ES360437A1 - Procedimiento y dispositivo de tratamiento de elementos de combustible ceramico irradiados. - Google Patents

Procedimiento y dispositivo de tratamiento de elementos de combustible ceramico irradiados.

Info

Publication number
ES360437A1
ES360437A1 ES360437A ES360437A ES360437A1 ES 360437 A1 ES360437 A1 ES 360437A1 ES 360437 A ES360437 A ES 360437A ES 360437 A ES360437 A ES 360437A ES 360437 A1 ES360437 A1 ES 360437A1
Authority
ES
Spain
Prior art keywords
fragments
fuel
extension
drum
balls
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
ES360437A
Other languages
English (en)
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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 Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Publication of ES360437A1 publication Critical patent/ES360437A1/es
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
    • 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
    • G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
ES360437A 1967-11-21 1968-11-20 Procedimiento y dispositivo de tratamiento de elementos de combustible ceramico irradiados. Expired ES360437A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR129085 1967-11-21

Publications (1)

Publication Number Publication Date
ES360437A1 true ES360437A1 (es) 1972-01-01

Family

ID=8642040

Family Applications (1)

Application Number Title Priority Date Filing Date
ES360437A Expired ES360437A1 (es) 1967-11-21 1968-11-20 Procedimiento y dispositivo de tratamiento de elementos de combustible ceramico irradiados.

Country Status (10)

Country Link
BE (1) BE722979A (es)
CH (1) CH505443A (es)
DE (1) DE1809163B2 (es)
ES (1) ES360437A1 (es)
FR (1) FR1552176A (es)
GB (1) GB1171257A (es)
IL (1) IL30961A (es)
LU (1) LU57316A1 (es)
RO (1) RO58521A (es)
SE (1) SE337870B (es)

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3103900C2 (de) * 1981-02-05 1984-02-02 Kernforschungsanlage Jülich GmbH, 5170 Jülich Anlage zum Aufbereiten graphitischer Brennelemente von Hochtemperatur-Kernreaktoren
JPS604890A (ja) * 1983-06-23 1985-01-11 株式会社日立製作所 セラミツク核燃料再処理における前処理方法
KR100347107B1 (ko) * 1999-10-28 2002-07-31 한국전력공사 원전연료 펠릿의 탈피복 방법 및 장치
FR3053151B1 (fr) * 2016-06-23 2018-08-10 Commissariat A L'energie Atomique Et Aux Energies Alternatives Procede de dissolution d'un combustible nucleaire
EP3970163A4 (en) 2019-05-17 2023-01-04 Metatomic, Inc. SYSTEMS AND PROCESSES FOR PRODUCTION OF FUEL SALTS FOR MOLTEN SALT REACTORS
US10685753B1 (en) 2019-05-17 2020-06-16 Metatomic, Inc. Systems and methods for fast molten salt reactor fuel-salt preparation

Also Published As

Publication number Publication date
LU57316A1 (es) 1969-02-25
BE722979A (es) 1969-04-01
RO58521A (es) 1975-09-15
DE1809163A1 (de) 1970-03-19
IL30961A0 (en) 1970-01-29
CH505443A (fr) 1971-03-31
IL30961A (en) 1972-07-26
SE337870B (es) 1971-08-23
FR1552176A (es) 1969-01-03
DE1809163B2 (de) 1971-06-16
GB1171257A (en) 1969-11-19

Similar Documents

Publication Publication Date Title
ES360437A1 (es) Procedimiento y dispositivo de tratamiento de elementos de combustible ceramico irradiados.
JPS638438B2 (es)
US3644104A (en) Process for processing canned irradiated ceramic fuel elements
DE1918133A1 (de) Verfahren und Vorrichtung zur Herstellung von gepulvertem Urandioxyd
US3324540A (en) Method for making porous target pellets for a nuclear reactor
Marlowe et al. Tracer study of the surface diffusivity of UO2
US6783706B1 (en) Method for dry process recycling of mixed (U,Pu)O2 oxide nuclear fuel waste
JPS647025B2 (es)
US3714322A (en) Method for preparing high purity 233 uranium
CA1169643A (en) Method for producing mixed-oxide nuclear fuel pellets soluble in nitric acid
GB1219528A (en) Fluoride reprocessing of nuclear fuels
GB1073000A (en) Method for the reprocessing of uranium-containing nuclear fuels
Nichols et al. Radiation exposures in fabricating 233U-Th fuels
GB1198454A (en) Method for Reprocessing Nuclear Fuel
GB986852A (en) Method of preparing uranic oxide in granulated form
Ono et al. Heat capacity of uranium phosphides above room temperature
RU2225047C2 (ru) Способ сухой переработки скрапа ядерного топлива из смешанного оксида (u, pu) o2
GB967568A (en) Fluorination of oxidic nuclear fuel
US3279913A (en) Methods of preparing uranium by magnesiothermy
GB1138578A (en) Heat source material
Odom CONTINUOUS OR SEMICONTINUOUS LEACHER FOR LEACHING SOLUBLE CORE MATERIAL FROM SHEARED SPENT NUCLEAR FUEL TUBES.
GB787971A (en) Improvements in devices for discharging rods of fissionable material from nuclear reactors
Gallon THE PLANT AT BOUCHET
GB1292778A (en) Furnace and method for the pyrochemical processing of nuclear reactor fuel elements
Fleming et al. THE MASS ASSIGNMENT OF THE CHAIN 2 MIN. Sb→ 77.7 HR. Te→ 2.25 HR. I