CH385364A - Nuclear reactor plant for the generation of superheated steam - Google Patents

Nuclear reactor plant for the generation of superheated steam

Info

Publication number
CH385364A
CH385364A CH7888659A CH7888659A CH385364A CH 385364 A CH385364 A CH 385364A CH 7888659 A CH7888659 A CH 7888659A CH 7888659 A CH7888659 A CH 7888659A CH 385364 A CH385364 A CH 385364A
Authority
CH
Switzerland
Prior art keywords
generation
superheated steam
nuclear reactor
reactor plant
plant
Prior art date
Application number
CH7888659A
Other languages
German (de)
Inventor
Andreas Dipl Ing Setzwein
Braun Helmut
Original Assignee
Bbc Brown Boveri & Cie
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 Bbc Brown Boveri & Cie filed Critical Bbc Brown Boveri & Cie
Publication of CH385364A publication Critical patent/CH385364A/en

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04—Reactor and engine not structurally combined
    • G21D5/06—Reactor and engine not structurally combined with engine working medium circulating through reactor 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
    • F22B1/023—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers with heating tubes for nuclear reactors, as long as they are not classified according to a specified heating fluid, in another group
    • 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
    • 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
    • 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)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
CH7888659A 1959-06-06 1959-09-30 Nuclear reactor plant for the generation of superheated steam CH385364A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DEB53513A DE1128573B (en) 1959-06-06 1959-06-06 Nuclear reactor plant for the generation of superheated steam with a nuclear reactor with a heterogeneous reactor core

Publications (1)

Publication Number Publication Date
CH385364A true CH385364A (en) 1964-12-15

Family

ID=6970298

Family Applications (1)

Application Number Title Priority Date Filing Date
CH7888659A CH385364A (en) 1959-06-06 1959-09-30 Nuclear reactor plant for the generation of superheated steam

Country Status (5)

Country Link
BE (1) BE583878A (en)
CH (1) CH385364A (en)
DE (1) DE1128573B (en)
FR (1) FR1239599A (en)
GB (1) GB906556A (en)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE627360A (en) * 1960-07-15 1900-01-01
DE1134391B (en) * 1961-01-06 1962-08-09 Borsig Ag Steam circuit with multiple indirect intermediate overheating
DE1133401B (en) * 1961-08-14 1962-07-19 Bernhard Polock Dipl Ing Process for converting the heat released in nuclear reactors into mechanical energy
NL288038A (en) * 1962-07-05 1900-01-01
GB966409A (en) * 1963-01-15 1900-01-01

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1051425B (en) * 1958-03-07 1959-02-26 Siemens Ag Pressurized water reactor system with overheating of the working medium

Also Published As

Publication number Publication date
BE583878A (en)
DE1128573B (en) 1962-04-26
GB906556A (en) 1962-09-26
FR1239599A (en) 1960-08-26

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