BE591447A - - Google Patents

Info

Publication number
BE591447A
BE591447A BE591447DA BE591447A BE 591447 A BE591447 A BE 591447A BE 591447D A BE591447D A BE 591447DA BE 591447 A BE591447 A BE 591447A
Authority
BE
Belgium
Application number
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.)
Publication of BE591447A publication Critical patent/BE591447A/xx

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/06Casings; Jackets
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C13/00Pressure vessels; Containment vessels; Containment in general
    • G21C13/02Details
    • 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
    • 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
    • G21C15/04Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
    • G21C15/06Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material in 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
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/16Details of the construction within the casing
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/16Details of the construction within the casing
    • G21C3/18Internal spacers or other non-active material within the casing, e.g. compensating for expansion of fuel rods or for compensating excess reactivity
    • 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
    • G21C5/00Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02Details
    • G21C5/06Means for locating or supporting fuel elements
    • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
  • Glass Compositions (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
BE591447D 1959-06-03 BE591447A (en:Method)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
FR796455A FR1238281A (fr) 1959-06-03 1959-06-03 Perfectionnements aux procédés de réalisation d'éléments de réacteurs nucléaires
FR819663A FR76850E (fr) 1959-06-03 1960-02-26 Perfectionnements aux procédés de réalisation d'éléments de réacteurs nucléaires
FR823313A FR77484E (fr) 1959-06-03 1960-04-04 Perfectionnements aux procédés de réalisation d'éléments de réacteurs nucléaires

Publications (1)

Publication Number Publication Date
BE591447A true BE591447A (en:Method)

Family

ID=27245275

Family Applications (1)

Application Number Title Priority Date Filing Date
BE591447D BE591447A (en:Method) 1959-06-03

Country Status (6)

Country Link
US (2) US3252868A (en:Method)
BE (1) BE591447A (en:Method)
DE (1) DE1217514B (en:Method)
FR (4) FR1238281A (en:Method)
GB (2) GB953873A (en:Method)
NL (2) NL252138A (en:Method)

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3445254A (en) * 1964-10-14 1969-05-20 Atomic Energy Commission Glass fibers and treatment therefor
US3285826A (en) * 1966-05-20 1966-11-15 James E Lang Fuel element containing a mechanically compressible mandril
DE3472489D1 (en) * 1983-05-06 1988-08-04 Babcock & Wilcox Co Annular fuel rods for nuclear reactors
FR2670046B1 (fr) * 1990-11-30 1993-03-05 Framatome Sa Reacteur nucleaire a eau sous pression et a cloisonnement massif.
US5182077A (en) * 1991-04-15 1993-01-26 Gamma Engineering Corporation Water cooled nuclear reactor and fuel elements therefor
US6233299B1 (en) * 1998-10-02 2001-05-15 Japan Nuclear Cycle Development Institute Assembly for transmutation of a long-lived radioactive material

Family Cites Families (29)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CA543048A (en) * 1945-07-03 1957-07-02 Atomic Energy Of Canada Limited - Energie Atomique Du Canada, Limitee Electrical power generation from nuclear reactor produced beta rays
US2741593A (en) * 1945-11-06 1956-04-10 Herbert E Metcalf Fluid cooled neutronic reactor
US2798848A (en) * 1951-07-13 1957-07-09 Kenneth H Kingdon Neutronic reactor fuel element
FR1078563A (fr) * 1953-03-31 1954-11-19 Perfectionnements apportés aux générateurs thermiques, notamment à ceux pour la propulsion d'aérodynes
BE529536A (en:Method) * 1953-06-12 1900-01-01
US2852456A (en) * 1953-11-17 1958-09-16 Elmer J Wade Neutronic reactor
DE1011594B (de) * 1955-03-05 1957-07-04 Quartz & Silice Soc Verfahren zur Herstellung von Quarzglas
NL103807C (en:Method) * 1955-07-27
DE1004744B (de) 1955-08-26 1957-03-21 Babcock & Wilcox Dampfkessel Mit Schutzhuelle versehener Uranstab fuer Kernreaktoren
BE550598A (en:Method) * 1955-08-26
US2948517A (en) * 1956-01-05 1960-08-09 Martin Co Tube bundle assembly
DE1010660B (de) * 1956-04-19 1957-06-19 Siemens Ag Schutzhuelse fuer Spaltstoffelemente von Kernreaktoren
BE559844A (en:Method) * 1956-08-06
NL220915A (en:Method) * 1956-09-27 1900-01-01
BE560063A (en:Method) * 1956-10-26
NL128573C (en:Method) * 1956-11-30
DE1033807B (de) * 1957-03-02 1958-07-10 Siemens Ag Uranbrennstoff fuer heterogene oder homogene Kernreaktoren
GB831679A (en) * 1957-05-21 1960-03-30 Norton Grinding Wheel Co Ltd Ceramic nuclear fuel element
CH348476A (de) * 1957-05-31 1960-08-31 Escher Wyss Ag Spaltstoffelement
GB847125A (en) * 1957-06-24 1960-09-07 Atomic Energy Authority Uk Improvements in or relating to fuel elements for nuclear reactors
DE1068821B (en:Method) * 1957-09-12 1959-11-12
BE571786A (en:Method) * 1957-10-16
US3039947A (en) * 1957-12-16 1962-06-19 Fortescue Peter Fuel elements for nuclear reactors
US3079316A (en) * 1958-05-22 1963-02-26 Minnesota Mining & Mfg Thermally resistant articles and method for their fabrication
NL242148A (en:Method) * 1958-08-08
US3085059A (en) * 1958-10-02 1963-04-09 Gen Motors Corp Fuel element for nuclear reactors
NL111725C (en:Method) * 1959-01-14
US3009869A (en) * 1959-01-19 1961-11-21 Charles H Bassett Fuel element for nuclear reactors
US2984613A (en) * 1959-04-09 1961-05-16 Charles H Bassett Fuel element for nuclear reactors

Also Published As

Publication number Publication date
DE1217514B (de) 1966-05-26
NL252138A (en:Method) 1964-02-25
FR1238281A (fr) 1960-08-12
GB940856A (en) 1963-11-06
NL262797A (en:Method) 1964-05-25
FR77736E (fr) 1962-04-13
US3179572A (en) 1965-04-20
GB953873A (en) 1964-04-02
FR76850E (fr) 1961-12-08
FR77484E (fr) 1962-03-09
US3252868A (en) 1966-05-24

Similar Documents

Publication Publication Date Title
BE584924A (en:Method)
JPS3622266Y1 (en:Method)
AT219961B (en:Method)
AT219811B (en:Method)
AT218043B (en:Method)
BE575800A (en:Method)
NL254063A (en:Method)
BE592454A (en:Method)
BE574478A (en:Method)
BE586320A (en:Method)
BE503570A (en:Method)
BE570722A (en:Method)
BE567060A (en:Method)
NL252138A (en:Method)
BE559419A (en:Method)
BE576344A (en:Method)
BE576772A (en:Method)
SE300881B (en:Method)
NL6513773A (en:Method)
NL290620A (en:Method)
NL257070A (en:Method)
NL256163A (en:Method)
NL255423A (en:Method)
BE585897A (en:Method)
NL252512A (en:Method)