AT270010B - Brennelement für wassergekühlte und moderierte Kernreaktoren - Google Patents

Brennelement für wassergekühlte und moderierte Kernreaktoren

Info

Publication number
AT270010B
AT270010B AT208366A AT208366A AT270010B AT 270010 B AT270010 B AT 270010B AT 208366 A AT208366 A AT 208366A AT 208366 A AT208366 A AT 208366A AT 270010 B AT270010 B AT 270010B
Authority
AT
Austria
Prior art keywords
cooled
water
fuel element
nuclear reactors
moderated nuclear
Prior art date
Application number
AT208366A
Other languages
English (en)
Original Assignee
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
Application filed by Siemens Ag filed Critical Siemens Ag
Application granted granted Critical
Publication of AT270010B publication Critical patent/AT270010B/de

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/18—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone
    • G21C5/22—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone wherein one zone is a superheating zone
    • 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
    • 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
    • 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
    • G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder 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
    • G21C15/24—Promoting flow of the coolant
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/322—Means to influence the coolant flow through or around the bundles
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
AT208366A 1965-05-19 1966-03-07 Brennelement für wassergekühlte und moderierte Kernreaktoren AT270010B (de)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DES0097170 1965-05-19

Publications (1)

Publication Number Publication Date
AT270010B true AT270010B (de) 1969-04-10

Family

ID=7520550

Family Applications (1)

Application Number Title Priority Date Filing Date
AT208366A AT270010B (de) 1965-05-19 1966-03-07 Brennelement für wassergekühlte und moderierte Kernreaktoren

Country Status (5)

Country Link
US (1) US3528885A (de)
AT (1) AT270010B (de)
DE (1) DE1514462A1 (de)
GB (1) GB1123996A (de)
SE (1) SE323461B (de)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0050837A1 (de) * 1980-10-29 1982-05-05 Ab Asea-Atom Brennelementbündel für einen Kernreaktor

Families Citing this family (22)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5259292A (en) * 1975-11-10 1977-05-16 Hitachi Ltd Core part structure of atomic pile
US4664880A (en) * 1984-12-07 1987-05-12 Westinghouse Electric Corp. Wire mesh debris trap for a fuel assembly
DE3515469A1 (de) * 1985-04-29 1986-10-30 Kraftwerk Union AG, 4330 Mülheim Brennelement fuer einen wassergekuehlten kernreaktor
US6278757B1 (en) * 1986-09-17 2001-08-21 Hitachi, Ltd Fuel assembly and nuclear reactor
US5023047A (en) * 1987-12-18 1991-06-11 Hitachi, Ltd. Nuclear reactor having an ascending cooling path much greater than the descending cooling path
US5617456A (en) * 1988-01-14 1997-04-01 Hitachi, Ltd. Fuel assembly and nuclear reactor
US7215729B1 (en) * 1988-01-14 2007-05-08 Hitachi, Ltd. Fuel assembly and nuclear reactor
US5640435A (en) * 1988-01-14 1997-06-17 Hitachi, Ltd. Fuel assembly and nuclear reactor
US5483564A (en) * 1993-04-12 1996-01-09 General Electric Company Lower tie plate strainers including double corrugated strainers for boiling water reactors
US5384814A (en) * 1993-04-12 1995-01-24 General Electric Company Lower tie plate strainers for boiling water reactors
US5390221A (en) * 1993-08-23 1995-02-14 General Electric Company Debris filters with flow bypass for boiling water reactors
US5390220A (en) * 1993-11-29 1995-02-14 General Electric Company Lower tie plate strainers including helical spring strainers for boiling water reactors
US5345483A (en) * 1993-12-02 1994-09-06 General Electric Company Lower tie plate strainers having double plate with offset holes for boiling water reactors
US5488634A (en) * 1994-02-10 1996-01-30 General Electric Company Lower tie plate debris catcher for a nuclear reactor
US5473650A (en) * 1994-04-15 1995-12-05 General Electric Company Lower tie plate debris catcher for a nuclear reactor
US5481578A (en) * 1994-06-24 1996-01-02 General Electric Company Perforated tube debris catcher for a nuclear reactor
US5539793A (en) * 1994-10-27 1996-07-23 General Electric Company Lower tie plate debris catcher for a nuclear reactor
US5519745A (en) * 1994-11-03 1996-05-21 General Electric Company Lower tie plate debris catcher for a nuclear reactor
US5528640A (en) * 1994-11-07 1996-06-18 General Electric Company Low pressure double offset plate catcher for a nuclear reactor
US6181763B1 (en) * 1997-10-08 2001-01-30 General Electric Company Siphon water rods
JP3504857B2 (ja) * 1998-06-19 2004-03-08 株式会社日立製作所 沸騰水型原子炉の運転方法
CN1319074C (zh) * 2005-03-18 2007-05-30 张育曼 采用套管燃料组件的超临界水核反应堆

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3182003A (en) * 1960-04-04 1965-05-04 Westinghouse Electric Corp Means for supporting fuel elements in a nuclear reactor
GB1075522A (en) * 1963-02-22 1967-07-12 Soc Anglo Belge Vulcain Sa Nuclear fuel assembly
GB1104631A (en) * 1963-12-16 1968-02-28 Atomic Energy Authority Uk Improvements in or relating to nuclear reactor fuel element assemblies
US3212991A (en) * 1964-06-03 1965-10-19 Glen V Brynsvold Continuous support fuel rod spacer system
GB1137251A (en) * 1964-11-30 1968-12-18 Lucas Industries Ltd Heat exchange apparatus

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0050837A1 (de) * 1980-10-29 1982-05-05 Ab Asea-Atom Brennelementbündel für einen Kernreaktor
US4826653A (en) * 1980-10-29 1989-05-02 Ab Asea Atom Fuel assembly with a water flow separated from the fuel rodsr

Also Published As

Publication number Publication date
SE323461B (de) 1970-05-04
US3528885A (en) 1970-09-15
GB1123996A (en) 1968-08-14
DE1514462A1 (de) 1969-08-28

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