CA1062451A - Fabrication method for mixed oxide fuel - Google Patents

Fabrication method for mixed oxide fuel

Info

Publication number
CA1062451A
CA1062451A CA248,903A CA248903A CA1062451A CA 1062451 A CA1062451 A CA 1062451A CA 248903 A CA248903 A CA 248903A CA 1062451 A CA1062451 A CA 1062451A
Authority
CA
Canada
Prior art keywords
fuel
coarse
fraction
oxide
fabrication method
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
CA248,903A
Other languages
English (en)
French (fr)
Inventor
Melville A. Feraday
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.)
Atomic Energy of Canada Ltd AECL
Original Assignee
Atomic Energy of Canada Ltd AECL
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 Atomic Energy of Canada Ltd AECL filed Critical Atomic Energy of Canada Ltd AECL
Priority to CA248,903A priority Critical patent/CA1062451A/en
Priority to SE7701018A priority patent/SE7701018L/xx
Priority to FR7704957A priority patent/FR2345790A1/fr
Priority to GB8572/77A priority patent/GB1545658A/en
Application granted granted Critical
Publication of CA1062451A publication Critical patent/CA1062451A/en
Expired legal-status Critical Current

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C04CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04BLIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B38/00Porous mortars, concrete, artificial stone or ceramic ware; Preparation thereof
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C21/00Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G21C21/02Manufacture of fuel elements or breeder elements contained in non-active casings
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/58Solid reactor fuel Pellets made of fissile material
    • G21C3/62Ceramic fuel
    • G21C3/623Oxide fuels
    • 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

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Chemical & Material Sciences (AREA)
  • Ceramic Engineering (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Structural Engineering (AREA)
  • Organic Chemistry (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
CA248,903A 1976-03-26 1976-03-26 Fabrication method for mixed oxide fuel Expired CA1062451A (en)

Priority Applications (4)

Application Number Priority Date Filing Date Title
CA248,903A CA1062451A (en) 1976-03-26 1976-03-26 Fabrication method for mixed oxide fuel
SE7701018A SE7701018L (sv) 1976-03-26 1977-02-01 Sett att framstella ett blandoxidbrensle
FR7704957A FR2345790A1 (fr) 1976-03-26 1977-02-21 Procede de fabrication d'un combustible nucleaire a base d'oxydes mixtes
GB8572/77A GB1545658A (en) 1976-03-26 1977-03-01 Fabrication method for mixed oxide nuclear fuel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CA248,903A CA1062451A (en) 1976-03-26 1976-03-26 Fabrication method for mixed oxide fuel

Publications (1)

Publication Number Publication Date
CA1062451A true CA1062451A (en) 1979-09-18

Family

ID=4105562

Family Applications (1)

Application Number Title Priority Date Filing Date
CA248,903A Expired CA1062451A (en) 1976-03-26 1976-03-26 Fabrication method for mixed oxide fuel

Country Status (4)

Country Link
CA (1) CA1062451A (enrdf_load_stackoverflow)
FR (1) FR2345790A1 (enrdf_load_stackoverflow)
GB (1) GB1545658A (enrdf_load_stackoverflow)
SE (1) SE7701018L (enrdf_load_stackoverflow)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB9901284D0 (en) * 1999-01-22 1999-03-10 British Nuclear Fuels Plc Fuel fabrication
RU2202130C2 (ru) * 2001-05-21 2003-04-10 Открытое акционерное общество "Машиностроительный завод" Способ изготовления таблеток ядерного топлива

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3789013A (en) * 1967-09-25 1974-01-29 Grace W R & Co Process for preparing multi-component nuclear fuels
GB1159520A (en) * 1967-09-25 1969-07-30 Grace W R & Co Process for preparing multi-component nuclear fuels
CA872722A (en) * 1968-06-17 1971-06-08 Pawliw John Preparation of mixed oxide nuclear fuel
BE813383A (fr) * 1974-04-05 1974-07-31 Procede de fabrication de combustible nucleaire mixte

Also Published As

Publication number Publication date
SE7701018L (sv) 1977-09-27
GB1545658A (en) 1979-05-10
FR2345790B1 (enrdf_load_stackoverflow) 1980-04-25
FR2345790A1 (fr) 1977-10-21

Similar Documents

Publication Publication Date Title
US3081249A (en) Process of making a nuclear fuel element
Lucuta et al. Microstructural features of SIMFUEL—Simulated high-burnup UO2-based nuclear fuel
US4020131A (en) Preparation of mixed oxide nuclear fuel
US20120228788A1 (en) Method for preparing a porous nuclear fuel based on at least one minor actinide
US3263004A (en) Process of making a sintered, homogeneous dispersion of nuclear fuel and burnable poison
KR102626243B1 (ko) SiC 및 흑연 매트릭스 TRISO-포함 페블 연료의 신속한 처리를 위한 공정
US4566989A (en) Burnable neutron absorbers
CA1107054A (en) Process for the production of ceramic plutonium uranium nuclear fuel in the form of sintered pellets
ES8900077A1 (es) Procedimiento de fabricacion de pellets combustibles
Mayer et al. On the valency state of americium in (U0. 5Am0. 5) O2− x
US3035895A (en) Preparation of high-density, compactible thorium oxide particles
Song et al. Sintering of mixed UO2 and U3O8 powder compacts
CA1062451A (en) Fabrication method for mixed oxide fuel
Hung et al. The UO2 ex-ADU powder preparation and pellet sintering for optimum efficiency: experimental and modeling studies
Matzke et al. Incorporation of transuranic elements in titanate nuclear waste ceramics
US3320178A (en) Process for making nuclear fuel material
Allen et al. Linear ordering of oxygen clusters in hyperstoicheiometric uranium dioxide
CA1169643A (en) Method for producing mixed-oxide nuclear fuel pellets soluble in nitric acid
US3168601A (en) Process for the production of plutonium oxide-containing nuclear fuel compacts
US3564081A (en) Process for preparation of ceramics of fissionable materials
Song et al. Densification behavior of U3O8 powder compacts by dilatometry
GB1182080A (en) Nuclear Fuel
US3102850A (en) Method of preparing a ceramic fuel element
US3657137A (en) Nuclear fuel comprising uranium dioxide in a porous ceramic oxide matrix
US3362914A (en) Uranium carbide-plutonium phosphide as a reactor fuel