CA2134264C - Methode pour la production de molybdene-99 et gestion des dechets qui en contiennent - Google Patents

Methode pour la production de molybdene-99 et gestion des dechets qui en contiennent Download PDF

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Publication number
CA2134264C
CA2134264C CA002134264A CA2134264A CA2134264C CA 2134264 C CA2134264 C CA 2134264C CA 002134264 A CA002134264 A CA 002134264A CA 2134264 A CA2134264 A CA 2134264A CA 2134264 C CA2134264 C CA 2134264C
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CA
Canada
Prior art keywords
uranium
target
nitric acid
acid solution
uranium oxide
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
CA002134264A
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English (en)
Other versions
CA2134264A1 (fr
Inventor
William T. Hancox
Jean-Pierre Labrie
Richard J. Harrison
Deonaraine Singh
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
Individual
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 Individual filed Critical Individual
Priority to CA002134264A priority Critical patent/CA2134264C/fr
Priority to AU25592/95A priority patent/AU2559295A/en
Priority to PCT/CA1995/000333 priority patent/WO1996013039A1/fr
Publication of CA2134264A1 publication Critical patent/CA2134264A1/fr
Priority to ZA958980A priority patent/ZA958980B/xx
Application granted granted Critical
Publication of CA2134264C publication Critical patent/CA2134264C/fr
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
    • G21G1/02—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B3/00—Extraction of metal compounds from ores or concentrates by wet processes
    • C22B3/04—Extraction of metal compounds from ores or concentrates by wet processes by leaching
    • C22B3/06—Extraction of metal compounds from ores or concentrates by wet processes by leaching in inorganic acid solutions, e.g. with acids generated in situ; in inorganic salt solutions other than ammonium salt solutions
    • C22B3/065—Nitric acids or salts thereof
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B34/00—Obtaining refractory metals
    • C22B34/30—Obtaining chromium, molybdenum or tungsten
    • C22B34/34—Obtaining molybdenum
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/14—Processing by incineration; by calcination, e.g. desiccation
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
    • G21G1/04—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes outside nuclear reactors or particle accelerators
    • 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
    • Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P10/00—Technologies related to metal processing
    • Y02P10/20—Recycling

Landscapes

  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Organic Chemistry (AREA)
  • General Chemical & Material Sciences (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Geology (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Plasma & Fusion (AREA)
  • Environmental & Geological Engineering (AREA)
  • Geochemistry & Mineralogy (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Inorganic Chemistry (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

Il est proposé un procédé de production de Mo-99 à partir d'uranium-235 et de gestion des déchets qui en résultent. Ledit procédé consiste à séparer le Mo-99 de l'uranium irradié et à solidifier les déchets résultant de cette séparation. En raison de la forte réduction de la quantité de déchets produite par ce procédé par rapport aux procédés antérieurs, ce procédé est particulièrement utile dans la production de Mo-99 à grande échelle. En outre, le présent procédé entraîne un temps de traitement réduit par rapport aux procédés antérieurs et entraîne donc une réduction de la perte de Mo-99 par désintégration.
CA002134264A 1994-10-25 1994-10-25 Methode pour la production de molybdene-99 et gestion des dechets qui en contiennent Expired - Lifetime CA2134264C (fr)

Priority Applications (4)

Application Number Priority Date Filing Date Title
CA002134264A CA2134264C (fr) 1994-10-25 1994-10-25 Methode pour la production de molybdene-99 et gestion des dechets qui en contiennent
AU25592/95A AU2559295A (en) 1994-10-25 1995-06-07 Process for production of molybdenum-99 and management of waste therefrom
PCT/CA1995/000333 WO1996013039A1 (fr) 1994-10-25 1995-06-07 Procede de production de molybdene-99 et de gestion des dechets qui en resultent
ZA958980A ZA958980B (en) 1994-10-25 1995-10-24 Process for production of molybdenum-99 and management of waste therefrom

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CA002134264A CA2134264C (fr) 1994-10-25 1994-10-25 Methode pour la production de molybdene-99 et gestion des dechets qui en contiennent

Publications (2)

Publication Number Publication Date
CA2134264A1 CA2134264A1 (fr) 1995-10-13
CA2134264C true CA2134264C (fr) 2000-09-12

Family

ID=4154518

Family Applications (1)

Application Number Title Priority Date Filing Date
CA002134264A Expired - Lifetime CA2134264C (fr) 1994-10-25 1994-10-25 Methode pour la production de molybdene-99 et gestion des dechets qui en contiennent

Country Status (4)

Country Link
AU (1) AU2559295A (fr)
CA (1) CA2134264C (fr)
WO (1) WO1996013039A1 (fr)
ZA (1) ZA958980B (fr)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2282478B (en) * 1993-10-01 1997-08-13 Us Energy Method of fabricating 99Mo production targets using low enriched uranium
US9997267B2 (en) * 2013-02-13 2018-06-12 Battelle Memorial Institute Nuclear reactor target assemblies, nuclear reactor configurations, and methods for producing isotopes, modifying materials within target material, and/or characterizing material within a target material
JP7310736B2 (ja) * 2020-07-02 2023-07-19 Ｊｆｅエンジニアリング株式会社 精製装置

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3940318A (en) * 1970-12-23 1976-02-24 Union Carbide Corporation Preparation of a primary target for the production of fission products in a nuclear reactor
CN85109328B (zh) * 1985-12-26 1986-11-05 中国原子能科学研究院 从铀-235及其裂变产物中分离医用钼-99的方法
US4839133A (en) * 1987-10-26 1989-06-13 The United States Of America As Represented By The Department Of Energy Target and method for the production of fission product molybdenum-99

Also Published As

Publication number Publication date
CA2134264A1 (fr) 1995-10-13
AU2559295A (en) 1996-05-15
ZA958980B (en) 1996-05-23
WO1996013039A1 (fr) 1996-05-02

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