GB1015004A - Improvements in or relating to fuel for nuclear reactors - Google Patents

Improvements in or relating to fuel for nuclear reactors

Info

Publication number
GB1015004A
GB1015004A GB42820/63A GB4282063A GB1015004A GB 1015004 A GB1015004 A GB 1015004A GB 42820/63 A GB42820/63 A GB 42820/63A GB 4282063 A GB4282063 A GB 4282063A GB 1015004 A GB1015004 A GB 1015004A
Authority
GB
United Kingdom
Prior art keywords
uranium dioxide
higher oxide
dioxide
uranium
powder
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
GB42820/63A
Inventor
Bernard Robert Steele
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to ES0305432A priority Critical patent/ES305432A1/en
Publication of GB1015004A publication Critical patent/GB1015004A/en
Expired legal-status Critical Current

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • C01G43/01—Oxides; Hydroxides
    • C01G43/025—Uranium dioxide
    • 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
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2004/00—Particle morphology
    • C01P2004/01—Particle morphology depicted by an image
    • C01P2004/03—Particle morphology depicted by an image obtained by SEM
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/10—Solid density
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/12—Surface area
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/88—Isotope composition differing from the natural occurrence
    • 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

Landscapes

  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Geology (AREA)
  • Inorganic Chemistry (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Ceramic Engineering (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

A nuclear fuel body of uranium dioxide, which is suitable for incorporation in nuclear reactor fuel elements, is produced by mixing uranium dioxide powder with powder of a higher oxide of uranium, compacting the mixed powders, and sintering the resulting compact in a reducing atmosphere. The uranium dioxide, which is predominant in the mixture, is of a form which after compaction sinters to a high density. The mixing of the powders is so limited that agglomerates of the higher oxide powder exist in a continuous matrix of the uranium dioxide powder, the higher oxide being reduced to dioxide prior to actual sintering and in so doing shrinking more than does the dioxide originally present, thereby producing a body of high-density uranium dioxide containing discrete regions of internal porosity. Preferably, the surface area of the uranium dioxide is from 2 to 6 square metres per gram and of the higher oxide is from 0.5 to 12 square metres per gram, the higher oxide, which may be U3O8, UO3 or UO4, constituting from 5 to 30% by weight of the mixed powders. Advantageously, the uranium dioxide has a natural U-235 content and the higher oxide is enriched in U-235.
GB42820/63A 1963-10-30 1963-10-30 Improvements in or relating to fuel for nuclear reactors Expired GB1015004A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
ES0305432A ES305432A1 (en) 1963-10-30 1964-10-29 Procedure for the preparation of nuclear fuel elements. (Machine-translation by Google Translate, not legally binding)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
BE655041A BE655041A (en) 1964-10-29 1964-10-29

Publications (1)

Publication Number Publication Date
GB1015004A true GB1015004A (en) 1965-12-31

Family

ID=3847011

Family Applications (1)

Application Number Title Priority Date Filing Date
GB42820/63A Expired GB1015004A (en) 1963-10-30 1963-10-30 Improvements in or relating to fuel for nuclear reactors

Country Status (2)

Country Link
BE (1) BE655041A (en)
GB (1) GB1015004A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE19944984C1 (en) * 1999-09-20 2000-12-21 Siemens Ag Nuclear reactor fuel element pellet comprises central core which is easier to deform than outer region

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
TW359837B (en) * 1996-09-18 1999-06-01 Siemens Ag Nuclear fuel sinter substance, method for manufacturing a nuclear fuel sinter substance and the fuel rod with an encasing tube

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE19944984C1 (en) * 1999-09-20 2000-12-21 Siemens Ag Nuclear reactor fuel element pellet comprises central core which is easier to deform than outer region

Also Published As

Publication number Publication date
BE655041A (en) 1965-04-29

Similar Documents

Publication Publication Date Title
US4020131A (en) Preparation of mixed oxide nuclear fuel
ES350364A1 (en) Process for manufacturing sintered pellets of nuclear fuel
ES8405548A1 (en) Burnable neutron absorbers.
GB1375498A (en)
ES419677A1 (en) Process for controlling end-point density of sintered uranium dioxide nuclear fuel bodies and product
ES473401A1 (en) Method of producing PuO2/UO2/-nuclear fuels
US3375306A (en) Method of producing dense,sintered bodies of uo2 or uo2-puo2 mixtures
GB1285190A (en) Improvements in ceramic fissile materials
ES480546A1 (en) Production of nuclear fuel pellets
GB1015004A (en) Improvements in or relating to fuel for nuclear reactors
ES8703034A1 (en) Method for the manufacture of oxidic nuclear fuel sintered bodies.
GB1053786A (en)
GB913858A (en) Improvements in or relating to ceramic fuel for nuclear reactors
GB1034505A (en) Improvements in or relating to sintered uranium-plutonium compounds
GB1334391A (en) Nuclear fuels
GB1079427A (en) Improvements in nuclear reactors
ES299210A1 (en) Method of preparation of nuclear combustible elements (Machine-translation by Google Translate, not legally binding)
GB1017187A (en) Preparation of dense uranium oxide
ES309178A1 (en) Method of preparation of mixed oxides of actinides
US3609095A (en) Uranium dioxide article and method of producing the same
JP2981580B2 (en) Manufacturing method of nuclear fuel assembly
US3168371A (en) Process for producing high density urania fuel elements
GB1371595A (en) Manufacturing process for mixed nuclear fuel pellets
GB2020641A (en) Nuclear fuel pellets containing niobium pentoxide
GB1079042A (en) Improvements in or relating to sintering refractory materials