GB1284871A - Improvements in or relating to nuclear reactors - Google Patents
Improvements in or relating to nuclear reactorsInfo
- Publication number
- GB1284871A GB1284871A GB41691/68A GB4169168A GB1284871A GB 1284871 A GB1284871 A GB 1284871A GB 41691/68 A GB41691/68 A GB 41691/68A GB 4169168 A GB4169168 A GB 4169168A GB 1284871 A GB1284871 A GB 1284871A
- Authority
- GB
- United Kingdom
- Prior art keywords
- steam
- turbine
- reactor
- aug
- correspondence
- 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
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Engine Equipment That Uses Special Cycles (AREA)
- Control Of Turbines (AREA)
Abstract
1284871 Nuclear power plant ATOMIC POWER CONSTRUCTIONS Ltd 13 Aug 1969 [30 Aug 1968] 41691/68 Heading G6C In a nuclear power plant, the hood on the gascooled, graphite-moderated, high temperature reactor is automatically controlled in correspondence with the alternator output. Gas coolant from the reactor 1 is circulated through the heat exchangers 2, 2a to produce a steam supply for the turbines Id and 1e. The controller, 3, which produces signals corresponding to the frequency and load of the alternator, 3a, supplies control signals to the gas circulator vane adjuster, 6; to the turbine 7b driving the exchanger feed water pump, 7c; to the turbine steam control valve, 8; to the valve 1j controlling the flow of steam from the reheater 2a to the turbine, 1e. A further adjustment of the reactor gas circulator vanes is effected at 6a in correspondence with the temperature of the steam leaving the heat exchanger, 2.
Priority Applications (4)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB41691/68A GB1284871A (en) | 1968-08-30 | 1968-08-30 | Improvements in or relating to nuclear reactors |
DE19681806183 DE1806183A1 (en) | 1968-08-30 | 1968-10-30 | Nuclear power plant and procedures for its operation |
FR1591208D FR1591208A (en) | 1968-08-30 | 1968-10-31 | |
BE723300D BE723300A (en) | 1968-08-30 | 1968-10-31 |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB41691/68A GB1284871A (en) | 1968-08-30 | 1968-08-30 | Improvements in or relating to nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1284871A true GB1284871A (en) | 1972-08-09 |
Family
ID=10420902
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB41691/68A Expired GB1284871A (en) | 1968-08-30 | 1968-08-30 | Improvements in or relating to nuclear reactors |
Country Status (4)
Country | Link |
---|---|
BE (1) | BE723300A (en) |
DE (1) | DE1806183A1 (en) |
FR (1) | FR1591208A (en) |
GB (1) | GB1284871A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2337354A1 (en) * | 1973-07-23 | 1975-02-06 | Siemens Ag | PRESSURE WATER REACTOR WITH ADJUSTABLE CONTROL RODS |
US4470949A (en) * | 1980-11-03 | 1984-09-11 | Framatome | Method of control of a nuclear reactor by movement within the core of this reactor, of groups of control rods |
-
1968
- 1968-08-30 GB GB41691/68A patent/GB1284871A/en not_active Expired
- 1968-10-30 DE DE19681806183 patent/DE1806183A1/en active Pending
- 1968-10-31 BE BE723300D patent/BE723300A/xx unknown
- 1968-10-31 FR FR1591208D patent/FR1591208A/fr not_active Expired
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2337354A1 (en) * | 1973-07-23 | 1975-02-06 | Siemens Ag | PRESSURE WATER REACTOR WITH ADJUSTABLE CONTROL RODS |
US4470949A (en) * | 1980-11-03 | 1984-09-11 | Framatome | Method of control of a nuclear reactor by movement within the core of this reactor, of groups of control rods |
Also Published As
Publication number | Publication date |
---|---|
DE1806183A1 (en) | 1970-03-05 |
FR1591208A (en) | 1970-04-27 |
BE723300A (en) | 1969-04-01 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PLNP | Patent lapsed through nonpayment of renewal fees |