GB900821A - Forced flow once through steam generator associated with a gas-cooled nuclear reactor - Google Patents
Forced flow once through steam generator associated with a gas-cooled nuclear reactorInfo
- Publication number
- GB900821A GB900821A GB14117/59A GB1411759A GB900821A GB 900821 A GB900821 A GB 900821A GB 14117/59 A GB14117/59 A GB 14117/59A GB 1411759 A GB1411759 A GB 1411759A GB 900821 A GB900821 A GB 900821A
- Authority
- GB
- United Kingdom
- Prior art keywords
- tubes
- gas
- reactor
- tube
- header
- 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
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
- G21C1/322—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed above the core
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/24—Homogeneous reactors, i.e. in which the fuel and moderator present an effectively homogeneous medium to the neutrons
- G21C1/26—Single-region reactors
-
- 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
Abstract
900,821. Forced-flow steam boilers. VEREINIGTE KESSELWERKE A.G. April 24, 1959, No. 14117/59. Class 123 (2). [Also in Group XL (a)] A forced-flow, once-through steam boiler 3 is disposed in a double-walled pressure vessel 10, 11 above a nuclear reactor 1 and is heated by the gas coolant from the reactor, the gases being circulated by external fans 7 which force the gases downwardly through an annular passage 2 and upwardly through the reactor and the tube bank of the generator. Dampers 16 are provided in the gas passage 2 so that some or all of the gases can by-pass the reactor. The space between the double-walls of the pressure vessel is filled with rammed concrete 12 and, where the gas circulating tubes 6, 8 and the water and steam tubes 27, 33 pass through the upper part of the vessel walls, with gravel which allows of expansion movements of the tubes, the gas tubes being fitted with expansion joints 14 whilst the water and steam tubes 27, 33 have expansion bends 15 in this region. The tube system of the generator consists of an external annular feedwater header 26, Fig. 2, divided into a number, say four, sections from each of which a number of parallel connected tubes 27 pass into the pressure vessel and are therein serially connected in a number of superposed " pancake" platens forming an economizer 28, an evaporating section 29 and a superheater 32. Between the evaporator and superheater all the tubes are connected to an external annular mixing header 30 divided into four sections each provided with means for removing salts-contaminated water whilst the superheated steam flows through the tubes 33 into a similarly divided external annular header 34 provided with superheat temperature controlling water sprays. In accordance with the invention, the "pancake" " platens are, as shown in Fig. 3a, formed of tubes bent to form identical, equally spaced involutes 17 extending from a central space which is occupied by a tube 35, capped at its lower end 36 to prevent gas short-circuiting, to the periphery of the generator which thus has a circular section. The involute form of the tubes ensures that they are equally spaced throughout each platen and therefore receive the same amount of heat from the upflowing gases. The platens are supported by tubes 31 conveying steam from the mixing header 30 to the superheater. In a modification, Fig. 3b, not shown, each platen consists of U-tubes, the arms of which are bent into parallel extending involutes, the involutes in adjacent platens being oppositely directed. If a leak should occur in a tube of any one of the four independent sections of the system, isolating valves for that section are closed, the reactor is shut down and the gas by-pass dampers 16 changed over to prevent gases carrying reactor residual heat into the boiler. The three undamaged sections are drained and the outlet header of the damaged section opened into a screened vessel. Radioactivity can then be detected in the damaged tube where it enters the header and both ends of this tube are then sealed off. The generator can then be put into operation again with the reduced heating surface.
Priority Applications (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB14117/59A GB900821A (en) | 1959-04-24 | 1959-04-24 | Forced flow once through steam generator associated with a gas-cooled nuclear reactor |
FR798835A FR1228787A (en) | 1959-04-24 | 1959-06-29 | Steam generator for gas-cooled nuclear reactors |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB14117/59A GB900821A (en) | 1959-04-24 | 1959-04-24 | Forced flow once through steam generator associated with a gas-cooled nuclear reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
GB900821A true GB900821A (en) | 1962-07-11 |
Family
ID=10035310
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB14117/59A Expired GB900821A (en) | 1959-04-24 | 1959-04-24 | Forced flow once through steam generator associated with a gas-cooled nuclear reactor |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB900821A (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3310104A (en) * | 1962-12-29 | 1967-03-21 | Babcock & Wilcox Ltd | Tube bank heat exchanger with supports |
US3379616A (en) * | 1965-07-09 | 1968-04-23 | Soc Indatom | Heat extraction device for nuclear reactor |
DE1464849B1 (en) * | 1963-08-01 | 1970-08-20 | Commissariat Energie Atomique | Nuclear reactor plant |
-
1959
- 1959-04-24 GB GB14117/59A patent/GB900821A/en not_active Expired
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3310104A (en) * | 1962-12-29 | 1967-03-21 | Babcock & Wilcox Ltd | Tube bank heat exchanger with supports |
DE1464849B1 (en) * | 1963-08-01 | 1970-08-20 | Commissariat Energie Atomique | Nuclear reactor plant |
US3379616A (en) * | 1965-07-09 | 1968-04-23 | Soc Indatom | Heat extraction device for nuclear reactor |
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