[go: up one dir, main page]

ES466675A1 - A PROCEDURE FOR RELEASING VOLATILE FISSION PRODUCTS FROM IRRADIATED NUCLEAR FUEL - Google Patents

A PROCEDURE FOR RELEASING VOLATILE FISSION PRODUCTS FROM IRRADIATED NUCLEAR FUEL

Info

Publication number
ES466675A1
ES466675A1 ES466675A ES466675A ES466675A1 ES 466675 A1 ES466675 A1 ES 466675A1 ES 466675 A ES466675 A ES 466675A ES 466675 A ES466675 A ES 466675A ES 466675 A1 ES466675 A1 ES 466675A1
Authority
ES
Spain
Prior art keywords
nuclear fuel
fission products
volatile fission
releasing volatile
irradiated 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.)
Expired
Application number
ES466675A
Other languages
Spanish (es)
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.)
Framatome ANP Richland Inc
Original Assignee
Exxon Nuclear Co Inc
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 Exxon Nuclear Co Inc filed Critical Exxon Nuclear Co Inc
Publication of ES466675A1 publication Critical patent/ES466675A1/en
Expired legal-status Critical Current

Links

Classifications

    • EFIXED CONSTRUCTIONS
    • E21EARTH OR ROCK DRILLING; MINING
    • E21BEARTH OR ROCK DRILLING; OBTAINING OIL, GAS, WATER, SOLUBLE OR MELTABLE MATERIALS OR A SLURRY OF MINERALS FROM WELLS
    • E21B7/00Special methods or apparatus for drilling
    • E21B7/26Drilling without earth removal, e.g. with self-propelled burrowing devices
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42Reprocessing of irradiated fuel
    • G21C19/44Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/48Non-aqueous processes
    • BPERFORMING OPERATIONS; TRANSPORTING
    • B25HAND TOOLS; PORTABLE POWER-DRIVEN TOOLS; MANIPULATORS
    • B25DPERCUSSIVE TOOLS
    • B25D9/00Portable percussive tools with fluid-pressure drive, i.e. driven directly by fluids, e.g. having several percussive tool bits operated simultaneously
    • B25D9/14Control devices for the reciprocating piston
    • B25D9/26Control devices for adjusting the stroke of the piston or the force or frequency of impact thereof
    • EFIXED CONSTRUCTIONS
    • E21EARTH OR ROCK DRILLING; MINING
    • E21BEARTH OR ROCK DRILLING; OBTAINING OIL, GAS, WATER, SOLUBLE OR MELTABLE MATERIALS OR A SLURRY OF MINERALS FROM WELLS
    • E21B4/00Drives for drilling, used in the borehole
    • E21B4/06Down-hole impacting means, e.g. hammers
    • E21B4/14Fluid operated hammers
    • E21B4/145Fluid operated hammers of the self propelled-type, e.g. with a reverse mode to retract the device from the hole
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/30Processing
    • 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
    • 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
    • Y02WCLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00Technologies for solid waste management
    • Y02W30/50Reuse, recycling or recovery technologies

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Mining & Mineral Resources (AREA)
  • Geology (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Fluid Mechanics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Mechanical Engineering (AREA)
  • Environmental & Geological Engineering (AREA)
  • General Engineering & Computer Science (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Geochemistry & Mineralogy (AREA)
  • Automation & Control Theory (AREA)
  • Plasma & Fusion (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)

Abstract

Un procedimiento para desprender productos de fisión volátiles de un combustible nuclear irradiado, que comprende hacer reaccionar aglomerados del combustible nuclear irradiado con un oxidante de óxido de nitrógeno a una temperatura de reacción comprendida entre aproximadamente 325º y 800ºC , durante un periodo de tiempo suficiente para formar un polvo fino, con lo que se desprenden los productos de fisión volátiles.A process for releasing volatile fission products from irradiated nuclear fuel, comprising reacting agglomerates of irradiated nuclear fuel with a nitrogen oxide oxidant at a reaction temperature of from about 325° to 800°C for a period of time sufficient to form a fine powder, releasing volatile fission products.

ES466675A 1977-02-07 1978-02-06 A PROCEDURE FOR RELEASING VOLATILE FISSION PRODUCTS FROM IRRADIATED NUCLEAR FUEL Expired ES466675A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US76614277A 1977-02-07 1977-02-07

Publications (1)

Publication Number Publication Date
ES466675A1 true ES466675A1 (en) 1979-11-16

Family

ID=25075540

Family Applications (1)

Application Number Title Priority Date Filing Date
ES466675A Expired ES466675A1 (en) 1977-02-07 1978-02-06 A PROCEDURE FOR RELEASING VOLATILE FISSION PRODUCTS FROM IRRADIATED NUCLEAR FUEL

Country Status (8)

Country Link
JP (1) JPS6034718B2 (en)
BE (1) BE863675A (en)
DE (1) DE2801744C2 (en)
ES (1) ES466675A1 (en)
FR (1) FR2379884A1 (en)
GB (1) GB1593323A (en)
IT (1) IT1092476B (en)
SE (1) SE429587B (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0439019U (en) * 1990-08-01 1992-04-02
RU2303303C1 (en) * 2005-11-15 2007-07-20 Федеральное государственное унитарное предприятие Научно-исследовательский Институт Научно-производственное объединение "Луч" (ФГУП НИИ НПО "Луч") Method for recovering irradiated nuclear fuel
CN119601275A (en) * 2024-11-18 2025-03-11 中国原子能科学研究院 Method for recovering tritium and zirconium from nuclear fuel cladding

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3140151A (en) * 1959-11-12 1964-07-07 James R Foltz Method of reprocessing uo2 reactor fuel
BE611199A (en) * 1961-12-06 1962-06-06 Ct D Etude De L En Nucleaire Process for the reprocessing of nuclear fuels, which include carbon in their structure and / or in their cladding.
IT1034322B (en) * 1975-03-17 1979-09-10 Agip Nucleare Spa PYROCHEMICAL SEPARATION OF PLUTUS NIUM FROM IRRAYED NUCLEAR FUELS BY THERMODECOMPOSITION IN MELTED NITRATES

Also Published As

Publication number Publication date
DE2801744A1 (en) 1978-08-10
JPS5399196A (en) 1978-08-30
GB1593323A (en) 1981-07-15
JPS6034718B2 (en) 1985-08-10
FR2379884B1 (en) 1984-10-19
DE2801744C2 (en) 1986-12-11
BE863675A (en) 1978-08-07
FR2379884A1 (en) 1978-09-01
IT1092476B (en) 1985-07-12
IT7819802A0 (en) 1978-01-30
SE429587B (en) 1983-09-12
SE7801361L (en) 1978-08-08

Similar Documents

Publication Publication Date Title
BE851670A (en) FUEL BEAM FOR NUCLEAR REACTOR
JPS543687A (en) Fuel subbassembly for nuclear reactor
AU1752676A (en) Cutting a bundle of tubes containing nuclear fuels
JPS5419097A (en) Device for storing irradiated or burned fuel element picked out of highhtemperature nuclear reactor
GB2056055B (en) Measuring the linear heat generation rate of a nuclear reactor fuel pin
IT1131487B (en) DEPURATION PROCEDURE FOR A GAS CONTAINING HYDROGEN SULPHIDE
BE866647A (en) HIGH TEMPERATURE NUCLEAR REACTOR WITH GAS COOLING
ES243076Y (en) GRID FOR NUCLEAR REACTOR FUEL ASSEMBLY.
FR2422230B1 (en) STORAGE CABINET FOR NUCLEAR REACTOR FUEL ELEMENTS
FR1180325A (en) Improvements to fuel cartridges for nuclear reactors
JPS52110395A (en) Nuclear fuel for power reactor
CH409160A (en) Fuel cartridge for nuclear reactor
ES466675A1 (en) A PROCEDURE FOR RELEASING VOLATILE FISSION PRODUCTS FROM IRRADIATED NUCLEAR FUEL
ES454561A1 (en) NUCLEAR REACTOR.
SE432679B (en) Nuclear Reactor Flat Type Fuel Cartridge
IT7968992A0 (en) FUEL ASSEMBLY FOR NUCLEAR REACTORS
JPS5263588A (en) Neutraon source for nuclear reactor
ES8707815A1 (en) Method of coating nuclear fuel with boron nitride.
JPS54152784A (en) Nuclear reactor cooled by highhtemperature gas
BE554737A (en) Fuel for neutron reactor
CH406460A (en) Fuel cartridge for nuclear reactor
FR1223909A (en) Fuel cartridge for nuclear reactor
SE415215B (en) FUEL ELEMENT FOR GAS COOLED NUCLEAR REACTORS.
FR1313868A (en) Device for handling fuel cartridges of a nuclear reactor
JPS53100389A (en) Nuclear fuel for highhgemperature reactor