GB1174477A - Method of Decontamination of Media Containing Fission Products. - Google Patents

Method of Decontamination of Media Containing Fission Products.

Info

Publication number
GB1174477A
GB1174477A GB4915267A GB4915267A GB1174477A GB 1174477 A GB1174477 A GB 1174477A GB 4915267 A GB4915267 A GB 4915267A GB 4915267 A GB4915267 A GB 4915267A GB 1174477 A GB1174477 A GB 1174477A
Authority
GB
United Kingdom
Prior art keywords
solution
ruthenium
chloride
fission products
plutonium
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
GB4915267A
Inventor
Claude Musikas
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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 Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Publication of GB1174477A publication Critical patent/GB1174477A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/42—Reprocessing of irradiated fuel
    • G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
    • G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G55/00—Compounds of ruthenium, rhodium, palladium, osmium, iridium, or platinum
    • C01G55/001—Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchange
    • 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
    • C22B3/20—Treatment or purification of solutions, e.g. obtained by leaching
    • C22B3/26—Treatment or purification of solutions, e.g. obtained by leaching by liquid-liquid extraction using organic compounds
    • C22B3/28—Amines
    • C22B3/288—Quaternary ammonium
    • 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
    • G21F9/125—Processing by absorption; by adsorption; by ion-exchange by solvent extraction
    • 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
    • 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
    • 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
    • Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
    • Y02W30/00—Technologies for solid waste management
    • Y02W30/50—Reuse, recycling or recovery technologies

Landscapes

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

Abstract

1,174,477. Removal of fission products. COMMISSARIAT A L'ENERGIE ATOMIQUE. 30 Oct., 1967 [3 Nov., 1966], No. 49152/67. Heading G6R. [Also in Division C1] Fission products, in particular ruthenium, are removed from solution by oxidation to the heptavalent state, followed by liquid-liquid extraction with an organic solution of a quaternary ammonium salt in an inert solvent. Irradiated plutonium-aluminium alloy is treated with sodium hydroxide solution, sodium hypochlorite added as oxidizing agent, and the solution contacted with a solution of trilaurylmethyl-ammonium chloride in xylene or carbon tetrachloride. Ruthenium is recovered from the organic solution by treatment with a basic solution containing ethanol. Graphs are given showing the effect on the ruthenium partition coefficient of variations in the concentration in the aqueous phase of NaOH, NaClO, and chloride, nitrate, aluminate, and nitrite ions. Another quaternary ammonium salt which may be used is tricaprylmethylammonium chloride, and a nitrate may be used in place of a chloride; other suitable oxidizing agents are potassium periodate and sodium hypobromite. In Example I, an effluent is decontaminated by the removal of ruthenium and technetium, and in Example II pure Ru 106 is separated from a fission product solution containing also technetium. Reference is also made to the processing of plutonium targets clad with aluminium in the preparation of transuranic elements.
GB4915267A 1966-11-03 1967-10-30 Method of Decontamination of Media Containing Fission Products. Expired GB1174477A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR82411A FR1515048A (en) 1966-11-03 1966-11-03 Improvements in decontamination processes for media containing fission products contaminated in particular with ruthenium and in ruthenium separation processes

Publications (1)

Publication Number Publication Date
GB1174477A true GB1174477A (en) 1969-12-17

Family

ID=8620378

Family Applications (1)

Application Number Title Priority Date Filing Date
GB4915267A Expired GB1174477A (en) 1966-11-03 1967-10-30 Method of Decontamination of Media Containing Fission Products.

Country Status (5)

Country Link
BE (1) BE705723A (en)
CH (1) CH484001A (en)
FR (1) FR1515048A (en)
GB (1) GB1174477A (en)
LU (1) LU54758A1 (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109994237A (en) * 2017-12-31 2019-07-09 中国人民解放军63653部队 The preparation method of novel plutonium separation material
CN110255632A (en) * 2019-07-17 2019-09-20 江西省汉高新材料有限公司 The method for preparing ruthenium trichloride with waste material containing ruthenium
CN110423896A (en) * 2019-08-13 2019-11-08 江苏理工学院 A method of ruthenium trichloride in recycling plating ruthenium waste liquid

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2448506A1 (en) * 1979-02-08 1980-09-05 Commissariat Energie Atomique PROCESS FOR RECOVERING RUTHENIUM FROM AN ACIDIC AQUEOUS SOLUTION

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109994237A (en) * 2017-12-31 2019-07-09 中国人民解放军63653部队 The preparation method of novel plutonium separation material
CN109994237B (en) * 2017-12-31 2022-10-11 中国人民解放军63653部队 Preparation method of novel plutonium separation material
CN110255632A (en) * 2019-07-17 2019-09-20 江西省汉高新材料有限公司 The method for preparing ruthenium trichloride with waste material containing ruthenium
CN110255632B (en) * 2019-07-17 2021-05-25 江西省汉氏贵金属有限公司 Method for preparing ruthenium trichloride from ruthenium-containing waste
CN110423896A (en) * 2019-08-13 2019-11-08 江苏理工学院 A method of ruthenium trichloride in recycling plating ruthenium waste liquid
CN110423896B (en) * 2019-08-13 2021-11-16 江苏理工学院 Method for recovering ruthenium trichloride from ruthenium plating waste liquid

Also Published As

Publication number Publication date
FR1515048A (en) 1968-03-01
BE705723A (en) 1968-03-01
LU54758A1 (en) 1968-01-29
CH484001A (en) 1970-01-15

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Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PLNP Patent lapsed through nonpayment of renewal fees