GB1006471A - Nuclear reactors - Google Patents

Nuclear reactors

Info

Publication number
GB1006471A
GB1006471A GB27291/63A GB2729163A GB1006471A GB 1006471 A GB1006471 A GB 1006471A GB 27291/63 A GB27291/63 A GB 27291/63A GB 2729163 A GB2729163 A GB 2729163A GB 1006471 A GB1006471 A GB 1006471A
Authority
GB
United Kingdom
Prior art keywords
coolant
heat exchanger
fuel
heat
remainder
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
GB27291/63A
Inventor
Everett Long
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
Application filed by English Electric Co Ltd filed Critical English Electric Co Ltd
Priority to GB27291/63A priority Critical patent/GB1006471A/en
Publication of GB1006471A publication Critical patent/GB1006471A/en
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
    • G21C1/04—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
    • 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
    • G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
    • 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
    • G21C1/086—Pressurised water reactors
    • 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

Abstract

1,006,471. Reactors. ENGLISH ELECTRIC CO. Ltd. July 9, 1964 [July 10, 1963], No. 27291/63. Heading G6C. A reactor of the type comprising a pressure vessel 10 containing a moderator core 11 (graphite), containing nuclear fuel, a heat exchanger 16 to transfer heat from a coolant heated by the fuel (gas) to a secondary coolant (water, steam), and a pump for closed circuit circulation of coolant between the heat exchanger and core, is characterized in that a portion of the coolant is heated by some of the fuel to a higher temperature than the remainder of the coolant, heated by the remaining fuel, and the heat exchanger includes a section which receives only the coolant at higher temperature, cools it to the temperature of the remainder whereon it is joined by the remainder for cooling of the entire coolant circulated. Thus channels 12a which constitute 5-19% of the total have stainless steel clad uranium oxide fuel elements which heat gas to 600‹ C. and pass it via plenum tank 15 to section 19b-19c of the heat exchanger. The remaining channels 12 contain uranium in magnesium alloy cans and heat coolant to 400‹ C. This gas is fed to the point 19c in the heat exchanger, at which point the first portion has reached this temperature.
GB27291/63A 1963-07-10 1963-07-10 Nuclear reactors Expired GB1006471A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB27291/63A GB1006471A (en) 1963-07-10 1963-07-10 Nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB27291/63A GB1006471A (en) 1963-07-10 1963-07-10 Nuclear reactors

Publications (1)

Publication Number Publication Date
GB1006471A true GB1006471A (en) 1965-10-06

Family

ID=10257193

Family Applications (1)

Application Number Title Priority Date Filing Date
GB27291/63A Expired GB1006471A (en) 1963-07-10 1963-07-10 Nuclear reactors

Country Status (1)

Country Link
GB (1) GB1006471A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2085380A1 (en) * 1970-04-15 1971-12-24 Commissariat Energie Atomique Reactor cooling system - with improved economy in heat utilisation
FR2085381A1 (en) * 1970-04-15 1971-12-24 Commissariat Energie Atomique Reactor cooling system - with improved economy of heat utilisation in heavy-water moderated reactors

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2085380A1 (en) * 1970-04-15 1971-12-24 Commissariat Energie Atomique Reactor cooling system - with improved economy in heat utilisation
FR2085381A1 (en) * 1970-04-15 1971-12-24 Commissariat Energie Atomique Reactor cooling system - with improved economy of heat utilisation in heavy-water moderated reactors

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