CA1109663A - Methode de traitement d'une combustible nucleaire en particules - Google Patents

Methode de traitement d'une combustible nucleaire en particules

Info

Publication number
CA1109663A
CA1109663A CA293,779A CA293779A CA1109663A CA 1109663 A CA1109663 A CA 1109663A CA 293779 A CA293779 A CA 293779A CA 1109663 A CA1109663 A CA 1109663A
Authority
CA
Canada
Prior art keywords
composition
ammonium
uranium
agglomerates
fluoride
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
CA293,779A
Other languages
English (en)
Inventor
William R. Dehollander
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.)
General Electric Co
Original Assignee
General Electric Co
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 General Electric Co filed Critical General Electric Co
Priority to CA293,779A priority Critical patent/CA1109663A/fr
Application granted granted Critical
Publication of CA1109663A publication Critical patent/CA1109663A/fr
Expired legal-status Critical Current

Links

Landscapes

  • Inorganic Compounds Of Heavy Metals (AREA)
CA293,779A 1977-12-22 1977-12-22 Methode de traitement d'une combustible nucleaire en particules Expired CA1109663A (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CA293,779A CA1109663A (fr) 1977-12-22 1977-12-22 Methode de traitement d'une combustible nucleaire en particules

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CA293,779A CA1109663A (fr) 1977-12-22 1977-12-22 Methode de traitement d'une combustible nucleaire en particules

Publications (1)

Publication Number Publication Date
CA1109663A true CA1109663A (fr) 1981-09-29

Family

ID=4110371

Family Applications (1)

Application Number Title Priority Date Filing Date
CA293,779A Expired CA1109663A (fr) 1977-12-22 1977-12-22 Methode de traitement d'une combustible nucleaire en particules

Country Status (1)

Country Link
CA (1) CA1109663A (fr)

Similar Documents

Publication Publication Date Title
US3168369A (en) Uranium processing
US4234550A (en) Method for treating a particulate nuclear fuel material
KR100287326B1 (ko) 산화물 핵연료 소결체의 불량품을 재활용 하는 방법
US4112055A (en) Method of fabrication of uranium oxide UO2 by the dry processing route and a device for the practical application of the method
Lerch et al. Nuclear fuel conversion and fabrication chemistry
RU2081063C1 (ru) Способ получения топливных урановых таблеток (варианты)
US3275564A (en) Process of fabrication of sintered compounds based on uranium and plutonium
CA1109663A (fr) Methode de traitement d'une combustible nucleaire en particules
US2905528A (en) Method for preparation of uo2 particles
US3671453A (en) Process for preparing multi-component nuclear fuels
US3272602A (en) Method of producing uranium dioxide powder
US3046090A (en) Production of uranium monocarbide
US3037839A (en) Preparation of uo for nuclear reactor fuel pellets
Cordfunke et al. Particle properties and sintering behaviour of uranium dioxide
US3477830A (en) Production of sinterable uranium dioxide
US3860691A (en) Actinide mononitride microspheres and process
US3819804A (en) Conversion of uranium hexafluoride to uranium dioxide structures of controlled density and grain size
US3761546A (en) Method of making uranium dioxide bodies
US2952535A (en) Sintering metal oxides
El-Fekey et al. Solid phase decomposition of ammonium uranate
US3846520A (en) Sintering of sol-gel material
JP2671265B2 (ja) ウランおよび/またはプルトニウムの窒化物の製造方法
US20020005597A1 (en) Dry recycle process for recovering UO2 scrap material
RU2098870C1 (ru) Топливная композиция для реакторов на быстрых нейтронах и способ ее получения
US3168371A (en) Process for producing high density urania fuel elements

Legal Events

Date Code Title Description
MKEX Expiry