Sa | DEVICE FOR THE SAFETY INJECTION OF A PRESSURIZED WATER NUCLEAR REACTOR |
| EP0199179A1 (en) * | 1985-04-15 | 1986-10-29 | Hitachi, Ltd. | Drain recovery system for condensate feedwater system of nuclear power plant |
| CN110275461A (en) * | 2018-03-17 | 2019-09-24 | 杭州恒勋能源科技有限公司 | A kind of joint steam supplying device and its method of operation |
| CN113636707A (en) * | 2021-09-18 | 2021-11-12 | 江苏诺江环境工程有限公司 | Industrial wastewater recycling high-efficiency treatment equipment |
-
1959
- 1959-05-01 GB GB15052/59A patent/GB926615A/en not_active Expired
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2514933A1 (en) * | 1981-10-16 | 1983-04-22 | Framatome Sa | DEVICE FOR THE SAFETY INJECTION OF A PRESSURIZED WATER NUCLEAR REACTOR |
| EP0078192A1 (en) * | 1981-10-16 | 1983-05-04 | Framatome | Emergency feed system for a pressurized-water reactor |
| EP0199179A1 (en) * | 1985-04-15 | 1986-10-29 | Hitachi, Ltd. | Drain recovery system for condensate feedwater system of nuclear power plant |
| US4713209A (en) * | 1985-04-15 | 1987-12-15 | Hitachi, Ltd. | Drain recovery system for condensate feedwater system of nuclear power plant |
| CN110275461A (en) * | 2018-03-17 | 2019-09-24 | 杭州恒勋能源科技有限公司 | A kind of joint steam supplying device and its method of operation |
| CN113636707A (en) * | 2021-09-18 | 2021-11-12 | 江苏诺江环境工程有限公司 | Industrial wastewater recycling high-efficiency treatment equipment |
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