FR2483673B1 - Procede de traitement de pastilles de combustible nucleaire renfermant une matiere fissile - Google Patents

Procede de traitement de pastilles de combustible nucleaire renfermant une matiere fissile

Info

Publication number
FR2483673B1
FR2483673B1 FR8110810A FR8110810A FR2483673B1 FR 2483673 B1 FR2483673 B1 FR 2483673B1 FR 8110810 A FR8110810 A FR 8110810A FR 8110810 A FR8110810 A FR 8110810A FR 2483673 B1 FR2483673 B1 FR 2483673B1
Authority
FR
France
Prior art keywords
nuclear fuel
fuel pellets
pellets containing
fissile material
treating 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
FR8110810A
Other languages
English (en)
French (fr)
Other versions
FR2483673A1 (fr
Inventor
Richard Conrad Hoyt
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.)
Boeing North American Inc
Original Assignee
Rockwell International Corp
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 Rockwell International Corp filed Critical Rockwell International Corp
Publication of FR2483673A1 publication Critical patent/FR2483673A1/fr
Application granted granted Critical
Publication of FR2483673B1 publication Critical patent/FR2483673B1/fr
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements 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
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/48—Non-aqueous processes
    • 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
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G21C3/60—Metallic fuel; Intermetallic dispersions
    • 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
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G21C3/62—Ceramic fuel
    • G21C3/623—Oxide fuels
    • 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00—Technologies for solid waste management
    • Y02W30/50—Reuse, recycling or recovery technologies

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Dispersion Chemistry (AREA)
  • Ceramic Engineering (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
FR8110810A 1980-06-02 1981-06-01 Procede de traitement de pastilles de combustible nucleaire renfermant une matiere fissile Expired FR2483673B1 (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US06/155,829 US4331618A (en) 1980-06-02 1980-06-02 Treatment of fuel pellets

Publications (2)

Publication Number Publication Date
FR2483673A1 FR2483673A1 (fr) 1981-12-04
FR2483673B1 true FR2483673B1 (fr) 1988-01-22

Family

ID=22556963

Family Applications (1)

Application Number Title Priority Date Filing Date
FR8110810A Expired FR2483673B1 (fr) 1980-06-02 1981-06-01 Procede de traitement de pastilles de combustible nucleaire renfermant une matiere fissile

Country Status (4)

Country Link
US (1) US4331618A (OSRAM)
JP (1) JPS5723897A (OSRAM)
CA (1) CA1172438A (OSRAM)
FR (1) FR2483673B1 (OSRAM)

Families Citing this family (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4663110A (en) * 1982-03-12 1987-05-05 Ga Technologies Inc. Fusion blanket and method for producing directly fabricable fissile fuel
FR2590068B1 (fr) * 1985-11-08 1987-12-11 Novatome Procede de recyclage de pastilles de combustible nucleaire precedemment irradiees dans un reacteur nucleaire a neutrons rapides
US5041193A (en) * 1989-09-29 1991-08-20 Rockwell International Corporation Acitnide recovery
US5597538A (en) * 1995-05-19 1997-01-28 Atomic Energy Of Canada Limited Process to remove rare earths from spent nuclear fuel
KR100293482B1 (ko) * 1998-09-08 2001-07-12 이종훈 핵연료소결체의제조방법
KR100922565B1 (ko) 2007-10-12 2009-10-21 한국원자력연구원 이중 구조 가연성 흡수 핵연료 소결체 재활용을 위한소결체 분말 분리방법
US9799414B2 (en) 2010-09-03 2017-10-24 Atomic Energy Of Canada Limited Nuclear fuel bundle containing thorium and nuclear reactor comprising same
WO2012065249A1 (en) 2010-11-15 2012-05-24 Atomic Energy Of Canada Limited Nuclear fuel containing a neutron absorber
KR102249126B1 (ko) 2010-11-15 2021-05-06 아토믹 에너지 오브 캐나다 리미티드 재생된 감손 우라늄을 함유하는 핵연료, 핵연료 다발 및 그것을 포함하는 원자로
JP5944237B2 (ja) * 2012-06-15 2016-07-05 株式会社東芝 核燃料物質の回収方法
EP4679456A2 (en) 2019-05-17 2026-01-14 Metatomic, Inc. Systems for molten salt reactor fuel-salt preparation

Family Cites Families (7)

* 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
SE346048B (OSRAM) * 1968-02-01 1972-06-19 Nukem Gmbh
GB1297158A (OSRAM) * 1969-11-12 1972-11-22
US3752872A (en) * 1971-08-26 1973-08-14 Atomic Energy Commission Method of preparing uniform size powders
US4134941A (en) * 1973-12-14 1979-01-16 Hobeg Hochtemperaturreaktor-Brennelement Gmbh Spherical fuel elements made of graphite for temperature reactors and process for reworking it after the irradiation
FR2358728A1 (fr) * 1976-07-12 1978-02-10 Ishikawajima Harima Heavy Ind Systeme de retraitement de combustible nucleaire
JPS5847039B2 (ja) * 1977-04-01 1983-10-20 石川島播磨重工業株式会社 核燃料の処理方法及び核方法に用いる処理装置

Also Published As

Publication number Publication date
JPS6351517B2 (OSRAM) 1988-10-14
CA1172438A (en) 1984-08-14
FR2483673A1 (fr) 1981-12-04
JPS5723897A (en) 1982-02-08
US4331618A (en) 1982-05-25

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Legal Events

Date Code Title Description
ST Notification of lapse