ES254698A1 - Perfeccionamientos introducidos en los reactores nucleares de vapor recalentado, moderados por liquido - Google Patents

Perfeccionamientos introducidos en los reactores nucleares de vapor recalentado, moderados por liquido

Info

Publication number
ES254698A1
ES254698A1 ES0254698A ES254698A ES254698A1 ES 254698 A1 ES254698 A1 ES 254698A1 ES 0254698 A ES0254698 A ES 0254698A ES 254698 A ES254698 A ES 254698A ES 254698 A1 ES254698 A1 ES 254698A1
Authority
ES
Spain
Prior art keywords
liquid
tubes
nuclear
water
moderated
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
ES0254698A
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.)
General Electric Co
Original Assignee
General Electric 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
Application filed by General Electric Co filed Critical General Electric Co
Publication of ES254698A1 publication Critical patent/ES254698A1/es
Expired legal-status Critical Current

Links

Classifications

    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F13/00—Arrangements for modifying heat-transfer, e.g. increasing, decreasing
    • F28F13/06—Arrangements for modifying heat-transfer, e.g. increasing, decreasing by affecting the pattern of flow of the heat-exchange media
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/06—Flue or fire tubes; Accessories therefor, e.g. fire-tube inserts
    • 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
    • G21C1/082—Reactors where the coolant is overheated
    • 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
    • G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
    • G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
    • G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
    • G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
    • 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
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
    • 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
    • G21C15/20—Partitions or thermal insulation between fuel channel and moderator
    • 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
    • G21C15/22—Structural association of coolant tubes with headers
    • 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)
  • Hydrogen, Water And Hydrids (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

Perfeccionamientos introducidos en los reactores nucleares de vapor recalentado, moderados por líquido que comprenden un recipiente de reactor, una placa matriz dispuesta transversalmente cerca del extremo inferior de dicho recipiente, una pluralidad de tubos de transmisión paralelos que contienen el combustible nuclear, separados uno de otro y abiertos en ambos extremos para permitir el paso de refrigeración, medios para contener una capa de moderador de neutrones líquidos encima de dicha placa y alrededor de los mencionados tubos que contienen el combustible para formar un conjunto que reacciona en cadena nuclear, y medios para hacer pasar hacia arriba por dichos tubos de tratamiento para que se recaliente un refrigerante en fase gaseosa, caracterizados por el hecho de que los tubos de tratamiento están provistos de un soporte que establece un cierre hermético al fluido sólo en sus extremos inferiores, en dicha placa matriz,estando constituido por agua el moderador líquido y porvapor de agua el refrigerador en fase gaseosa.
ES0254698A 1959-01-02 1959-12-31 Perfeccionamientos introducidos en los reactores nucleares de vapor recalentado, moderados por liquido Expired ES254698A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US784763A US3085959A (en) 1959-01-02 1959-01-02 Liquid moderated vapor superheat reactor

Publications (1)

Publication Number Publication Date
ES254698A1 true ES254698A1 (es) 1960-05-01

Family

ID=25133457

Family Applications (1)

Application Number Title Priority Date Filing Date
ES0254698A Expired ES254698A1 (es) 1959-01-02 1959-12-31 Perfeccionamientos introducidos en los reactores nucleares de vapor recalentado, moderados por liquido

Country Status (9)

Country Link
US (1) US3085959A (es)
BE (1) BE586173A (es)
CH (1) CH377947A (es)
DE (1) DE1249412B (es)
ES (1) ES254698A1 (es)
FR (1) FR1244149A (es)
GB (1) GB937233A (es)
NL (2) NL246994A (es)
SE (1) SE316243B (es)

Families Citing this family (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB941132A (en) * 1959-02-26 1963-11-06 Licentia Gmbh A steam superheating nuclear reactor
US3182001A (en) * 1959-07-23 1965-05-04 Siemens Ag Heterogeneous nuclear reactor
NL260747A (es) * 1960-02-12
GB932463A (en) * 1960-10-27 1963-07-24 Atomic Energy Authority Uk Improvements in or relating to nuclear fuel elements
US3253999A (en) * 1961-08-18 1966-05-31 Westinghouse Electric Corp Boiling water nuclear reactor with improved vapor separating arrangement
US3183168A (en) * 1962-01-31 1965-05-11 Foster Wheeler Corp Nuclear reactor
US3240678A (en) * 1963-08-22 1966-03-15 Westinghouse Electric Corp Pressure tube neutronic reactor and coolant control means therefor
US3352365A (en) * 1964-06-26 1967-11-14 Babcock & Wilcox Co Nuclear reactor system
US3212986A (en) * 1964-11-05 1965-10-19 Robert T Pennington Three tank separate superheat reactor
SE366139B (es) * 1965-03-12 1974-04-08 Atomenergi Ab
US4557891A (en) * 1977-03-02 1985-12-10 Combustion Engineering, Inc. Pressurized water reactor flow arrangement

Family Cites Families (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2708656A (en) * 1944-12-19 1955-05-17 Fermi Enrico Neutronic reactor
US2861034A (en) * 1945-09-18 1958-11-18 Eugene P Wigner Neutronic reactor shield and spacer construction
US2868708A (en) * 1945-11-02 1959-01-13 Harcourt C Vernon Neutronic reactor
US2782158A (en) * 1945-11-02 1957-02-19 John A Wheeler Neutronic reactor
US2787593A (en) * 1946-02-21 1957-04-02 Herbert E Mctcalf Method and means of producing steam in neutronic reactors
US2778792A (en) * 1946-04-19 1957-01-22 Szilard Leo Method for unloading reactors
US2832733A (en) * 1946-04-23 1958-04-29 Szilard Leo Heavy water moderated neutronic reactor
US2806820A (en) * 1947-08-18 1957-09-17 Eugene P Wigner Neutronic reactor
CH282725A (de) * 1950-01-11 1952-05-15 Schweizerische Lokomotiv Eindampfapparat für kontinuierliche Arbeitsweise.
GB754183A (en) * 1954-05-14 1956-08-01 Asea Ab Improvements in nuclear-chain reactors
US2915446A (en) * 1954-11-29 1959-12-01 Asea Ab Gas cooled nuclear reactor
BE548285A (es) * 1955-05-31 1900-01-01
US2870076A (en) * 1956-07-31 1959-01-20 Leonard J Koch Method and apparatus for improving performance of a fast reactor
DE1039659B (de) * 1956-08-16 1958-09-25 Walther & Cie Ag Reaktor zur Durchfuehrung von Kernspaltungsreaktionen
DE1031901B (de) * 1957-01-26 1958-06-12 Siemens Ag Gasgekuehlter Kernreaktor

Also Published As

Publication number Publication date
US3085959A (en) 1963-04-16
NL246994A (es)
NL112938C (es)
CH377947A (de) 1964-05-31
GB937233A (en) 1963-09-18
DE1249412B (es)
BE586173A (fr) 1960-04-19
FR1244149A (fr) 1960-10-21
SE316243B (es) 1969-10-20

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