EP0021911B1 - Procédé de traitement des effluents provenant de la décontamination de composants de réacteurs nucléaires et dispositif pour la mise en oeuvre de ce procédé - Google Patents

Procédé de traitement des effluents provenant de la décontamination de composants de réacteurs nucléaires et dispositif pour la mise en oeuvre de ce procédé Download PDF

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Publication number
EP0021911B1
EP0021911B1 EP80400790A EP80400790A EP0021911B1 EP 0021911 B1 EP0021911 B1 EP 0021911B1 EP 80400790 A EP80400790 A EP 80400790A EP 80400790 A EP80400790 A EP 80400790A EP 0021911 B1 EP0021911 B1 EP 0021911B1
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EP
European Patent Office
Prior art keywords
effluent
reactor
hydrogen peroxide
process according
solution
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EP80400790A
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German (de)
English (en)
French (fr)
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EP0021911A1 (fr
Inventor
Yves Berton
Pierre Chauvet
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Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
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Commissariat a lEnergie Atomique CEA
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor

Definitions

  • the subject of the present invention is a method for treating effluents originating from the decontamination of components of nuclear reactors, such as those which result from the decontamination of metallic stainless steel parts. having stayed for a certain time in contact with the refrigerant fluid of a nuclear reactor, this fluid may consist of water or liquid sodium.
  • chemical agents in solution are used in a known manner which make it possible to dissolve the active products thus deposited on the parts.
  • the chemical agents used are variable in nature, but generally contain acids and / or bases in aqueous solution and are often supplemented by potassium permanganate which acts as an oxidizing agent.
  • the composition of such a decontamination effluent is as follows:
  • the chemical treatment of such an effluent must firstly aim at decontamination, which consists in passing the main part of the radioactivity into precipitates of sludge which are subsequently stored separately so as to be able to reject the phase liquid in nature, and, on the other hand, obtaining a good concentration of said sludge formed during the treatment of the effluent, that is to say a small volume of this sludge relative to the initial volume of the liquid effluent to be treated.
  • the subject of the present invention is precisely a process for treating such decontamination effluents which makes it possible to obtain both satisfactory decontamination factors, a good concentration of the sludge to be stored and the rejection in nature of a liquid phase acceptable to the with regard to defined legal standards.
  • This treatment process which applies to effluents which contain permanganate, phosphate and sulphate ions and radioactive ions of manganese, chromium and cobalt in solution, is essentially characterized in that it comprises the successive stages of reduction of permanganate ions by addition of hydrogen peroxide, alkalinization to a pH equal to or greater than 12, separation of the precipitate formed and final acidification of the remaining liquid phase to bring its pH to a value between 5.5 and 8 , 5, consistent with its release into the wild.
  • the reduction of permanganate ions is carried out by hydrogen peroxide, generally at 100 volumes, which is added to the liquid phase until an adjustment of the potential is obtained.
  • redox at a value close to 550 mV compared to a calomel electrode.
  • the decontamination factors are improved by adding a nickel salt or a ferrous salt to the effluent after the addition of hydrogen peroxide and before alkalization.
  • the nickel salt can be either S0 4 Ni sulfate or nitrate (Ni (NO 3 ) 2 , 6H 2 O; the ferrous salt used is most often S0 4 Fe, 7H sulfate 2 0.
  • the present invention also relates to a device for implementing this method.
  • the device for implementing the method is characterized in that it comprises a first tank communicating with a second tank, the two tanks being provided with stirring means, means for introducing into said first tank the liquid effluent to treating and the hydrogen peroxide, means for adjusting the oxidation-reduction potential of the effluent present in said tank to the desired value, means for introducing into said second tank a nickel salt and an alkaline solution, means to adjust the pH of the effluent present in said tank to the desired value, means for separating the precipitate formed from the effluent and for bringing it into a third tank provided with stirring means, means for introducing an acid solution into said third tank and means for adjusting the pH of the effluent to the desired value.
  • This device is characterized in that the means for separating the precipitate formed are constituted by a centrifuge and by a filter.
  • the hydrogen peroxide added is 100 volumes hydrogen peroxide and the amount used was 1.1 ml / l of solution. Alkalization at a pH above 12 was obtained using sodium hydroxide in an amount equal to 85 g / l of solution.
  • Nickel is introduced in the form of a solution of nickel sulphate SO 4 Ni at 0.3 g / I.
  • the following table gives, for each of the three radionuclides 54 Mn, 60 Co and 51 Cr, the activities in micro-curies / m 3 before and after the treatment. It can be seen that good decontamination factors are already obtained by treating hydrogen peroxide plus soda, but that these factors are still much improved if the nickel salt is added. A decontamination factor greater than 430 for manganese, greater than 15 for chromium and equal to 10 for cobalt is then obtained.
  • the second example of implementation of the treatment method according to the invention relates to an effluent solution whose initial activity (indicated below) is clearly greater than the effluent activities of the previous example. It will be seen in the table below that the results obtained with regard to the decontamination factor are therefore much more spectacular.
  • This effluent has the following chemical characteristics:
  • the effluent solution was treated with the addition of hydrogen peroxide at 100 volumes at a dose of 1.5 ml / l of solution to reduce the permanganate ions; 0.3 g / l of nickel ion solution in the form of sulphate was then added and the medium was basified by adding 80 to 95 g / l of sodium hydroxide to obtain a pH equal to or greater than 12.
  • This example relates to comparative experiments carried out with nickel and other metallic cations such as iron, copper, calcium or cobalt, in order to compare the decontamination factors obtained.
  • the following table clearly shows the clear superiority of nickel over the other cations.
  • 1.5 ml of oxygenated water was introduced at 100 volumes per liter of effluent and after addition of the metal salt, sodium hydroxide was added until a pH of 12 was obtained.
  • a column called “total gamma” has been added to the specific decontamination factor for each of the three preceding radionuclides, corresponding to the overall decontamination of all the gamma emitters considered as a whole.
  • FIG. 1 shows, under the conditions of the experiment corresponding to the penultimate line of the table above (300 mg / 1 of nickel ions) the influence of the pH of the solution, plotted on the abscissa on the factor of decontamination obtained for each of the three radionuclides contained in the starting effluent, namely 5 'Cr, 6 ° Co, and 54 Mn. It is obvious, when consulting this curve, that the maximum effect of pH on decontamination is located for a value of the latter equal to or greater than 12.
  • the sludge formed by precipitation during chemical treatment is generally very divided and, given the high salinity of the treated effluent, they do not settle. Under these conditions, to obtain a true separation of the liquid and solid phases, use must be made of a filtration or preferably centrifugation operation, since the latter technique is much more effective due to the low cohesion of the sludge. Additional filtration eliminates fine particles that may have remained in suspension after centrifugation.
  • the effluents are brought by a pipe 1 into a first tank 2 provided with an agitator 3.
  • the hydrogen peroxide contained in a storage tank 5 is injected into the container 2, controlling at using a device per se known 6 the redox potential of this solution so as to bring it to the desired value, generally close to 550 mV relative to a calomel electrode.
  • the effluents generally stay for a period of the order of 30 minutes in the tank 2.
  • Line 7 then conducts the effluents in a second container 8 also fitted with an agitator 9 and into which is introduced via line 10 the nickel sulphate stored in container 11, and, via line 12 the sodium hydroxide stored in container 13 to bring the pH to a value equal to or greater than 12, which is checked using the probe 14.
  • the effluent then passes through the pipe 15 in a buffer tank 16 before reaching the centrifuge 17 where the sludge separation takes place. by spin.
  • the liquid effluent must still be filtered through the filter 23 to remove fine particles which would not have been completely separated by centrifugation; the pipe 24 then leads the liquid phase thus treated in a new tank 25 provided with an agitator and into which is introduced by a pipe 26 the quantity of acid (nitric or sulfuric) necessary coming from the storage container 27 to adjust the pH before rejection at a value compatible with current regulations and generally around 7. Control of the pH value is carried out by a probe 28 bypass on the tank 25. The final rejection can then take place by gravity at base 29 of container 25.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Removal Of Specific Substances (AREA)
  • Treatment Of Water By Oxidation Or Reduction (AREA)
EP80400790A 1979-06-14 1980-06-03 Procédé de traitement des effluents provenant de la décontamination de composants de réacteurs nucléaires et dispositif pour la mise en oeuvre de ce procédé Expired EP0021911B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR7915273 1979-06-14
FR7915273A FR2459536A1 (fr) 1979-06-14 1979-06-14 Procede de traitement des effluents de decontamination, notamment de composants de reacteurs nucleaires et dispositif pour la mise en oeuvre de ce procede

Publications (2)

Publication Number Publication Date
EP0021911A1 EP0021911A1 (fr) 1981-01-07
EP0021911B1 true EP0021911B1 (fr) 1984-03-07

Family

ID=9226624

Family Applications (1)

Application Number Title Priority Date Filing Date
EP80400790A Expired EP0021911B1 (fr) 1979-06-14 1980-06-03 Procédé de traitement des effluents provenant de la décontamination de composants de réacteurs nucléaires et dispositif pour la mise en oeuvre de ce procédé

Country Status (7)

Country Link
US (1) US4312758A (enrdf_load_stackoverflow)
EP (1) EP0021911B1 (enrdf_load_stackoverflow)
JP (1) JPS562885A (enrdf_load_stackoverflow)
CA (1) CA1154180A (enrdf_load_stackoverflow)
DE (1) DE3066814D1 (enrdf_load_stackoverflow)
ES (1) ES492429A0 (enrdf_load_stackoverflow)
FR (1) FR2459536A1 (enrdf_load_stackoverflow)

Families Citing this family (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4572797A (en) * 1983-03-02 1986-02-25 The United States Of America As Represented By The United States Department Of Energy Method for removing trace pollutants from aqueous solutions
ATE140438T1 (de) * 1989-05-09 1996-08-15 Univ California Verfahren und zusammensetzung zur behandlung von abwasser
US4983306A (en) * 1989-05-09 1991-01-08 The Regents Of The University Of California Method of treating waste water
DE4313127A1 (de) * 1993-04-22 1994-10-27 Wismut Gmbh Verfahren zur gleichzeitigen Fällung von Uran, Arsen und Radium aus bergbaulichen Abwässern
RU2234153C2 (ru) * 2002-07-29 2004-08-10 ФГУП "Производственное объединение "Маяк" Способ переработки радиоактивных пульп и осадков соединений марганца (iv), (vi)
RU2250520C2 (ru) * 2003-04-25 2005-04-20 Открытое Акционерное Общество Сосновоборский Проектно-изыскательский институт "ВНИПИЭТ" (ОАО СПИИ "ВНИПИЭТ") Способ очистки жидких радиоактивных отходов
RU2268513C1 (ru) * 2004-12-28 2006-01-20 Закрытое акционерное общество "РАОТЕХ" Способ переработки жидких радиоактивных отходов
US9056784B2 (en) * 2006-09-19 2015-06-16 Ken V. Pandya High efficiency water-softening process
US20100010285A1 (en) * 2008-06-26 2010-01-14 Lumimove, Inc., D/B/A Crosslink Decontamination system
FR2937054B1 (fr) * 2008-10-13 2010-12-10 Commissariat Energie Atomique Procede et dispositif de decontamination d'une surface metallique.
RU2465666C2 (ru) * 2010-12-29 2012-10-27 Александр Гаврилович Басиев Способ переработки жидких радиоактивных отходов
RU2597242C1 (ru) * 2015-04-13 2016-09-10 Акционерное общество "Государственный научный центр Российской Федерации - Физико-энергетический институт имени А.И. Лейпунского" Способ очистки жидких радиоактивных отходов от органических примесей
RU2641656C1 (ru) * 2016-12-21 2018-01-19 федеральное государственное бюджетное образовательное учреждение высшего образования "Московский государственный технический университет имени Н.Э. Баумана (национальный исследовательский университет)" (МГТУ им. Н.Э. Баумана) Способ очистки жидких радиоактивных отходов и устройство для его осуществления
RU2654195C1 (ru) * 2017-06-01 2018-05-17 Общество с ограниченной ответственностью "РАОТЕХ" Способ переработки жидких радиоактивных отходов

Family Cites Families (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CA724706A (en) * 1965-12-28 H. Rice Archie Process for clarifying water
US2105835A (en) * 1932-12-13 1938-01-18 Katadyn Inc Sterilizing liquid
US3013978A (en) * 1959-09-15 1961-12-19 Rosinski John Removal of fission products from water
FR2031844A5 (en) * 1969-02-10 1970-11-20 Commissariat Energie Atomique Decontamination of radioactive effluent - from irradiated nuclear fuel treatment
FR2067743A5 (en) * 1969-11-14 1971-08-20 Commissariat Energie Atomique Decontamination of effluent liquids contng cesium 137
JPS4811280B1 (enrdf_load_stackoverflow) * 1970-11-09 1973-04-12
US3716485A (en) * 1971-01-11 1973-02-13 Ayteks International Corp Process and apparatus for destroying hexavalent chromium in solution
JPS49116854A (enrdf_load_stackoverflow) * 1973-03-08 1974-11-08
US3873362A (en) * 1973-05-29 1975-03-25 Halliburton Co Process for cleaning radioactively contaminated metal surfaces
JPS5132057A (en) * 1974-09-13 1976-03-18 Toa Gosei Chem Ind Haisui no shorihoho
DE2613128C2 (de) * 1976-03-27 1982-03-04 Hoechst Ag, 6000 Frankfurt Verfahren zur Verminderung des Quecksilbergehaltes von Betriebsabwässern
US4049545A (en) * 1976-07-08 1977-09-20 Rocky Carvalho Chemical waste water treatment method
DE2723025C3 (de) * 1977-05-21 1980-03-13 Rheinisch-Westfaelisches Elektrizitaetswerk Ag, 4300 Essen Verfahren zum Aufbereiten von Borsäure, radioaktives Antimon und weitere radioaktive Nuklide enthaltendem Abwasser
DE2724954C2 (de) * 1977-06-02 1984-11-15 Reaktor-Brennelement Union Gmbh, 6450 Hanau Verfahren zur Dekontamination von alpha- und beta-aktivem Prozeßwasser

Also Published As

Publication number Publication date
US4312758A (en) 1982-01-26
DE3066814D1 (en) 1984-04-12
EP0021911A1 (fr) 1981-01-07
ES8105115A1 (es) 1981-05-16
JPS6116957B2 (enrdf_load_stackoverflow) 1986-05-02
CA1154180A (en) 1983-09-20
ES492429A0 (es) 1981-05-16
FR2459536A1 (fr) 1981-01-09
FR2459536B1 (enrdf_load_stackoverflow) 1983-10-28
JPS562885A (en) 1981-01-13

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