EP0018923B1 - Verfahren zum Dekontaminieren von Ruthenium enthaltenden flüssigen radioaktiven Abfällen - Google Patents
Verfahren zum Dekontaminieren von Ruthenium enthaltenden flüssigen radioaktiven Abfällen Download PDFInfo
- Publication number
- EP0018923B1 EP0018923B1 EP80400616A EP80400616A EP0018923B1 EP 0018923 B1 EP0018923 B1 EP 0018923B1 EP 80400616 A EP80400616 A EP 80400616A EP 80400616 A EP80400616 A EP 80400616A EP 0018923 B1 EP0018923 B1 EP 0018923B1
- Authority
- EP
- European Patent Office
- Prior art keywords
- effluent
- iron
- ruthenium
- cupric ions
- decontamination
- 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
Links
Classifications
-
- 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
Definitions
- the present invention relates to a ruthenium decontamination process for radioactive effluents usable for raw effluents or for effluents subjected beforehand to chemical decontamination treatments of conventional type.
- radioactive effluents such as solutions originating from the treatment of irradiated fuels can be subjected to various chemical decontamination treatments making it possible in particular to remove ruthenium.
- Most of these treatments consist of forming precipitates capable of fixing ruthenium within the effluent to be treated, for example by adding ferrous ions and cupric ions to this effluent and then alkalizing the medium to precipitate the corresponding compounds of iron and copper and to separate the liquid effluent from the sludge formed as indicated in FR-A-2.124.126.
- Ruthenium can also be eliminated by bringing the effluent into contact with iron, iron alloys or activated iron compounds, for example iron wool activated by steam treatment, as described in the application for Japanese patent KOKAI 75 / 140,799.
- the ruthenium can also be eliminated by forming a precipitate of copper hydroxide within the effluent by dispersion of C U 2+ ions emitted from a copper electrode as described in FR A-2,063,717 .
- the present invention specifically relates to a ruthenium decontamination process for liquid radioactive effluents which in particular makes it possible to improve the ruthenium decontamination rate of effluents treated beforehand by chemical methods of conventional type.
- the process of the invention advantageously takes advantage of the fact that by bringing an effluent containing C U 2+ ions into contact with iron, the following reaction scheme is obtained: a copper metal deposit which entails most of the ruthenium, this copper deposit being accompanied by partial dissolution of the iron in the effluent in the state of ferrous iron.
- the decontamination rate of the ruthenium effluent can be further improved by then adjusting the pH of the effluent to a value greater than 8 to precipitate the iron that has passed into solution, which makes it possible to fix on the iron hydroxide precipitate an additional amount of ruthenium.
- the quantity of cupric ions added to said effluent is from 50 to 100 mg of Cu 2+ ions per liter of effluent.
- said effluent containing the cupric ions is brought into contact with a molar quantity of iron greater than the molar quantity of cupric ions added to said effluent.
- the quantity of iron used corresponds to approximately 500 mg of iron per liter of effluent.
- the process of the invention has the particular advantage of leading to a satisfactory decontamination rate and moreover of avoiding the formation of large volumes of precipitates and sludge which must then be stored.
- a radioactive effluent from a reprocessing plant for irradiated nuclear fuels is treated according to the method of the invention, this effluent having been treated beforehand by chemical means.
- cupric ions and ferrous ions were added to the effluent which initially exhibited a radiochemical activity in ruthenium 106 of 45,000 microcuries per m 3 , in the form of an aqueous solution of the corresponding sulfates, then soda to bring the pH of the effluent to a value of about 8.5, which allowed to form in this effluent precipitates entraining ruthenium.
- the effluent exhibited a ruthenium 106 activity of 3,180 microcuries per m 3 and had the following characteristics:
- cupric sulphate is added to the effluent so as to introduce approximately 100 mg of cupric ions per liter of effluent.
- the pH of the effluent was adjusted to a value of 3 by addition of nitric acid in order to avoid precipitation of the cupric ions in the form of cupric hydroxide.
- the effluent After stabilization of the pH, the effluent is brought into contact with powdered iron, the amount of iron used being 500 mg per liter of effluent, by subjecting the whole to stirring for a few minutes in a contactor of conventional type. , which makes it possible to obtain according to the following reaction scheme: a copper metal deposit and the partial solution of iron in the ferrous state.
- a quantity of sodium hydroxide sufficient to bring the pH to a value substantially equal to 8.5 is then added to the effluent, which leads to the precipitation of the iron passed into solution, and provides additional decontamination in ruthenium because the ruthenium binds on the iron precipitate thus formed.
- the liquid effluent is separated from the sludge formed, for example by decantation.
- the volume of sludge formed represents 1.5% of the volume of the treated effluent.
- the FD decontamination rate of the ruthenium effluent which corresponds to the ratio between the ruthenium activities of the effluent before and after decontamination treatment is of the order of 8.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Treatment Of Water By Oxidation Or Reduction (AREA)
- Removal Of Specific Substances (AREA)
Claims (5)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR7911470 | 1979-05-07 | ||
FR7911470A FR2456372A1 (fr) | 1979-05-07 | 1979-05-07 | Procede de decontamination en ruthenium d'effluents radio-actifs liquides |
Publications (2)
Publication Number | Publication Date |
---|---|
EP0018923A1 EP0018923A1 (de) | 1980-11-12 |
EP0018923B1 true EP0018923B1 (de) | 1983-09-21 |
Family
ID=9225134
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP80400616A Expired EP0018923B1 (de) | 1979-05-07 | 1980-05-06 | Verfahren zum Dekontaminieren von Ruthenium enthaltenden flüssigen radioaktiven Abfällen |
Country Status (5)
Country | Link |
---|---|
US (1) | US4331551A (de) |
EP (1) | EP0018923B1 (de) |
JP (1) | JPS5619499A (de) |
DE (1) | DE3064890D1 (de) |
FR (1) | FR2456372A1 (de) |
Families Citing this family (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS60161598A (ja) * | 1983-12-15 | 1985-08-23 | 日本原子力研究所 | 放射性ルテニウムを含む放射性廃液の処理方法 |
JPS60196700A (ja) * | 1984-03-21 | 1985-10-05 | 株式会社日立製作所 | 放射性廃液中の放射能除去方法 |
JPH06300042A (ja) * | 1993-04-13 | 1994-10-25 | Nippon Seiko Kk | 静圧気体軸受 |
EP1157076A1 (de) * | 1998-11-18 | 2001-11-28 | Radiovascular Systems, L.L.C. | Radioaktive beschichtungslösung, verfahren und substrate |
Family Cites Families (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2792412A (en) * | 1954-03-04 | 1957-05-14 | Harold R Schmidt | Recovery of ruthenium from aqueous solutions |
FR2124126B1 (de) * | 1971-02-08 | 1974-03-01 | Commissariat Energie Atomique |
-
1979
- 1979-05-07 FR FR7911470A patent/FR2456372A1/fr active Granted
-
1980
- 1980-04-29 US US06/144,911 patent/US4331551A/en not_active Expired - Lifetime
- 1980-05-06 EP EP80400616A patent/EP0018923B1/de not_active Expired
- 1980-05-06 DE DE8080400616T patent/DE3064890D1/de not_active Expired
- 1980-05-07 JP JP6046280A patent/JPS5619499A/ja active Pending
Also Published As
Publication number | Publication date |
---|---|
US4331551A (en) | 1982-05-25 |
DE3064890D1 (en) | 1983-10-27 |
EP0018923A1 (de) | 1980-11-12 |
FR2456372A1 (fr) | 1980-12-05 |
JPS5619499A (en) | 1981-02-24 |
FR2456372B1 (de) | 1981-08-14 |
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Legal Events
Date | Code | Title | Description |
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PUAI | Public reference made under article 153(3) epc to a published international application that has entered the european phase |
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AK | Designated contracting states |
Designated state(s): BE DE GB |
|
17P | Request for examination filed |
Effective date: 19810415 |
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AK | Designated contracting states |
Designated state(s): BE DE GB |
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REF | Corresponds to: |
Ref document number: 3064890 Country of ref document: DE Date of ref document: 19831027 |
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PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
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STAA | Information on the status of an ep patent application or granted ep patent |
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26N | No opposition filed | ||
BERE | Be: lapsed |
Owner name: COMMISSARIAT A L'ENERGIE ATOMIQUE ETABLISSEMENT D Effective date: 19840506 |
|
GBPC | Gb: european patent ceased through non-payment of renewal fee | ||
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: DE Effective date: 19850201 |
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PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
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