US3343947A - Ternary uranium alloys containing molybdenum with niobium or zirconium for use with nuclear reactors - Google Patents

Ternary uranium alloys containing molybdenum with niobium or zirconium for use with nuclear reactors Download PDF

Info

Publication number
US3343947A
US3343947A US466834A US46683465A US3343947A US 3343947 A US3343947 A US 3343947A US 466834 A US466834 A US 466834A US 46683465 A US46683465 A US 46683465A US 3343947 A US3343947 A US 3343947A
Authority
US
United States
Prior art keywords
molybdenum
niobium
uranium
weight
alloys
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 - Lifetime
Application number
US466834A
Other languages
English (en)
Inventor
Fizzotti Carlo
Dalmastri Benito
Masperoni Alberto
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.)
Agenzia Nazionale per le Nuove Tecnologie lEnergia e lo Sviluppo Economico Sostenibile ENEA
Original Assignee
Comitato Nazionale per lEnergia Nucleare CNEN
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 Comitato Nazionale per lEnergia Nucleare CNEN filed Critical Comitato Nazionale per lEnergia Nucleare CNEN
Application granted granted Critical
Publication of US3343947A publication Critical patent/US3343947A/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Classifications

    • 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
    • G21C3/60Metallic fuel; Intermetallic dispersions
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22CALLOYS
    • C22C43/00Alloys containing radioactive materials
    • 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
    • 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
    • Y10TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10STECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00Induced nuclear reactions: processes, systems, and elements
    • Y10S376/90Particular material or material shapes for fission reactors
    • Y10S376/901Fuel

Definitions

  • This invention relates to uranium alloys. Particular alloys are herein described together with their heat treatments which have been developed by the inventors with the purpose of preventing in the fuel elements any preferential orientation, any coarse grains and any particular structure which during the research work proved to be undesirable; all these imperfections at the moment in which the fuel is employed in a nuclear reactor would result in dimensional modifications which are known under the name of growth under irradiation or would produce a rough surface of the element.
  • Molybdenum added to uranium as an alloying element, is effective for producing ,a fine grains structure as a result of appropriate heat treatments; but, due to its large neutron absorbing cross section, it must be employed as an alloy component at the lowest possible percentage.
  • the inventors have also found that structures of uranium alloys with zirconium are not sufficiently thermally stable.
  • the alloys after casting in the form of unrefined bars show grains the size of which ranges from 100 to 175 a.
  • a better refinement and more homogeneous grains can be obtained by heating again the alloy in the 7 phase (e.g. 900 C.) and subsequently cooling it at the rate of to 80 C. per minute. At a cooling rate lower than 5 C. per minute, rather coarse grains and lamellar structures are produced. At a cooling rate greater than 80 C. per minute, both a refinement of the grains and a finer lamellar structure are obtained; however the structures so produced are much less thermally stable (e.g. when subjected to a subsequent extended heating at 550 C.) than those obtained through a cooling rate ranging from 5 to 80 C. per minute.
  • the heat treatments of ternary alloy bar conforming to the above specifications give a structure with or. grains the size of which ranges from 20 to 100 depending on the cooling rate.
  • uranium alloys are prepared by melting a uranium ingot, together with a basic alloy, in a graphite crucible to which a lining of electro-melted magnesium oxide has been applied by centrifugal casting.
  • the basic alloy is produced by melting uranium together with molybdenum and niobium or zirconium in 3,343,947 Patented Sept. 26, 1967 "ice an arc furnace and casting an ingot containing from 6 to 10% by weight of alloying elements.
  • the furnace charge for producing the uranium alloys of this invention is melted by means of high frequency induction heating in vacuum.
  • the product is kept in the melted state inside the crucible at 1,300'1,400 C. for 30 minutes and then is cast in a graphite chill to which a lining of electro-melted magnesium oxide has been applied by centrifugal casting and thereafter it is left to cool in the chill.
  • uranium alloys bars are obtained the diameters of which range from 26 to 33 mm. and which are up to 1,000 mm. long.
  • the size of the a grains ranged from to g.
  • the size of the on grains in the unrefined cast bars can be modified within a fairly wide range, by means of a heat treatment consisting of heating the alloy up to a high temperature (e.g. 900 C.) and subsequently cooling it in a continuous way at the rate of 5 to 80 C. per minute.
  • the treatment is carried out eiher in vacuum or in an inert atmosphere (as in argon) and, as already stated, it gives a structure of which the grain size ranges from 20 to 1001.1. depending on the cooling rate.
  • a bar which has undergone the above heat treatment is free from the preferential orientations and the remarkable distortions which generally occur in the case of a very sharp cooling as for instance in a quenching.
  • niobium (c) 0.3% by weight molybdenum and 2.0% by weight zirconium Heating in 7 phase (at 900 C.) during two hours in vacuum. Cooling at the rate of 60 C. per minute in vacuum. Average size of the a grains after heat treating:
  • Uranium-molybdenum-niobium alloys having a fine grain structure after casting, said alloys having a molybdenum content from 0.1 to 0.3% by Weight and a niobium content from 0.6 to 0.8% by weight, the remainder of said alloy being substantially composed of uranium.
  • a uranium-molybdenurn-niobium alloy having a fine grain structure after casting; said alloy having a molybdenum content of 0.5 by Weight and a niobium content of 0.5% by weight, the remainder of said alloy being substantially composed of uranium.
  • Uranium-molybdenum-zirconium alloys having a fine grain structure after casting, said alloys having a molybdenum content from 0.2 to 0.4% by weight and a zirconium content from 1.5 to 2.2% by weight, the remainder of said alloys being substantially composed of uranium.

Landscapes

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Dispersion Chemistry (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Mechanical Engineering (AREA)
  • Materials Engineering (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Manufacture And Refinement Of Metals (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
US466834A 1965-01-29 1965-06-24 Ternary uranium alloys containing molybdenum with niobium or zirconium for use with nuclear reactors Expired - Lifetime US3343947A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
IT166065 1965-01-29

Publications (1)

Publication Number Publication Date
US3343947A true US3343947A (en) 1967-09-26

Family

ID=11101859

Family Applications (1)

Application Number Title Priority Date Filing Date
US466834A Expired - Lifetime US3343947A (en) 1965-01-29 1965-06-24 Ternary uranium alloys containing molybdenum with niobium or zirconium for use with nuclear reactors

Country Status (7)

Country Link
US (1) US3343947A (fr)
BE (1) BE665642A (fr)
DE (1) DE1483196A1 (fr)
FR (1) FR1454421A (fr)
GB (1) GB1097904A (fr)
LU (1) LU48886A1 (fr)
NL (1) NL6507129A (fr)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3545966A (en) * 1968-02-27 1970-12-08 Etude La Realisation De Combus Manufacture of improved nuclear fuels
US5978432A (en) * 1998-04-17 1999-11-02 Korea Atomic Energy Research Institute Dispersion fuel with spherical uranium alloy, and the fuel fabrication process
EP1345239A1 (fr) * 2002-03-11 2003-09-17 Urenco Nederland B.V. Combustible nucléaire comprenant un alliage Uranium-Molybdène

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB784882A (en) * 1955-06-07 1957-10-16 Atomic Energy Authority Uk Improvements in or relating to uranium alloys
GB809597A (en) * 1955-06-03 1959-02-25 Atomic Energy Authority Uk Improvements in or relating to uranium alloys
US2888343A (en) * 1955-10-11 1959-05-26 Westinghouse Electric Corp Alloys and members produced therefrom
DE1152267B (de) * 1955-06-14 1963-08-01 Commissariat Energie Atomique Ternaere Uranlegierung und Verfahren zur Herstellung und Waermebehandlung derselben
FR1381990A (fr) * 1964-02-10 1964-12-14 Atomic Energy Authority Uk Alliages d'uranium
GB983803A (en) * 1964-02-11 1965-02-17 Atomic Energy Authority Uk Improvements in or relating to uranium alloys

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB809597A (en) * 1955-06-03 1959-02-25 Atomic Energy Authority Uk Improvements in or relating to uranium alloys
GB784882A (en) * 1955-06-07 1957-10-16 Atomic Energy Authority Uk Improvements in or relating to uranium alloys
DE1152267B (de) * 1955-06-14 1963-08-01 Commissariat Energie Atomique Ternaere Uranlegierung und Verfahren zur Herstellung und Waermebehandlung derselben
US2888343A (en) * 1955-10-11 1959-05-26 Westinghouse Electric Corp Alloys and members produced therefrom
FR1381990A (fr) * 1964-02-10 1964-12-14 Atomic Energy Authority Uk Alliages d'uranium
GB983803A (en) * 1964-02-11 1965-02-17 Atomic Energy Authority Uk Improvements in or relating to uranium alloys

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3545966A (en) * 1968-02-27 1970-12-08 Etude La Realisation De Combus Manufacture of improved nuclear fuels
US5978432A (en) * 1998-04-17 1999-11-02 Korea Atomic Energy Research Institute Dispersion fuel with spherical uranium alloy, and the fuel fabrication process
EP1345239A1 (fr) * 2002-03-11 2003-09-17 Urenco Nederland B.V. Combustible nucléaire comprenant un alliage Uranium-Molybdène
US20030223530A1 (en) * 2002-03-11 2003-12-04 Urenco Nederland B.V. Method of providing a nuclear fuel and a fuel element provided by such a method
US7187744B2 (en) * 2002-03-11 2007-03-06 Urenco Nederland B.V. Method of providing a nuclear fuel and a fuel element provided by such a method
US7978808B1 (en) 2002-03-11 2011-07-12 Urenco Nederland B.V. Method of providing a nuclear fuel and a fuel element provided by such a method

Also Published As

Publication number Publication date
NL6507129A (fr) 1966-08-01
GB1097904A (en) 1968-01-03
DE1483196A1 (de) 1969-10-09
LU48886A1 (fr) 1965-08-23
FR1454421A (fr) 1966-10-07
BE665642A (fr) 1965-10-18

Similar Documents

Publication Publication Date Title
US9099205B2 (en) Zirconium alloys for a nuclear fuel cladding having a superior oxidation resistance in a reactor accident condition, zirconium alloy nuclear fuel claddings prepared by using thereof and methods of preparing the same
CN108218456B (zh) 一种高安全性二氧化铀核燃料芯块的制备方法
US9202597B2 (en) Zirconium alloys for a nuclear fuel cladding having a superior corrosion resistance by reducing an amount of alloying elements and methods of preparing a zirconium alloy nuclear fuel cladding using thereof
US4865645A (en) Nuclear radiation metallic absorber
US3343947A (en) Ternary uranium alloys containing molybdenum with niobium or zirconium for use with nuclear reactors
Chiswik et al. Advances in the physical metallurgy of uranium and its alloys
US3425826A (en) Purification of vanadium and columbium (niobium)
US3346673A (en) Formation of submicorn uranium carbide particles in metallic uranium
US3720752A (en) Massive metal hydride structures and methods for their preparation
US3545966A (en) Manufacture of improved nuclear fuels
US4023992A (en) Uranium-base alloys
US3177069A (en) Methods of manufacturing fissionable materials for use in nuclear reactors
US3782924A (en) Fine-grained zirconium-base material
US3620852A (en) Process for producing cobalt alloys
Vatulin et al. High-density U-Mo fuel for research reactors
CN108251689A (zh) 具备高温热稳定性的耐腐蚀Pb-Li-Zr铅锂合金
US3285737A (en) Nuclear fuel materials
GB821639A (en) Improvements in fissionable materials for use in nuclear reactors and in the methodsof manufacturing such materials
US3306733A (en) Uranium-molybdenum alloy containing small amounts of other metals
US2951801A (en) Neutronic reaction fuel
US9111650B2 (en) Zirconium alloys for a nuclear fuel cladding having a superior oxidation resistance in a severe reactor operation condition and methods of preparing a zirconium alloy nuclear cladding by using thereof
US2961359A (en) Hydrided lithium-magnesium alloys and method
CN112941367A (zh) 一种纳米氧化物弥散增强耐热锆合金及其制备方法
US2929706A (en) Delta phase plutonium alloys
US2926113A (en) Heat treated u-mo alloy