EP0033091B1 - Verfahren zur Reinigung einer salpetersauren U/Pu-Lösung - Google Patents

Verfahren zur Reinigung einer salpetersauren U/Pu-Lösung Download PDF

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Publication number
EP0033091B1
EP0033091B1 EP81100235A EP81100235A EP0033091B1 EP 0033091 B1 EP0033091 B1 EP 0033091B1 EP 81100235 A EP81100235 A EP 81100235A EP 81100235 A EP81100235 A EP 81100235A EP 0033091 B1 EP0033091 B1 EP 0033091B1
Authority
EP
European Patent Office
Prior art keywords
solution
impurities
plutonium
americium
ions
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
EP81100235A
Other languages
German (de)
English (en)
French (fr)
Other versions
EP0033091A1 (de
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/de
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Classifications

    • 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.
  • solutions arise, for example, in the case of 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 PuO z .
  • the impurities contained in them, the z. B. caused by the material of the reaction vessel and the pipelines, ie are preferably metallic, must be removed beforehand.
  • the normal impurities therefore consist 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 newly manufactured nuclear fuel tablets.
  • impurities are removed from uranium / plutonium solutions by extraction processes. This is usually divided into a uranium and a plutonium solution at the same time.
  • 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) is in this case as a nitrate complex and remains in the ion exchange column, while the impurities, such as. B. Americium, uranium and heavy metals go through the column. Uranium and plutonium are thus separated and the plutonium must be re-mixed with large amounts of dilute acid.
  • the plutonium (111) with all 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 process is of particular interest when processing plutonium in a fuel assembly plant.
  • soluble (U / Pu) 0 2 powders are produced. If an americium content has built up in the material during long-term interim storage of plutonium, which must be separated off before further processing, these powders can be dissolved and cleaned and processed further by the process according to the invention. Manufacturing scrap that has been collected over a longer period of time and may also be contaminated can be dissolved and cleaned using the same procedure.
  • the process can advantageously be used to separate americium from nuclear fuel powders or tablets which have been stored for a very long time.
  • This oxidized solution is fed via valve 11 and line 51 with the help 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 in such a way that predominantly the trivalent heavy metal ions do not 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 to the conversion system.
  • this is eluted in a targeted manner.
  • the ion exchange column 4 is rinsed with 0.5 l malar 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 of the same is not shown for the sake of clarity, since devices of this type are known per se.
  • the rinsing solution is concentrated in this vaporizer and reaches the storage container 2 as distillate. This process step involves concentration of the U / Pu ions in the remaining solution, which is then returned via line 32 to the conversion system.
  • the impurities remain on the ion exchanger column 4. These are then eluted with 1 to 3 molar nitric acid, which was prepared in the tank 2 and was filled into it via the line 25 and the valve 26, and the eluate is fed via the valve 44 and the line 43 to an evaporator 6, the Distillate produced there is fed back to the storage tank 2 via line 62 and the concentrated solution is fed via line 61 either to the americium conversion or to the waste processing known per se. After rinsing with approximately 0.5 molar nitric acid, the ion exchange column 4 is available for a renewed cleaning cycle.
  • this initially discontinuous process can be made quasi-continuous.
  • the apparatuses are state of the art, so that this simple process 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)
  • Manufacturing & Machinery (AREA)
  • Environmental & Geological Engineering (AREA)
  • Geology (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Treatment Of Liquids With Adsorbents In General (AREA)
EP81100235A 1980-01-29 1981-01-14 Verfahren zur Reinigung einer salpetersauren U/Pu-Lösung Expired EP0033091B1 (de)

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 EP0033091A1 (de) 1981-08-05
EP0033091B1 true EP0033091B1 (de) 1984-06-06

Family

ID=6093162

Family Applications (1)

Application Number Title Priority Date Filing Date
EP81100235A Expired EP0033091B1 (de) 1980-01-29 1981-01-14 Verfahren zur Reinigung einer salpetersauren U/Pu-Lösung

Country Status (4)

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

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BR0114467B1 (pt) * 2000-10-05 2010-11-03 processo para reduzir um nìvel de radionúcleos em um material de fosfogesso tendo um contaminante radioativo.
KR20160072846A (ko) 2008-05-02 2016-06-23 샤인 메디컬 테크놀로지스, 인크. 의료용 동위원소를 생산하는 디바이스 및 방법
US10978214B2 (en) 2010-01-28 2021-04-13 SHINE Medical Technologies, LLC Segmented reaction chamber for radioisotope production
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 (3)

* 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
FR2198902A1 (enrdf_load_stackoverflow) * 1972-09-09 1974-04-05 Bayer Ag
DE2733396B1 (de) * 1977-07-23 1978-09-07 Kernforschungsanlage Juelich Verfahren und Vorrichtung zum Beladen von Kernen schwachsaurer Kationenaustauscherharze mit Uranylionen

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CA526260A (en) * 1956-06-12 G. Harvey Bernard Radioactive compositions
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
GB801743A (en) * 1954-05-18 1958-09-17 Atomic Energy Authority Uk Extraction of plutonium and uranium
US3158577A (en) * 1963-06-20 1964-11-24 Lane A Bray Method of treating radioactive waste
US3880980A (en) * 1972-11-30 1975-04-29 Allied Chem Recovery of uranium from HCl digested phosphate rock solution

Patent Citations (3)

* 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
FR2198902A1 (enrdf_load_stackoverflow) * 1972-09-09 1974-04-05 Bayer Ag
DE2733396B1 (de) * 1977-07-23 1978-09-07 Kernforschungsanlage Juelich Verfahren und Vorrichtung zum Beladen von Kernen schwachsaurer Kationenaustauscherharze mit Uranylionen

Also Published As

Publication number Publication date
US4431580A (en) 1984-02-14
JPH0128920B2 (enrdf_load_stackoverflow) 1989-06-06
DE3003088A1 (de) 1981-07-30
EP0033091A1 (de) 1981-08-05
DE3162623D1 (en) 1984-07-12
JPS5716396A (en) 1982-01-27

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