ES422740A2 - Perfeccionamientos en sistemas generadores de fuerza de va- riedad nuclear - Google Patents

Perfeccionamientos en sistemas generadores de fuerza de va- riedad nuclear

Info

Publication number
ES422740A2
ES422740A2 ES422740A ES422740A ES422740A2 ES 422740 A2 ES422740 A2 ES 422740A2 ES 422740 A ES422740 A ES 422740A ES 422740 A ES422740 A ES 422740A ES 422740 A2 ES422740 A2 ES 422740A2
Authority
ES
Spain
Prior art keywords
steam generator
nuclear steam
consolidated nuclear
consolidated
attainment
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
ES422740A
Other languages
English (en)
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 and Wilcox Co
Original Assignee
Babcock and Wilcox Co
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
Priority claimed from US05/327,349 external-priority patent/US3941187A/en
Application filed by Babcock and Wilcox Co filed Critical Babcock and Wilcox Co
Publication of ES422740A2 publication Critical patent/ES422740A2/es
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C13/00Pressure vessels; Containment vessels; Containment in general
    • G21C13/02Details
    • G21C13/032Joints between tubes and vessel walls, e.g. taking into account thermal stresses
    • G21C13/036Joints between tubes and vessel walls, e.g. taking into account thermal stresses the tube passing through the vessel wall, i.e. continuing on both sides of the wall
    • 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
    • F22B1/16Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour
    • F22B1/162Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour in combination with a nuclear installation
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22STEAM GENERATION
    • F22BMETHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00Component parts or details of steam boilers
    • F22B37/02Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/10Water tubes; Accessories therefor
    • F22B37/20Supporting arrangements, e.g. for securing water-tube sets
    • F22B37/205Supporting and spacing arrangements for tubes of a tube bundle
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28HEAT EXCHANGE IN GENERAL
    • F28DHEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
    • F28D7/00Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall
    • F28D7/16Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall the conduits being arranged in parallel spaced relation
    • F28D7/163Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall the conduits being arranged in parallel spaced relation with conduit assemblies having a particular shape, e.g. square or annular; with assemblies of conduits having different geometrical features; with multiple groups of conduits connected in series or parallel and arranged inside common casing
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28HEAT EXCHANGE IN GENERAL
    • F28FDETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F13/00Arrangements for modifying heat-transfer, e.g. increasing, decreasing
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28HEAT EXCHANGE IN GENERAL
    • F28FDETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F9/00Casings; Header boxes; Auxiliary supports for elements; Auxiliary members within casings
    • F28F9/02Header boxes; End plates
    • F28F9/0246Arrangements for connecting header boxes with flow lines
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28HEAT EXCHANGE IN GENERAL
    • F28FDETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F9/00Casings; Header boxes; Auxiliary supports for elements; Auxiliary members within casings
    • F28F9/02Header boxes; End plates
    • F28F9/026Header boxes; End plates with static flow control means, e.g. with means for uniformly distributing heat exchange media into conduits
    • F28F9/027Header boxes; End plates with static flow control means, e.g. with means for uniformly distributing heat exchange media into conduits in the form of distribution pipes
    • F28F9/0275Header boxes; End plates with static flow control means, e.g. with means for uniformly distributing heat exchange media into conduits in the form of distribution pipes with multiple branch pipes
    • FMECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28HEAT EXCHANGE IN GENERAL
    • F28DHEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
    • F28D21/00Heat-exchange apparatus not covered by any of the groups F28D1/00 - F28D20/00
    • F28D2021/0019Other heat exchangers for particular applications; Heat exchange systems not otherwise provided for
    • F28D2021/0054Other heat exchangers for particular applications; Heat exchange systems not otherwise provided for for nuclear applications
    • 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
    • Y02E30/10Nuclear fusion 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
    • 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
    • Y10TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10STECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00Induced nuclear reactions: processes, systems, and elements
    • Y10S376/911Plural reactor systems

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Sustainable Development (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Plasma & Fusion (AREA)
  • Sustainable Energy (AREA)
  • Geometry (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Engine Equipment That Uses Special Cycles (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Saccharide Compounds (AREA)
  • Jet Pumps And Other Pumps (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

Según el invento, estos problemas citados anteriormente se resuelven en grado notable. Un ejemplo típico del perfeccionamiento en éste sistema generador de vapor de agua consiste en una cubierta o refuerzo para el tubo de entrada de alimentación que penetra en la plancha del tubo de entrada de alimentación que penetra en la plancha el tubo de entrada de alimentación que penetra en la plancha del tubo y establece comunicación de fluido con una cámara de cabeza de entrada de agua. Se ha averiguado que la cubierta que circunscribe el tubo de entrada de agua de alimentación inhibe la formación de vapor de agua en el interior del tubo y, por lo tanto, reduce el potencial de conducciones de vapor de agua-agua inestables en el cambiador de calor. Otro perfeccionamiento en éste sistema consiste en una penetración de entrada de agua de alimentación para el recipiente del reactor que protege la pared interior del recipiente de presión del reactor contra esfuerzos inducidos térmicamente. Este aparatocomprende una conducción de entrada de agua de alimentación externa al recipiente de presión, una brida formada en el extremo de la conducción de agua de alimentación adyacente al recipiente de presión, un manguito de unión que sobresale de la superficie del recipiente de presión provisto de una brida formada en su extremo, colocada en sentido opuesto y alineada axialmente con la brida de la conducción de agua de alimentación, un tubo formado sobre la brida alineado axialmente con la misma para atravesar el recipiente de presión, y una camisa de varias laminaciones de aislamiento térmicos reflectante interpuesto en una corona circular que se forma entre el recipiente interpuesto en una corona circular que se forma entre el recipiente de presión, y una camisa de varias laminaciones de aislamiento térmico reflectante interpuesto en una corona circular que se forma entre el recipiente de presión del reactor y el tubo. El perfeccionamiento consiste también en una placa interpuesta entre las bridas, con un orificio formado en su centro, y un protector térmico sujeto a dicha placa de orificio con un eje geométrico alineado generalmente con el orificio y sobresaliendo a través del recipiente de presión. El aparato de penetración perfeccionado, además de proteger térmicamente al recipiente de presión, promueve también la estabilidad de flujo impidiendo la iniciación de ebullición dentro del tubo de alimentación de agua y gracias también a los beneficios de estabilización de flujo que supone el orificio. Otro perfeccionamiento adicional de éste sistema consiste en un par de lineas o conducciones de entrada o salida del refrigerante secundario que se unen entre sí junto a la pared exterior del recipiente de presión en una conexión de codo de retorno. Además, una "T" une el codo de retorno a una tuburladura de entrada o salida. La conexión de codo de retorno a una tubuladura de entrada o salida. La conexión de codo de otro modo incontrolado, de un tubo de vapor de agua hendido en caso de fallo de una de las conducciones.
ES422740A 1973-01-29 1974-01-29 Perfeccionamientos en sistemas generadores de fuerza de va- riedad nuclear Expired ES422740A2 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US05/327,349 US3941187A (en) 1971-07-14 1973-01-29 Consolidated nuclear steam generator

Publications (1)

Publication Number Publication Date
ES422740A2 true ES422740A2 (es) 1979-10-16

Family

ID=23276190

Family Applications (1)

Application Number Title Priority Date Filing Date
ES422740A Expired ES422740A2 (es) 1973-01-29 1974-01-29 Perfeccionamientos en sistemas generadores de fuerza de va- riedad nuclear

Country Status (19)

Country Link
US (1) US4124064A (es)
JP (1) JPS5321041B2 (es)
AT (1) AT332901B (es)
BE (1) BE808645A (es)
BR (1) BR7400476D0 (es)
CA (1) CA1004377A (es)
CH (4) CH591743A5 (es)
DK (1) DK138917B (es)
ES (1) ES422740A2 (es)
FR (5) FR2215674B1 (es)
GB (1) GB1451501A (es)
IE (1) IE39321B1 (es)
IL (1) IL43700A (es)
NL (1) NL174776C (es)
NO (1) NO138351C (es)
PH (1) PH14766A (es)
SE (4) SE378471B (es)
TR (1) TR19077A (es)
ZA (1) ZA74176B (es)

Families Citing this family (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2419565A1 (fr) * 1978-03-07 1979-10-05 Commissariat Energie Atomique Echangeur d'ultime secours, notamment pour reacteur nucleaire a neutrons rapides
US4508677A (en) * 1983-02-09 1985-04-02 General Electric Company Modular nuclear reactor for a land-based power plant and method for the fabrication, installation and operation thereof
JPH07119817B2 (ja) * 1989-01-31 1995-12-20 動力炉・核燃料開発事業団 自律分散型高速増殖炉システム
US6302194B1 (en) * 1991-03-13 2001-10-16 Siemens Aktiengesellschaft Pipe with ribs on its inner surface forming a multiple thread and steam generator for using the pipe
IT1398998B1 (it) * 2010-03-22 2013-03-28 Cosmogas Srl Scambiatore di calore
US20110286564A1 (en) * 2010-05-19 2011-11-24 Johnson Rolland P Accelerator driven power generation
FR2989506B1 (fr) * 2012-04-11 2018-08-31 Societe Technique Pour L'energie Atomique Reacteur nucleaire avec echangeurs de chaleur a plaques ou micro canaux integres dans la cuve
US9230697B2 (en) * 2012-04-20 2016-01-05 Nuscale Power, Llc Steam generator for a nuclear reactor
US9593866B2 (en) * 2012-06-14 2017-03-14 Sunlight Power, Inc. Thermal heat storage system
US9997262B2 (en) 2013-12-26 2018-06-12 Nuscale Power, Llc Integral reactor pressure vessel tube sheet
CZ201586A3 (cs) * 2015-02-10 2016-08-03 ENERGOVĂťZKUM, spol. s.r.o. Modulový obrácený parní generátor pro jaderné energetické zařízení
CZ306101B6 (cs) * 2015-02-10 2016-08-03 ENERGOVĂťZKUM, spol. s.r.o. Sekce modulů obráceného parního generátoru pro jaderná energetická zařízení
US20170023305A1 (en) * 2015-07-22 2017-01-26 General Electric Company Steam generator having an integrated modular heat exchanger

Family Cites Families (17)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3012547A (en) * 1955-04-21 1961-12-12 Westinghouse Electric Corp Unitized steam generator
US3033538A (en) * 1956-06-11 1962-05-08 Babcock & Wilcox Co Fluid heaters
GB846754A (en) * 1957-06-24 1960-08-31 Atomic Energy Authority Uk Improvements in or relating to heat exchangers
US3129697A (en) * 1959-01-14 1964-04-21 Trepaud Georges Heat exchanger and boiler, particularly to use the heat given off by nuclear reactors
GB997757A (en) * 1960-04-14 1965-07-07 Superheater Co Ltd Improvements relating to heat exchangers
US3255088A (en) * 1960-08-22 1966-06-07 Babcock & Wilcox Co Integral nuclear reactor-steam generator unit
BE631026A (es) * 1962-04-13
GB1015912A (en) * 1962-05-28 1966-01-05 Foster Wheeler Ltd Improvements in and relating to vapour generators
NL136725C (es) * 1962-07-31
GB1128913A (en) * 1965-02-05 1968-10-02 English Electric Co Ltd Nuclear reactors
FR1469515A (fr) * 1965-11-08 1967-02-17 Fives Penhoet Echangeur de chaleur monotubulaire à circulation forcée
FR1511662A (fr) * 1966-12-23 1968-02-02 Commissariat Energie Atomique Réacteur nucléaire refroidi par un liquide
BE785941A (fr) * 1971-07-07 1973-01-08 Atomic Energy Authority Uk Perfectionnements aux elements combustibles de reacteurs nucleaires
US3892027A (en) * 1971-10-28 1975-07-01 Babcock & Wilcox Co Industrial technique
US3920515A (en) * 1972-09-26 1975-11-18 Westinghouse Electric Corp Fuel assembly for a nuclear reactor
US3955620A (en) * 1974-04-26 1976-05-11 Artemov Lev N Heat exchanger
DE2430161C2 (de) * 1974-06-24 1983-07-07 Hochtemperatur-Reaktorbau GmbH, 5000 Köln Wärmetauscher mit kreisförmigem oder hexagonalem Querschnitt

Also Published As

Publication number Publication date
IE39321B1 (en) 1978-09-13
ATA1071073A (de) 1976-02-15
PH14766A (en) 1981-12-09
TR19077A (tr) 1978-05-01
CA1004377A (en) 1977-01-25
IL43700A (en) 1976-08-31
NL7315563A (es) 1974-07-31
CH568637A5 (es) 1975-10-31
FR2228276A1 (es) 1974-11-29
FR2228210B1 (es) 1976-12-31
SE7508135L (sv) 1975-07-16
SE7508137L (sv) 1975-07-16
GB1451501A (en) 1976-10-06
FR2215674A1 (es) 1974-08-23
FR2228277A1 (es) 1974-11-29
BR7400476D0 (pt) 1974-08-22
SE415306B (sv) 1980-09-22
IE39321L (en) 1974-07-29
FR2228277B1 (es) 1976-12-31
JPS5321041B2 (es) 1978-06-30
AT332901B (de) 1976-10-25
JPS49104094A (es) 1974-10-02
FR2215674B1 (es) 1976-11-26
CH591743A5 (es) 1977-09-30
SE7508136L (sv) 1975-07-16
FR2228210A1 (es) 1974-11-29
FR2228211B1 (es) 1976-12-31
BE808645A (nl) 1974-06-14
DK138917C (es) 1979-04-23
SE378471B (es) 1975-09-01
FR2228276B1 (es) 1976-10-22
NO138351B (no) 1978-05-08
CH568639A5 (es) 1975-10-31
NL174776C (nl) 1984-08-01
SE402834B (sv) 1978-07-17
US4124064A (en) 1978-11-07
ZA74176B (en) 1974-12-24
NO138351C (no) 1978-08-16
IL43700A0 (en) 1974-03-14
DK138917B (da) 1978-11-13
CH568638A5 (es) 1975-10-31
FR2228211A1 (es) 1974-11-29

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