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FR1399180A - Advanced steam generators of the tubular type, in which the heating fluid is a liquefied metal, such as sodium, which is particularly advantageous for nuclear reactors - Google Patents

Advanced steam generators of the tubular type, in which the heating fluid is a liquefied metal, such as sodium, which is particularly advantageous for nuclear reactors

Info

Publication number
FR1399180A
FR1399180A FR978801A FR978801A FR1399180A FR 1399180 A FR1399180 A FR 1399180A FR 978801 A FR978801 A FR 978801A FR 978801 A FR978801 A FR 978801A FR 1399180 A FR1399180 A FR 1399180A
Authority
FR
France
Prior art keywords
sodium
particularly advantageous
heating fluid
tubular type
steam generators
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
FR978801A
Other languages
French (fr)
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.)
Amec Foster Wheeler Holdings Ltd
Original Assignee
Foster Wheeler Ltd
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 Foster Wheeler Ltd filed Critical Foster Wheeler Ltd
Priority to FR978801A priority Critical patent/FR1399180A/en
Application granted granted Critical
Publication of FR1399180A publication Critical patent/FR1399180A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • F22B1/06Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium
    • F22B1/063Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium for metal cooled nuclear reactors
    • 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
    • F28D7/0066Multi-circuit heat-exchangers, e.g. integrating different heat exchange sections in the same unit or heat-exchangers for more than two fluids
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/04Thermal reactors ; Epithermal reactors
    • G21C1/06Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/14Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
    • G21C1/16Heterogeneous 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
    • 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
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/02Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • 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

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Plasma & Fusion (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
FR978801A 1964-06-18 1964-06-18 Advanced steam generators of the tubular type, in which the heating fluid is a liquefied metal, such as sodium, which is particularly advantageous for nuclear reactors Expired FR1399180A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR978801A FR1399180A (en) 1964-06-18 1964-06-18 Advanced steam generators of the tubular type, in which the heating fluid is a liquefied metal, such as sodium, which is particularly advantageous for nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR978801A FR1399180A (en) 1964-06-18 1964-06-18 Advanced steam generators of the tubular type, in which the heating fluid is a liquefied metal, such as sodium, which is particularly advantageous for nuclear reactors

Publications (1)

Publication Number Publication Date
FR1399180A true FR1399180A (en) 1965-05-14

Family

ID=8832713

Family Applications (1)

Application Number Title Priority Date Filing Date
FR978801A Expired FR1399180A (en) 1964-06-18 1964-06-18 Advanced steam generators of the tubular type, in which the heating fluid is a liquefied metal, such as sodium, which is particularly advantageous for nuclear reactors

Country Status (1)

Country Link
FR (1) FR1399180A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2448832A1 (en) * 1974-10-14 1976-04-22 Interatom LIQUID METAL / WATER HEAT EXCHANGER WITH REPLACEABLE PIPE COILS
EP0004218A2 (en) * 1978-03-07 1979-09-19 COMMISSARIAT A L'ENERGIE ATOMIQUE Etablissement de Caractère Scientifique Technique et Industriel Fast nuclear reactor with at least one auxiliary heat exchanger
EP0020264A1 (en) * 1979-05-31 1980-12-10 COMMISSARIAT A L'ENERGIE ATOMIQUE Etablissement de Caractère Scientifique Technique et Industriel Semi-modular type heat exchanger for nuclear reactor

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2448832A1 (en) * 1974-10-14 1976-04-22 Interatom LIQUID METAL / WATER HEAT EXCHANGER WITH REPLACEABLE PIPE COILS
EP0004218A2 (en) * 1978-03-07 1979-09-19 COMMISSARIAT A L'ENERGIE ATOMIQUE Etablissement de Caractère Scientifique Technique et Industriel Fast nuclear reactor with at least one auxiliary heat exchanger
EP0004218A3 (en) * 1978-03-07 1979-10-17 Commissariat A L'energie Atomique Etablissement De Caractere Scientifique Technique Et Industriel Fast nuclear reactor with at least one auxiliary heat exchanger
EP0020264A1 (en) * 1979-05-31 1980-12-10 COMMISSARIAT A L'ENERGIE ATOMIQUE Etablissement de Caractère Scientifique Technique et Industriel Semi-modular type heat exchanger for nuclear reactor
FR2458132A1 (en) * 1979-05-31 1980-12-26 Commissariat Energie Atomique SEMI-MODULAR INTERMEDIATE HEAT EXCHANGER FOR NUCLEAR REACTOR

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