FR1483407A - Réacteur nucléaire - Google Patents

Réacteur nucléaire

Info

Publication number
FR1483407A
FR1483407A FR65566A FR65566A FR1483407A FR 1483407 A FR1483407 A FR 1483407A FR 65566 A FR65566 A FR 65566A FR 65566 A FR65566 A FR 65566A FR 1483407 A FR1483407 A FR 1483407A
Authority
FR
France
Prior art keywords
nuclear reactor
nuclear
reactor
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
FR65566A
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.)
English Electric Co Ltd
Original Assignee
English Electric Co 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
Priority claimed from GB29057/65A external-priority patent/GB1129363A/en
Application filed by English Electric Co Ltd filed Critical English Electric Co Ltd
Priority to FR65566A priority Critical patent/FR1483407A/fr
Application granted granted Critical
Publication of FR1483407A publication Critical patent/FR1483407A/fr
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/32—Integral 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
    • G21C1/326—Integral 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 next to or beside the core
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G21C1/022—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders characterised by the design or properties of the core
    • G21C1/024—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders characterised by the design or properties of the core where the core is divided in zones with fuel and zones with breeding material
    • 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
    • G21C1/10—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 moderator and coolant being different or separated
    • G21C1/12—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 moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C11/00—Shielding structurally associated with the reactor
    • G21C11/02—Biological shielding ; Neutron or gamma shielding
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C11/00—Shielding structurally associated with the reactor
    • G21C11/02—Biological shielding ; Neutron or gamma shielding
    • G21C11/022—Biological shielding ; Neutron or gamma shielding inside the reactor vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C11/00—Shielding structurally associated with the reactor
    • G21C11/02—Biological shielding ; Neutron or gamma shielding
    • G21C11/028—Biological shielding ; Neutron or gamma shielding characterised by the form or by the material
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C11/00—Shielding structurally associated with the reactor
    • G21C11/08—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation
    • 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
    • G21C15/08—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from moderating 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
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/10—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from reflector or thermal shield
    • 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
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G21C5/08—Means for preventing undesired asymmetric expansion of the complete structure ; Stretching devices, pins
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G21C5/10—Means for supporting the complete structure
    • 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)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Biomedical Technology (AREA)
  • General Health & Medical Sciences (AREA)
  • Molecular Biology (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
FR65566A 1965-07-08 1966-06-15 Réacteur nucléaire Expired FR1483407A (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR65566A FR1483407A (fr) 1965-07-08 1966-06-15 Réacteur nucléaire

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB29057/65A GB1129363A (en) 1965-07-08 1965-07-08 Nuclear reactors
FR65566A FR1483407A (fr) 1965-07-08 1966-06-15 Réacteur nucléaire

Publications (1)

Publication Number Publication Date
FR1483407A true FR1483407A (fr) 1967-06-02

Family

ID=26171334

Family Applications (1)

Application Number Title Priority Date Filing Date
FR65566A Expired FR1483407A (fr) 1965-07-08 1966-06-15 Réacteur nucléaire

Country Status (1)

Country Link
FR (1) FR1483407A (fr)

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2067167A1 (fr) * 1968-11-08 1971-08-20 Nuclear Power Group Ltd
FR2099666A1 (fr) * 1970-07-29 1972-03-17 British Nuclear Design Constr
FR2108896A1 (fr) * 1970-10-16 1972-05-26 Commissariat Energie Atomique
FR2211716A1 (en) * 1972-12-27 1974-07-19 Commissariat Energie Atomique Composite heat transport medium - using a solid e.g. graphite dispersed in a gas e.g. helium for high temperature heat transmission e.g. from nuclear reactors
FR2382264A1 (fr) * 1977-03-03 1978-09-29 Ght Hochtemperaturreak Tech Dispositif melangeur et disperseur pour gaz a haute temperature
FR2389201A1 (fr) * 1977-04-26 1978-11-24 Hochtemperatur Reaktorbau Gmbh Support du coeur d'un reacteur a haute temperature de grande puissance refroidi par gaz
FR2462000A1 (fr) * 1979-07-23 1981-02-06 Hochtemperatur Reaktorbau Gmbh Fond porteur forme d'un grand nombre de blocs de graphite pour le coeur d'un reacteur nucleaire a elements combustibles spheriques
FR2497388A1 (fr) * 1980-12-30 1982-07-02 Commissariat Energie Atomique Reacteur nucleaire refroidi par un metal liquide et comprenant une cuve posee a fond froid

Cited By (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2067167A1 (fr) * 1968-11-08 1971-08-20 Nuclear Power Group Ltd
FR2099666A1 (fr) * 1970-07-29 1972-03-17 British Nuclear Design Constr
FR2108896A1 (fr) * 1970-10-16 1972-05-26 Commissariat Energie Atomique
FR2211716A1 (en) * 1972-12-27 1974-07-19 Commissariat Energie Atomique Composite heat transport medium - using a solid e.g. graphite dispersed in a gas e.g. helium for high temperature heat transmission e.g. from nuclear reactors
FR2382264A1 (fr) * 1977-03-03 1978-09-29 Ght Hochtemperaturreak Tech Dispositif melangeur et disperseur pour gaz a haute temperature
FR2389201A1 (fr) * 1977-04-26 1978-11-24 Hochtemperatur Reaktorbau Gmbh Support du coeur d'un reacteur a haute temperature de grande puissance refroidi par gaz
FR2462000A1 (fr) * 1979-07-23 1981-02-06 Hochtemperatur Reaktorbau Gmbh Fond porteur forme d'un grand nombre de blocs de graphite pour le coeur d'un reacteur nucleaire a elements combustibles spheriques
FR2497388A1 (fr) * 1980-12-30 1982-07-02 Commissariat Energie Atomique Reacteur nucleaire refroidi par un metal liquide et comprenant une cuve posee a fond froid
EP0055963A3 (en) * 1980-12-30 1982-08-11 Commissariat A L'energie Atomique Etablissement De Caractere Scientifique Technique Et Industriel Liquid metal cooled nuclear reactor comprising a main vessel cooled at the bottom
US4671922A (en) * 1980-12-30 1987-06-09 Commissariat A L'energie Atomique Nuclear reactor cooled by a liquid metal

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