GB1105194A - Heterogeneous nuclear reactors - Google Patents

Heterogeneous nuclear reactors

Info

Publication number
GB1105194A
GB1105194A GB36321/66A GB3632166A GB1105194A GB 1105194 A GB1105194 A GB 1105194A GB 36321/66 A GB36321/66 A GB 36321/66A GB 3632166 A GB3632166 A GB 3632166A GB 1105194 A GB1105194 A GB 1105194A
Authority
GB
United Kingdom
Prior art keywords
reactor
nuclear reactors
heterogeneous nuclear
exchanger
aug
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
GB36321/66A
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.)
Siemens Schuckertwerke AG
Siemens AG
Original Assignee
Siemens Schuckertwerke AG
Siemens AG
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 DES92534A external-priority patent/DE1281049B/en
Application filed by Siemens Schuckertwerke AG, Siemens AG filed Critical Siemens Schuckertwerke AG
Publication of GB1105194A publication Critical patent/GB1105194A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • G21C1/08Heterogeneous 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
    • 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
    • G21C1/18Heterogeneous 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
    • G21C1/20Heterogeneous 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
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/34Spacer grids
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/005Flux flattening
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/02Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/22Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material, e.g. by adding neutron-absorbing material to the coolant
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/26Control of nuclear reaction by displacement of the moderator or parts thereof by changing the moderator concentration
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/32Control of nuclear reaction by varying flow of coolant through the core by adjusting the coolant or moderator temperature
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D1/00Details of nuclear power plant
    • G21D1/02Arrangements of auxiliary equipment
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D5/00Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04Reactor and engine not structurally combined
    • G21D5/06Reactor and engine not structurally combined with engine working medium circulating through reactor core
    • 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
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)

Abstract

1,105,194. Controlling reactors. SIEMENSSCHUCKERTWERKE A.G. 12 Aug., 1966 [13 Aug., 1965], No. 36321/66. Addition to 1,069,016. Heading G6C. In a reactor of the type described in Specification 1,069,016, the water coolant-moderator is heated in a heat exchanger prior to entry into the reactor pressure vessel. The exchanger is heated by steam from the reactor output duct which is condensed in the exchanger and pumped into the reactor coolant supply system.
GB36321/66A 1964-08-08 1966-08-12 Heterogeneous nuclear reactors Expired GB1105194A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DES92534A DE1281049B (en) 1964-08-08 1964-08-08 Heterogeneous pressure vessel reactor
DES0098818 1965-08-13

Publications (1)

Publication Number Publication Date
GB1105194A true GB1105194A (en) 1968-03-06

Family

ID=39316156

Family Applications (1)

Application Number Title Priority Date Filing Date
GB36321/66A Expired GB1105194A (en) 1964-08-08 1966-08-12 Heterogeneous nuclear reactors

Country Status (5)

Country Link
AT (1) AT271649B (en)
BE (1) BE685472A (en)
CH (1) CH440468A (en)
FR (1) FR93553E (en)
GB (1) GB1105194A (en)

Also Published As

Publication number Publication date
FR93553E (en) 1969-04-18
AT271649B (en) 1969-06-10
CH440468A (en) 1967-07-31
BE685472A (en) 1967-02-13

Similar Documents

Publication Publication Date Title
US3467577A (en) Water moderated and cooled nuclear reactor power plant
GB906096A (en) Improvements in or relating to nuclear reactor powered steam generating systems
GB1117100A (en) Improvements in nuclear reactors
GB1003714A (en) Improvements in or relating to pressure vessels and to pressurisers using such vessel
GB1069032A (en) Superheating of steam in nuclear reactors
GB1093078A (en) Nuclear reactor of the pressurized water type
GB1131548A (en) Nuclear reactor
GB1043500A (en) Improvements relating to nuclear reactors
GB1105194A (en) Heterogeneous nuclear reactors
ES331941A1 (en) A pressure equalizing device. (Machine-translation by Google Translate, not legally binding)
GB1134457A (en) Thermal power plant and method of operation
GB968598A (en) Improvements in and relating to feed heaters for steam turbine plant
GB1049298A (en) Improvements in nuclear reactors
GB1121984A (en) Improvements in or relating to a method of regulating steam pressure and a thermal excess-pressure device or "pressurizer" employing said method
GB1161654A (en) Process for Sodium Heated Modules
GB1285677A (en) Nuclear reactor installations
GB1171856A (en) Improvements in Nuclear Reactors.
GB1115354A (en) Improvements in nuclear reactors
GB1131547A (en) Controlling the power of a nuclear reactor plant comprising steam generators
GB1041714A (en) Improvements in and relating to nuclear reactors
GB1083087A (en) Improvements in nuclear reactors
GB1102174A (en) Nuclear reactor
GB1235446A (en) Method of operating a nuclear reactor facility with a steam cooled fast breeder reactor as the heat source
GB1243372A (en) Improvements in or relating to nuclear reactors
GB1160553A (en) Improvements in or relating to Nuclear Reactors