EP0033091A1 - Procédé de purification d'une solution d'uranium/plutonium contenant de l'acide nitrique - Google Patents

Procédé de purification d'une solution d'uranium/plutonium contenant de l'acide nitrique Download PDF

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Publication number
EP0033091A1
EP0033091A1 EP81100235A EP81100235A EP0033091A1 EP 0033091 A1 EP0033091 A1 EP 0033091A1 EP 81100235 A EP81100235 A EP 81100235A EP 81100235 A EP81100235 A EP 81100235A EP 0033091 A1 EP0033091 A1 EP 0033091A1
Authority
EP
European Patent Office
Prior art keywords
solution
plutonium
impurities
americium
acid
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.)
Granted
Application number
EP81100235A
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German (de)
English (en)
Other versions
EP0033091B1 (fr
Inventor
Volker Dr. Schneider
Gerhard Margraf
Wolf-Günther Dr. Druckenbrodt
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.)
Alkem GmbH
Original Assignee
Alkem GmbH
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 Alkem GmbH filed Critical Alkem GmbH
Publication of EP0033091A1 publication Critical patent/EP0033091A1/fr
Application granted granted Critical
Publication of EP0033091B1 publication Critical patent/EP0033091B1/fr
Expired legal-status Critical Current

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    • 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
    • C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02—Obtaining thorium, uranium, or other actinides
    • C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
    • C22B60/0265—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries extraction by solid resins
    • 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
    • C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02—Obtaining thorium, uranium, or other actinides
    • C22B60/04—Obtaining plutonium
    • 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
    • G21F9/12—Processing by absorption; by adsorption; by ion-exchange

Definitions

  • the present invention relates to a method for cleaning a nitric acid U / Pu solution from impurities.
  • Such solutions arise, for example, from the wet scrap return in a fuel element factory. They must be returned to the conversion process, ie the process for the production of nuclear fuels and fuel tablets from U0 2 ' or Pu ° 2.
  • the impurities contained in them which are caused, for example, by the material of the reaction vessel and the pipelines, that is to say are preferably of a metallic nature, must be removed beforehand.
  • the normal contaminants are therefore made of iron and chromium, with plutonium-containing nuclear fuels there is also americium, a decay product of plutonium that arises during the storage of plutonium-containing nuclear fuels, but must not be incorporated as a neutron poison in nuclear fuel tablets that are to be manufactured.
  • impurities are removed from uranium / plutonium solutions by extraction processes. This is usually divided into a uranium and a a plutonium solution.
  • extraction process the use of organic, flammable solvents is necessary, which should be avoided as far as possible in the context of plutonium processing in glove boxes - the risk of fire must be kept as low as possible.
  • Ion exchangers from processes for cleaning plutonium have also been used in many areas. These are mostly anion exchangers that are loaded with strongly nitric acid solutions.
  • the plutonium (IV) in this case is in the form of a nitrato complex and remains in the ion exchange column, while the impurities, e.g. Americium, uranium and heavy metals pass through the column. Uranium and plutonium are thus separated and the plutonium must be eluted again with large amounts of dilute acid.
  • the plutonium (III) with other metal cations is retained in the exchange columns and uranium (IV) as an anion complex passes through the column. Uranium and plutonium are also separated again, which is still loaded with all metallic impurities - as mentioned at the beginning. The plutonium must also be eluted again with large amounts of dilute acid.
  • This solution is now let in via the line 13 into the oxidation container 1, which is provided with a heating device 12.
  • This solution is oxidized in a time of about 30 minutes by heating to 130-150 ° C. and the nitric acid concentration is adjusted.
  • the following compilation shows this nitric acid concentration and the valence levels of the ions contained therein.
  • This oxidized solution is fed via the valve 11 and the line 51 with the aid of a pump 5 to the ion exchange column 4 and the cation exchange resin contained therein (strongly acidic cation exchanger with SO 3 - as functional groups) is designed such that the trivalent heavy metal ions predominantly do not the uranyl and plutonyl ions are adsorbed.
  • the solution running through the opened valve 46 and the line 45 then has the following composition:
  • the running U / Pu solution can be fed directly back into the conversion system.
  • this is eluted in a targeted manner.
  • the ion exchange column 4 is rinsed with 0.5-1 molar nitric acid at medium temperature.
  • the rinsing liquid contains and is supplied from the container 2 via the line 51, the ion exchanger 4 and the opened valve 42 and the line 41 to the evaporator 3.
  • the heating device is not shown for the sake of clarity, since devices of this type are known per se.
  • the rinsing solution is concentrated in this evaporator and reaches the storage container 2 as distillate. From this, it was also removed for the rinsing process of the ion exchange column 4 via the valve 21. This process step involves concentrating the U / Pu ions in the remaining solution, which is then returned via line 32 to the conversion system.
  • this initially discontinuous process can be designed quasi-continuously.
  • the apparatuses are generally state of the art, so that this simple method does not cause any difficulties from this side either.
  • the simple construction of the required equipment also allows it to be installed in glove boxes, as is common in plutonium-processing plants. ,

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  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Manufacturing & Machinery (AREA)
  • Geology (AREA)
  • Materials Engineering (AREA)
  • Environmental & Geological Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Treatment Of Liquids With Adsorbents In General (AREA)
EP81100235A 1980-01-29 1981-01-14 Procédé de purification d'une solution d'uranium/plutonium contenant de l'acide nitrique Expired EP0033091B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE19803003088 DE3003088A1 (de) 1980-01-29 1980-01-29 Verfahren zur reinigung einer salpetersauren u/pu-loesung
DE3003088 1980-01-29

Publications (2)

Publication Number Publication Date
EP0033091A1 true EP0033091A1 (fr) 1981-08-05
EP0033091B1 EP0033091B1 (fr) 1984-06-06

Family

ID=6093162

Family Applications (1)

Application Number Title Priority Date Filing Date
EP81100235A Expired EP0033091B1 (fr) 1980-01-29 1981-01-14 Procédé de purification d'une solution d'uranium/plutonium contenant de l'acide nitrique

Country Status (4)

Country Link
US (1) US4431580A (fr)
EP (1) EP0033091B1 (fr)
JP (1) JPS5716396A (fr)
DE (2) DE3003088A1 (fr)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
MXPA03002981A (es) * 2000-10-05 2004-12-06 Pcs Nitrogen Fertilizer L P Proceso de descontaminacion del yeso.
RU2494484C2 (ru) 2008-05-02 2013-09-27 Шайн Медикал Текнолоджис, Инк. Устройство и способ производства медицинских изотопов
WO2012003009A2 (fr) 2010-01-28 2012-01-05 Shine Medical Technologies, Inc. Chambre de réaction segmentée pour production de radio-isotope
US10734126B2 (en) * 2011-04-28 2020-08-04 SHINE Medical Technologies, LLC Methods of separating medical isotopes from uranium solutions
KR102172861B1 (ko) 2012-04-05 2020-11-02 샤인 메디컬 테크놀로지스, 인크. 수성 집합체 및 제어 방법

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB801743A (en) * 1954-05-18 1958-09-17 Atomic Energy Authority Uk Extraction of plutonium and uranium

Family Cites Families (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB812815A (en) * 1954-12-08 1959-04-29 Permutit Co Ltd Improvements relating to the recovery of uranium from solutions
CA526260A (fr) * 1956-06-12 G. Harvey Bernard Compositions radioactives
US2875024A (en) * 1946-08-27 1959-02-24 Edward R Tompkins Separation of barium values from uranyl nitrate solutions
US2554476A (en) * 1949-01-25 1951-05-22 Louis B Werner Radioactive product and method of producing the same
US3158577A (en) * 1963-06-20 1964-11-24 Lane A Bray Method of treating radioactive waste
DE2244306A1 (de) * 1972-09-09 1974-03-21 Bayer Ag Verfahren zur trennung der actinidenelemente
US3880980A (en) * 1972-11-30 1975-04-29 Allied Chem Recovery of uranium from HCl digested phosphate rock solution
DE2733396C2 (de) * 1977-07-23 1979-09-06 Kernforschungsanlage Juelich Gmbh, 5170 Juelich Verfahren und Vorrichtung zum Beladen von Kernen schwachsaurer Kationenaustauscherharze mit Uranylionen

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB801743A (en) * 1954-05-18 1958-09-17 Atomic Energy Authority Uk Extraction of plutonium and uranium

Also Published As

Publication number Publication date
JPH0128920B2 (fr) 1989-06-06
US4431580A (en) 1984-02-14
JPS5716396A (en) 1982-01-27
DE3162623D1 (en) 1984-07-12
EP0033091B1 (fr) 1984-06-06
DE3003088A1 (de) 1981-07-30

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