[0001] This invention relates to methods and apparatus for treating aqueous industrial effluent.
In one particular aspect it relates to the treatment of radioactive effluent e.g.
from nuclear power stations, spent fuel reprocessing plants, radioisotope handling
facilities and other nuclear-related facilities. However, it may also relate to other
types of industrial effluent from which it is desired to separate dissolved components.
[0002] A typical radioactive effluent contains a variety of radionuclides in aqueous solution,
in volumes too large for long-term management. It is conventional to treat this effluent
solution to separate out the radionuclides - typically a mixture of heavy transition
metal ionsinto a more concentrated form, typically by precipitation, coprecipitation,
ion exchange, adsorption or solvent extraction.
[0003] A problem is that some radionuclides, such as iodine in reprocessing effluent, are
volatile and tend to be released gradually from the effluent throughout the separation
process. Special measures are needed to contain and adsorb these volatile radioactive
substances.
[0004] Separation processes of the type described also have relevance to other types of
industrial effluent containing useful or hazardous components which it is desired
to recover or remove. Examples arise in noble metal refining industry, metal plating
industry and catalyst manufacture.
[0005] The conventional separation processes are effective, but clearly it would be desirable
to make them still more effective.
[0006] Having investigated such effluent treatment processes, we have found that by a preliminary
treatment step in which gas is released from the effluent to reduce the level of certain
dissolved species therein, we can achieve practical advantages in the subsequent separation
treatment wherein the primary species is removed or separated from the effluent.
[0007] In one aspect the invention provides a method of treating aqueous industrial effluent,
in which a first species dissolved in the effluent is separated from the effluent
by a separation treatment, characterised by a preliminary step of treating the effluent
before the separation treatment to release and separate from it a gas, thereby enhancing
the separation treatment by reducing the content in the effluent of a dissolved second
species which stabilises the first species in solution in the effluent, said gas being,
or being derived from, the second species.
[0008] This reflects an application of our findings, that typical separation treatments
are hindered by the presence in the effluent of other species which tend to stabilise,
e.g. by complexing, the first, desired species.
[0009] Commonly, although not exclusively, a first species is a cation and a second species
an anion. Common relevant second species include oxy-anions e.g. of carbon, nitrogen
and sulphur, and organic ligands.
[0010] In most important industrial contexts, a first species is a transition metal species.
[0011] The second species may be a dissolved gas, in which case the preliminary treatment
may be simply to release it from the effluent. An example is carbon dioxide, which
exists in solution in equilibrium with carbonate and bicarbonate ion.
[0012] Commonly, however, the second species undergoes chemical conversion to form the gas.
For example, carbonates may be converted to carbon dioxide, nitrates to volatile nitrogen
oxides, and iodide oxidised or iodate reduced to volatile iodine.
[0013] Accordingly, the preliminary step may comprise one or more of oxidising or reducing
the second species, adjusting the pH of the effluent, heating and/or agitating the
effluent, and bubbling some other gas through the effluent, to achieve the desired
gas release.
[0014] In the specific context of radioactive effluent treatment, the invention provides
in a further aspect a method of treating aqueous radioactive effluent in which at
least one dissolved radionuclide is separated from the effluent by a separation treatment,
characterised by a preliminary step of treating the effluent before the separation
treatment to release and separate from it a gas, thereby reducing the level in the
effluent of dissolved species other than said at least one dissolved radionuclide.
[0015] In the context of radioactive effluent treatment, it should be noted that the gas
released from the effluent may itself be radioactive. In this case, the released gas
should be contained, and desirably absorbed or adsorbed, to prevent its spread in
the system.
[0016] In a further aspect, we provide apparatus for carrying out a method as defined above.
In particular, we provide apparatus for treating aqueous radioactive effluent, comprising
an enclosed vessel to hold the effluent and means for separating dissolved radionuclides
from the effluent, characterised by pH adjustment means, connected to act on effluent
held in the vessel, and gas uptake means for isolating gas, released from effluent
held in the vessel when the pH thereof is adjusted by the pH adjustment means, from
the effluent in the vessel.
[0017] Embodiments of the invention are now described by way of example, with reference
to the accompanying drawings in which
Fig. 1 illustrates variation of ²⁴¹Am decontamination factor with concentration of
dissolved carbonate;
Fig. 2 illustrates decontamination of radioactive carbon and iodine by pH adjustment;
Fig. 3 shows schematically apparatus for treating spent fuel effluent from a reprocessor;
Fig. 4 shows a different apparatus, for treating nuclear power plant effluent, and
Fig. 5 shows apparatus for treating a non-radioactive industrial effluent.
[0018] Examples of experimental work leading to the present invention are described with
reference to Figs. 1 and 2.
[0019] In a first experiment, the effect of carbonate concentration on the decontamination
factor (DF) of ²⁴¹Am³⁺ was investigated. A test solution, simulating a nuclear effluent,
contained sodium, nitrate, carbonate and Am³⁺ ions. The solution was treated with
ferrous ion and sodium hydroxide to coprecipitate Am as Am.Fe(OH)₃, a known coprecipitation
process for Am. The precipitate was separated by filtration and the DF (the ratio
between the initial and final concentrations of Am) determined for a variety of carbonate
concentrations. Fig. 1 shows the result. We found that DF ²⁴¹ Am was substantially
reduced by the presence of carbonate in solution, owing to stabilisation of the Am³⁺
in solution by a complexing effect.
[0020] We found furthermore that other transition metal species had decontamination factor
characteristics of a similar type, according to carbonate concentration.
[0021] In a further experiment the pH of a different test solution containing sodium cations
and nitrate, iodide, hydroxy and carbonate anions was adjusted downwardly by addition
of nitric acid from a starting pH above 10. As can be seen from Fig. 2, the decontamination
factors of ¹⁴C and ¹²⁹I increased for increasing reduction of the pH. The fall in
pH destabilised the iodide and carbonate in solution, displacing the corresponding
gases I₂ and CO₂. In this model experiment, there was one-to-one correspondence between
¹⁴C and carbonate ion. Carbonate was removed effectively from the solution by reducing
the pH value to below 8, and still more effectively below 6. Reduction to below 6
achieved an effective elimination of almost all of the iodine in solution.
[0022] Based on the above results, we observe that elimination of carbonate is a good way
of increasing the decontamination of Am and similar species, and reducing pH is a
good way of eliminating carbonate. Corresponding results can be obtained for other
radionuclides, with respect to other species in solution which may have a ligand or
anion complexing effect in solution, inhibiting separation of the radionuclides.
[0023] A typical radioactive effluent contains, for example, sodium ion, nitrate, sulphate
and carbonate at roughly molar levels (non-radioactive species) and radioactive species
such as Cs⁺, Sr⁺, Am³⁺, NpO₂²⁺, TcO₄⁻, I⁻ and CO₃²- at the order of hundredth-molar
concentrations. This would reflect the history of a spent reprocessing fuel, which
had been dissolved in nitric acid and then neutralised with NaOH. Carbonate may have-come
from the reprocessing process, also as an impurity in NaOH. Carbon may also be present
in organics such as carboxylates e.g. citrate and EDTA used in apparatus preparation.
Such compounds also tend to be stabilising with respect to radionuclide species in
solution.
[0024] It should be mentioned that during the actual reprocessing, gaseous iodine is given
off. That does not concern the effluent processing.
[0025] Fig. 3 illustrates a method and apparatus for removing carbonate and iodine from
reprocessor spent fuel effluent, using an initial pH adjustment step followed by conventional
coprecipitation of radionuclides.
[0026] Reprocessed effluent 1 containing radionuclides such as ¹³⁷Cs, ⁹⁰Sr, ¹⁴C, ²³⁷Np and
²⁴¹Am is contained in a batch in an effluent processing tank 2, from previous processing
indicated schematically at 3. Typical treatment volumes vary between 0.001 and 1 m³/day,
so a batch process may need to be carried out only once a day or less. A pM adjuster
was introduced controllably from pM adjuster supply tank 4 into the effluent, to adjust
its pM. Where the effluent pM is high, an acid such as nitric acid is a suitable adjuster.
The pH is reduced to a suitably low value e.g. from 2 to 4. As a consequence, carbonate
and iodine present in the effluent - including ¹⁴C and ¹²⁹I - are evolved from the
effluent as carbon dioxide and iodine gas. The effluent was stirred by an agitator
8 driven by a drive 7, to promote pH adjustment through the tank, and evolution of
the released gases.
[0027] Evolved gas, containing partly radioactive CO₂ and I₂, was collected in an adjacent
gas processor 6 to prevent scattering of its radioactivity into the surroundings.
A suitable gas processor 6 contains a silver-based adsorbent e.g. silver alumina,
to remove the iodine, and some suitable absorbent for CO₂, preferably a solid such
as CaCO₃ or BaCO₃ to minimise volume.
[0028] When evolution of gas is finished, a valve 6 is closed to isolate the gas processor
6 from the effluent tank 2. Coprecipitating agent is then fed into the tank 2 from
coprecipitating agent supply tank 5, to coprecipitate radionuclides. For example,
conventional reagents such as sodium phosphomolybdate and ferrocyanic acid (for Cs),
calcium phosphate and barium sulphate (for Sr) and ferric hydroxide and oxalate (for
Np and Am) are used. The various reagents need not necessarily be added simultaneously,
but it is desirable to add them in one stage to simplify the processing, provided
that the conditions required for the respective coprecipitations do not differ greatly.
Since the effluent is substantially carbonate-free, coprecipitation occurs with high
efficiency. Again the agitator 8 is operated, to promote formation of precipitate
with entrainment of radionuclide.
[0029] The effluent processing tank 2, the supply tanks 4,5 and gas processor 6 form an
integrated enclosed structure, preventing escape of volatile components into the surroundings.
[0030] After precipitation, the slurry is fed from the tank 2 into a precipitate separation
device 10 by a transfer pump 9. A filter, e.g. a sintered metal filter or tubular
filament, is an effective separator for the precipitate. Filtered effluent gradually
enters the processed effluent receiving tank 11. The precipitate, rich in radionuclides,
remains on the filter to be collected for long-term management. Typically the filter
is backwashed by a cleaning fluid, from cleaning fluid storage tank 12 by backwash
pump 13, into a precipitate receiving tank 14. Water may be used for backwash. The
smallest possible volume is used, to minimise the volume of the high-activity effluent
portion.
[0031] The use of backwash to transfer high-activity precipitate is just one possibility.
Mechanical removal of precipitate is also possible.
[0032] As described, the reprocessing effluent is processed into two parts: the liquid with
very substantially reduced radioactivity level, and the precipitate containing most
of the activity from the original effluent. The volume of the processed liquid effluent
is scarcely less than the original effluent volume, but its radionuclide concentration
is reduced typically to below 1% of the original value. Conversely, the concentration
of radionuclide in the precipitate is more than a hundred times the concentration
in the original effluent, with a volume about one hundredth the original effluent
volume.
[0033] As described, the preliminary removal of carbon dioxide enhances the decontamination
of Am and other transition elements showing a decontamination characteristic corresponding
to that of Fig. 1. Furthermore, the concomitant removal of radioactive iodine deals
with this iodine at an early stage and prevents it from volatilising and scattering
to interfere with the subsequent filtering etc. processes. Consequently special iodine
adsorbers are not needed at these subsequent stages.
[0034] In the process described, the pretreatment and the precipitation can be carried out
in a single vessel, so simple plant can be used.
[0035] The degassing can be promoted further by heating the effluent, and/or blowing gas
(e.g. air) through it in addition to adjusting the pH.
[0036] Fig. 4 shows an embodiment in which effluent from a nuclear power plant is treated.
The effluent 15, containing radionuclides such as ¹³⁷Cs, ⁹⁰Sr, ¹⁴C, ¹²⁹I and ⁶⁰Co,
is fed from the effluent supply tank 17 of the nuclear power plant to an effluent
processing tank 16. A perforated conduit 19 extends into the tank, for bubbling gas
through the tank contents from a gas supply container 18. A heater 33 is also provided
for heating the tank. In a preliminary treatment, the effluent is treated by bubbling
gas through it to promote the volatilisation of certain components therein, such as
¹²C/¹⁴C and I/¹²⁹I which volatilise as carbon dioxide and iodine respectively.
[0037] Where the initial pH of the effluent is high, an acid gas such as NO
x is appropriate for bubbling from the supply 18. It reduces the pH of the effluent,
with a result as described previously. If the pH is not high, air can be used. The
effect is slower, but the bubbling of air (lean in CO₂) through the richly carbonated
effluent gradually reduces the carbonate by taking out carbon dioxide. The same can
occur with other dissolved volatile components.
[0038] Suitable shaping of the gas conduit 19, as well as heating of the effluent, can further
promote escape of volatiles.
[0039] The released gases, containing radioactive iodine and CO₂ in this case, are collected
into gas processor 20 and adsorbed/absorbed as in the first embodiment, without scattering
into the environment. The valve 20 is then closed to isolate the effluent from the
gas processor and inhibit any tendency for redissolving.
[0040] The effluent then passes to an ion exchange column 21, for separation of the metal
species. Conventional ion exchangers such as ammonium phosphomolybdate, cobalt potassium
ferrocyanate and copper-impregnated zeolite ferrocyanate (for Cs), and sodium titanate
and titanium phosphate (for Sr and Co) may be used. The ion exchange processes need
not all be applied concurrently, but if conditions allow it is nevertheless preferred
that they be all loaded into one column.
[0041] Again, the preliminary removal of dissolved carbonate relatively destabilises the
mentioned metal species in solution (although not alkali and alkaline earth metal
species) and improves the efficiency of the ion exchange separation.
[0042] Aqueous effluent lean in radionuclides passes from the ion exchange column 21 to
the processed effluent storage tank 23. The ion exchanger operates until it starts
to be exhausted, whereupon it is removed and replaced (using flanges 22). Replacement
due time is assessed, in a known manner, by measuring radionuclide concentration in
the liquid leaching from the column. The exhausted ion exchanger is handled as relatively
high-level waste or, if it is of a reusable type, it is regenerated for re-use and
the regenerative solution (containing highly concentrated radionuclide at small volume)
is the high-level waste.
[0043] As with the first embodiment, it will be seen that the original effluent separates
into two portions, a small-volume high-activity ion exchanger portion and a large-volume
low-activity processed liquid effluent. The ion exchanger portion volume is typically
less than one fiftieth of the original effluent volume.
[0044] It will be understood how the above-described embodiments both increase the efficiency
of separation of radionuclides from effluent, enable a convenient process, and keep
short the time spent treating a given amount of effluent.
[0045] The use of ion exchange by chromatography allows equipment to be kept small, and
reduces the generation of secondary waste.
[0046] It should be understood that the features of the first two embodiments may be combined,
with additional or supplementary pH adjustment and/or heating being used together
with bubbling of gas.
[0047] Embodiments relating to general (non-radioactive) industrial effluents are now discussed
with reference to Fig. 5.
[0048] Relevant effluents typically include useful or hazardous components which it is desired
to recover/remove. Typical of such elements are Ru, Pd, Pt, Au, Cr and Cd. The apparatus
is broadly similar to that in the first embodiment. Industrial effluent 24 containing
components as mentioned is supplied from the effluent supply tank 26 into the effluent
processing tank 25 for treatment. Taking account of the specific nature of the effluent,
it is treated with oxidising or reducing agent from oxidising/reducing agent supply
container 27. For example, Ce (oxidising) and Ru, Pd (reducing) may be relevant. By
this means, stabilising species in the solution (and in particular anions) can be
converted to relatively volatile forms which can be taken off as gas. For example,
dissolved nitrates (which may stabilise dissolved platinum group species) can be rendered
more volatile by reduction to nitrite and still more volatile if reduced to nitrogen
monoxide. Equally, carbonate can be removed as carbon dioxide by using acidic agents.
As before, an agitator 38 promotes the reactions and the evolution of the volatile
products. Volatiles such as NO
x and CO₂ are discharged through gas outlet 29. According to the nature of the volatiles,
it may not be necessary to isolate them from the surroundings. It is however desirable
to close the gas outlet 29 by valve 29 to prevent re-dissolving of the removed substances
when gas evolution has substantially finished.
[0049] Suitable ion exchange substances for the useful/hazardous components are fed into
the processing tank 25 from an ion exchanger supply 28. Ion exchanger substances such
as described in the second embodiment may be relevant. If plural they need not all
be added simultaneously, but simultaneous addition is preferable.
[0050] Since stabilising anions were removed in the preceding volatilisation process, the
ion exchange proceeds efficiently. The ion exchanger with the adsorbed components
is then sent by slurry transfer pump 39 to separating mechanism 30, e.g. a filter
(sintered metal or tubular filament) to separate the ion exchange material from the
liquid effluent. Liquid effluent, separated from the ion exchanger and substantially
free of the desired/dangerous component, passes gradually to the processed effluent
tank 41. The ion exchange material incorporating the desired/dangerous component(s)
is transferred from the separating mechanism e.g. by backwash or mechanical removal,
to the ion exchanger receiving tank 32. Backwash, e.g. by water, may be from cleaning
liquid tank 31 through transfer pump 43.
[0051] By the means described, the liquid effluent may be rendered into a state in which
it can safely be discharged into the environment e.g. the sea or a river. Conversely,
the useful or dangerous substances are concentrated into a low volume making it more
efficient to recover or dispose of the materials as appropriate.
1. A method of treating aqueous industrial effluent, in which a first species dissolved
in the effluent is separated from the effluent by a separation treatment,
characterised by a preliminary step of treating the effluent before the separation
treatment to release and separate from it a gas, thereby reducing the content in the
effluent of a dissolved second species which stabilises the first species in solution
in the effluent, said gas being, or being derived from, the second species.
2. A method according to claim 1 in which the first species is cationic and the second
species is anionic.
3. A method according to claim 1 or claim 2 in which the first species is a transition
metal species.
4. A method according to any one of claims 1 to 3 in which the first species is radioactive.
5. A method according to any one of the preceding claims in which the preliminary step
causes chemical conversion of the second species to form said gas.
6. A method according to claim 5 in which the preliminary step comprises oxidizing or
reducing the second species.
7. A method according to any one of the preceding claims in which the preliminary step
comprises one or more of:
adjusting the pH of the effluent;
heating the effluent;
agitating the effluent, and
bubbling a treatment gas, different from said gas, into the effluent.
8. A method according to any one of the preceding claims, comprising absorbing or adsorbing
the released gas.
9. A method according to any one of the preceding claims in which the separation treatment
comprises one or more of
precipitation;
coprecipitation;
ion exchange;
adsorption, and
solvent extraction
of the first species from the effluent.
10. A method according to any one of the preceding claims in which the second species
is an oxy-anion or an organic ligand.
11. A method according to claim 10 in which the second species comprises carbon and the
released gas comprises carbon dioxide.
12. A method of treating aqueous radioactive effluent in which at least one dissolved
radionuclide is separated from the effluent by a separation treatment,
characterised by a preliminary step of treating the effluent before the separation
treatment to release and separate from it a gas, thereby reducing the level in the
effluent of dissolved species other than said at least one dissolved radionuclide.
13. A method according to claim 12, in which the preliminary step comprises one or more
treatments selected from
adjusting the effluent pH;
oxidizing or reducing the dissolved species;
heating the effluent;
agitating the effluent, and
bubbling a treatment gas, different from said gas, into the effluent.
14. A method according to claim 12 or claim 13 in which the separation treatment comprises
one or more of precipitation;
coprecipitation;
ion exchange;
adsorption, and
solvent extraction
of the at least one dissolved radionuclide.
15. A method according to any one of claims 12 to 14 in which the released gas comprises
radionuclides.
16. Apparatus for treating aqueous radioactive effluent, comprising an enclosed vessel
(2,16) to hold the effluent and means for separating dissolved radionuclides from
the effluent,
characterised by
pH adjustment means (4,18), connected to act on effluent held in the vessel (2,16),
and
gas uptake means (6,20) for isolating gas, released from effluent held in the vessel
(2,16) when the pH thereof is adjusted by the pH adjustment means, from the effluent
in the vessel (2,16).
17. Apparatus according to claim 16 in which the gas uptake means (6,20) comprises a gas
absorber or adsorber.
18. Apparatus according to claim 16 or claim 17, comprising at least one of
means (8) for agitating effluent in the vessel (2,16);
means (19) for bubbling gas through effluent in the vessel (16), and
means (33) for heating effluent in the vessel (16).