DE1764252A1 - Brennstoff fuer Kernreaktoren und gleichmaessig verteilte Neutronenquelle zur Ermittlung der Vervielfachungsquote in Reaktoren und treibenden unterkritischen Gittern - Google Patents

Brennstoff fuer Kernreaktoren und gleichmaessig verteilte Neutronenquelle zur Ermittlung der Vervielfachungsquote in Reaktoren und treibenden unterkritischen Gittern

Info

Publication number
DE1764252A1
DE1764252A1 DE19681764252 DE1764252A DE1764252A1 DE 1764252 A1 DE1764252 A1 DE 1764252A1 DE 19681764252 DE19681764252 DE 19681764252 DE 1764252 A DE1764252 A DE 1764252A DE 1764252 A1 DE1764252 A1 DE 1764252A1
Authority
DE
Germany
Prior art keywords
fuel
californium
nuclear reactors
amount
nuclear
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.)
Pending
Application number
DE19681764252
Other languages
German (de)
English (en)
Inventor
Rokin Maurice A
Porter Charles R
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.)
European Atomic Energy Community Euratom
Original Assignee
European Atomic Energy Community Euratom
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 European Atomic Energy Community Euratom filed Critical European Atomic Energy Community Euratom
Publication of DE1764252A1 publication Critical patent/DE1764252A1/de
Pending legal-status Critical Current

Links

Classifications

    • 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
    • G21C3/42—Selection of substances for use as reactor fuel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/30—Subcritical reactors ; Experimental reactors other than swimming-pool reactors or zero-energy 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
    • Y02E30/30—Nuclear fission 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00—Induced nuclear reactions: processes, systems, and elements
    • Y10S376/90—Particular material or material shapes for fission reactors
    • Y10S376/901—Fuel
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S422/00—Chemical apparatus and process disinfecting, deodorizing, preserving, or sterilizing
    • Y10S422/903—Radioactive material apparatus

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)
DE19681764252 1967-05-03 1968-05-03 Brennstoff fuer Kernreaktoren und gleichmaessig verteilte Neutronenquelle zur Ermittlung der Vervielfachungsquote in Reaktoren und treibenden unterkritischen Gittern Pending DE1764252A1 (de)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US637042A US3368979A (en) 1967-05-03 1967-05-03 Nuclear fuel composition for multiplication determination in reactors and driving subcritical lattices

Publications (1)

Publication Number Publication Date
DE1764252A1 true DE1764252A1 (de) 1971-07-01

Family

ID=24554306

Family Applications (1)

Application Number Title Priority Date Filing Date
DE19681764252 Pending DE1764252A1 (de) 1967-05-03 1968-05-03 Brennstoff fuer Kernreaktoren und gleichmaessig verteilte Neutronenquelle zur Ermittlung der Vervielfachungsquote in Reaktoren und treibenden unterkritischen Gittern

Country Status (5)

Country Link
US (1) US3368979A (enExample)
BE (1) BE713526A (enExample)
DE (1) DE1764252A1 (enExample)
LU (1) LU55907A1 (enExample)
NL (1) NL6805884A (enExample)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3787321A (en) * 1971-07-01 1974-01-22 Atomic Energy Commission Californium-palladium metal neutron source material
DE3604869A1 (de) * 1986-02-15 1987-08-20 Hochtemperatur Reaktorbau Gmbh Gasgekuehlter kernreaktor mit einer stationaeren schuettung kugelfoermiger betriebselemente

Also Published As

Publication number Publication date
NL6805884A (enExample) 1968-11-04
BE713526A (enExample) 1968-08-16
LU55907A1 (enExample) 1968-07-11
US3368979A (en) 1968-02-13

Similar Documents

Publication Publication Date Title
DE2926051C2 (enExample)
DE69632070T2 (de) Spalt-brut-kernreaktor
DE69014734T2 (de) Verfahren für die Berechnung der Leistungsverteilung im Kern eines Kernkraftreaktors und Verfahren zum Kalibrieren der umgebenden Neutronendetektoren des Kerns eines Kernkraftreaktors.
DE2819734A1 (de) Kernreaktor
Bostelmann Systematic sensitivity and uncertainty analysis of sodium-cooled fast reactor systems
DE1589994A1 (de) Brenn- und Brutelement mit in einer Umhuellung enthaltenen Brenn- und Brutstoffteilchen
DE1279224B (de) Thermischer Kernreaktor
DE102019007597A1 (de) Dual Fluid Reaktor - Variante mit Flüssigmetallspaltstoff (DFR/m)
DE1764252A1 (de) Brennstoff fuer Kernreaktoren und gleichmaessig verteilte Neutronenquelle zur Ermittlung der Vervielfachungsquote in Reaktoren und treibenden unterkritischen Gittern
DE1138169B (de) Atomkernleistungsreaktor mit unterkritischem Kern und aeusserer Neutronenquelle
DE1464625A1 (de) Hochtemperatur-Kernreaktor
DE1909109A1 (de) Kernreaktor mit einer Regelung der Reaktivitaet und Leistungsverteilung ueber abbrennbare Reaktorgifte
EP1595264B1 (de) Verfahren zur messung einer relativen grösse des abbrandes von brennelementen eines kugelhaufen-hochtemperaturreaktors (htr) sowie dazu geeignete vorrichtung
DE10334403A1 (de) Verfahren und Einrichtung zum Berechnen von Heliumprodukten in Komponenten aus rostfreiem Stahl von Kernreaktoren
DE69606537T2 (de) Verfahren zur vernichtung von plutonium mittels bestrahlung in einem leichtwasserreaktor
DE6926252U (de) Vorrichtung zum bestimmen der neutronenabsorptions- und multiplikations- parameter buendelartiger brennstoffelemente
AT338385B (de) Verfahren zur messung der leistungsverteilung in thermischen reaktorkernen
TERRELL An integrated model for time dependent and equilibrium fuel compositions in fast breeder reactors
DE19852761C1 (de) Verfahren und Vorrichtung zur Ermittlung von mindestens einer Strahlendosis außerhalb eines Behälters für radioaktive Strahlungsquellen und Anwendung des Verfahrens zur Prognose von Strahlendosen
DE1028249B (de) Verfahren zur thermischen Bruetung von Plutonium
DE1489919C3 (de) Betriebsverfahren einer Atomkern reaktoranlage mit einem schnellen Brut reaktor und einer Spaltstoffaufberei tungsanlage
DE69131322T2 (de) Herstellung von mox brennstoff für kernreaktor mit thermischen neutronen
DE1166391B (de) Thermischer Kernreaktor
DE2518876C2 (de) Verfahren zur Messung des Abbrandes von Kernbrennstoffen
DE2006300A1 (en) Fuel element for nuclear reactors