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 reactor

Info

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
Application number
GB14117/59A
Inventor
Otto Engler
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.)
Vereinigte Kesselwerke AG
Original Assignee
Vereinigte Kesselwerke AG
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 Vereinigte Kesselwerke AG filed Critical Vereinigte Kesselwerke AG
Priority to GB14117/59A priority Critical patent/GB900821A/en
Priority to FR798835A priority patent/FR1228787A/en
Publication of GB900821A publication Critical patent/GB900821A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/32Integral 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
    • G21C1/322Integral 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
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00Methods of steam generation characterised by form of heating method
    • F22B1/02Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F22B1/18Methods 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
    • F22B1/1823Methods 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
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/04Thermal reactors ; Epithermal reactors
    • G21C1/24Homogeneous reactors, i.e. in which the fuel and moderator present an effectively homogeneous medium to the neutrons
    • G21C1/26Single-region reactors
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear 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.
GB14117/59A 1959-04-24 1959-04-24 Forced flow once through steam generator associated with a gas-cooled nuclear reactor Expired GB900821A (en)

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)

* Cited by examiner, † Cited by third party
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

Cited By (3)

* Cited by examiner, † Cited by third party
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

Similar Documents

Publication Publication Date Title
GB803382A (en) Improvements in vapour generators
US3924675A (en) Energy absorber for sodium-heated heat exchanger
US3255088A (en) Integral nuclear reactor-steam generator unit
US3437077A (en) Once-through vapor generator
US3807365A (en) U-tube steam generator with segment superheater
US3245464A (en) Liquid metal heated vapor generator
US3398720A (en) Once-through steam generator having a central manifold and tube bundles of spiral tube construction
US2845906A (en) Vapor generating unit
US4446820A (en) Steam generator heated by liquid metal
US3279439A (en) Vapor generating superheating and reheating unit
US3633550A (en) Water pipe boiler
GB870735A (en) Improvements in tubulous boilers
GB900821A (en) Forced flow once through steam generator associated with a gas-cooled nuclear reactor
US3812825A (en) Sodium heated helical coil arrangement
JPS60244891A (en) Fast neutron reactor
US3153444A (en) Heat exchanger
GB772991A (en) Improvements in and relating to forced recirculation steam generators
US3775248A (en) Nuclear reactor boiler system
US3942482A (en) Bayonet tube steam generator
US3939804A (en) Helium heated bayonet tube steam generator
US2630104A (en) Steam generator
US2800113A (en) Steam generator
US3312198A (en) Steam generator having improved steam heating sections arranged for parallel flow
US3354869A (en) Heat exchangers
US3130713A (en) Horizontal vapor generating unit