WO2001065570A2 - Treatment for waste containing technetium - Google Patents
Treatment for waste containing technetium Download PDFInfo
- Publication number
- WO2001065570A2 WO2001065570A2 PCT/GB2001/000845 GB0100845W WO0165570A2 WO 2001065570 A2 WO2001065570 A2 WO 2001065570A2 GB 0100845 W GB0100845 W GB 0100845W WO 0165570 A2 WO0165570 A2 WO 0165570A2
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- dithionite
- addition
- mac
- ppm
- process according
- 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.)
- Ceased
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
-
- 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
-
- 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
- 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
Definitions
- the present invention relates to a novel process for the treatment of Tc".
- Tc nuclear fuel cycle and, in particular, the processing of nuclear waste material is described in "The Nuclear Fuel Cycle” edited by P D Wilson, the content of which is incorporated herein by reference.
- Tc nuclear waste material
- MAC medium active concentrate
- the majority of the Tc is contained in the MAC and therefore attention has been focussed upon treating MAC.
- Due to its low specific activity (6.28 x 10 "4 TBq/g) Tc has a relatively long half life (2.13 x 10 years), and is therefore usually present in MAC in chemically significant concentrations.
- Tc pertechnetate anion [Tc0 ] ⁇ is a very stable species which is soluble under aqueous conditions. It has long been held that any treatment process must change the valency of the technetium to precipitate it from solution.
- Tc is most likely to be present in effluent as Tc v ⁇ , e.g. [Tc0 ] " , and therefore it would be reduced substantially to Tc IV .
- Tc0 2 is generally insoluble in aqueous solutions it can therefore be readily separated using conventionally known techniques, such as filtration, sedimentation, aggregation, etc.
- the process of the invention is particularly advantageous in that it is able to minimise re-oxidation of Tc0 2 to e.g. Tc v ⁇ .
- a number of methods have been found which mitigate re-oxidation and therefore any one or any combination of these steps may be incorporated in the process of the invention.
- the preferred method of preventing re-oxidation is the stepwise or continuous addition of dithionite over the course of the reaction.
- the frequency of the stepwise dithionite addition may vary and will depend upon, inter alia, the volume to surface area ratio of the vessel used.
- the volume to surface area ratio of the vessel used may vary, although a large ratio is preferred, requiring fewer repeat dosages of dithionite.
- a dithionite addition every 60 minutes is currently preferred.
- the frequency of addition may be extended to as much as 60 hours.
- addition of dithionite can be effected in a continuous manner.
- the amount of dithionite added may also be varied depending upon, inter alia, the amount of Tc v ⁇ present.
- dithionite to be added either stepwise or continuously, at a rate to maintain the concentration of dithionite within the range of 100 - 2000 ppm, preferably 100 - 1500 ppm.
- the dithionite may be added in large quantities initially, with smaller quantities being added at later additions.
- the initial addition of dithionite may be from 500 to 1500 ppm, eg 1000 ppm.
- Later additions may be from 100 to 500 ppm, preferably 200 to 400 ppm, eg 300 ppm.
- the reduction may be facilitated under a nitrogen blanket or a nitrogen sparge.
- Nitrogen sparge experiments were conducted which studied the reaction's progress over a period of 72 hours. With dithionite under air a high DF is achieved quickly but this decays away with time. Flowever, under a nitrogen sparge, the Tc removal is stabilised and even appears to increase over the time period, to a peak of 2 x 10 after 50 hours.
- the process of the invention may be carried out under a nitrogen sparge, a nitrogen blanket or a combination of both.
- it is a distinct advantage of the present invention that, e.g. stepwise addition of dithionite, can remove the need for a nitrogen blanket and/or a nitrogen sparge.
- the process of the invention is also advantageous in that it generally does not have a detrimental effect on decontamination factors of other isotopes such as Ru 106 , Sr 90 and Cs 137
- MAC is generally acidic in nature and we have found that the dithionite reduction of MAC is pH sensitive.
- the MAC may be substantially neutralised by the addition of a base.
- bases Conventionally known bases may be used, but the preferred bases are hydroxides, such as alkali metal hydroxides, eg potassium hydroxide and especially sodium hydroxide.
- MAC is substantially neutralised, e.g. to a pH of between 7 and 1 1, preferably between 9 and 1 1 , more preferably between 10 and 1 1 , eg pH 10.5. Lowering of the pH will occur upon addition of the dithionite.
- the preferred pH for conducting dithionite reactions is pH 10.5.
- the addition of 1000 ppm dithionite will reduce the pH of the neutralised MAC to ⁇ 8.
- the large change in pH on addition of dithionite can be adjusted by the addition of further sodium hydroxide to readjust the pH to 10.5.
- the removal of some isotopes is pH dependent.
- the DFs for Cs and Sr vary with pH but in opposite ways. Thus a balance is drawn in order to optimise both Cs and Sr DFs and the reaction is conducted within the range pFI6 to 14, preferably pH8 to 1 1 and more preferably at pH 10.9.
- the dithionite may be added as a solution, ie dithionite dissolved in an aqueous sodium hydroxide solution.
- the advantdage of the use of an aqueous dithionite/sodium hydroxide solution is that effects on the pH of the MAC are mitigated.
- concentration of the aqueous sodium hydroxide solution may be varied, a preferred concentration is from 0.05 to 1.0 and preferably 0.1.
- Iron present in the MAC may form ferric hydroxide (Fe(OH) ) as a floe.
- Fe(OH) ferric hydroxide
- the Tc0 2 produced by the dithionite reduction may precipitate out of the reaction with the ferric hydroxide floe.
- the dithionite process can, of course be applied to MAC permeate (filtrate) or similar streams which have been filtered to remove the ferric floe and the bulk of the radionuclides, i.e. streams containing Tc only.
- the absence of floe makes filtering the Tc0 2 more difficult and the DFs are lowered.
- Figure 1 shows the Tc DFs obtained in the presence of floe and in the absence of floe (like filtrate/permeate) at different pH after a single addition of 1000 ppm dithionite.
- the filtration step is conducted prior to the addition of dithionite.
- the process can be operated on a continuous basis rather than batch wise, and employ the use of a flooded reactor, e.g. a plug flow reactor, so that oxygen may then be excluded from the process altogether without the use of a nitrogen blanket or sparge.
- a flooded reactor e.g. a plug flow reactor
- the Tc bearing stream is fed into the plug flow reactor concurrently with the sodium dithionite solution.
- the reactor is run flooded so the minimum amount of dithionite is added to effect reduction as oxygen can not absorb into the mixture.
- Sufficient dithionite is added to reduce the oxygen already absorbed, the chromium present and the Tc present.
- the mixture is passed down the reactor which is a sufficient length and at a rate sufficient to allow complete reduction of the Tc.
- the precipitated Tc0 2 is then filtered off through a 0.04 ⁇ m filter.
- Table 1 Medium Active Feed (MAC Neutralised to 3x its volume) In all experiments where MAC liquor was used, the final reaction volume was adjusted after neutralisation to three times the original volume of MAC used. This table gives the activity levels in the reaction mixture. In some experiments a MAC simulant was used which contained 250 g/1 sodium nitrate, 30 ppm chromium, 100 ppm Tc in the form of pertechnate and various levels of dissolved iron.
- Dithionite was added at 1000, 500 and 200 ppm as a solid to MAC neutralised to pH 10.5 and with a nitrogen sparge. With 1000 ppm dithionite added the pH dropped to 7.8 and a black grainy ppt was formed. The presence of 500 ppm dithionite lowered the pFI to 9 and again a black grainy ppt was produced. In both cases Tc decontamination factors (DFs) were > 10 3 after 72 hours, with 200 ppm dithionite added, however, the Tc DFs were never very high.
- DFs decontamination factors
- Dithionite 40 ml of MAC were neutralised with sodium hydroxide solution to a volume of 120 ml and pH 1 1.2.
- Dithionite was added (1000 ppm) as the mixture was stirred and then added again after every hour (1000 ppm).
- the pH was continually adjusted to maintain pH 1 1.2.
- a nitrogen sparge was not used in these experiments.
- a sample of the MAC solution was taken just before each dithionite addition and filtered through a 0.02 ⁇ m filter. The filtrate was then analysed for Tc, Sr and Cs.
- Dithionite 50 ml of MAC were neutralised with sodium hydroxide solution to a volume of 130 ml and pH 1 1.2. The mixture was stirred at a high rate. Dithionite was added (300 ppm) and then again at 300 ppm concentration after every hour. The pH was continually adjusted to maintain pH 11.2. A sample of the MAC solution was taken just before each dithionite addition and filtered through a 0.02 ⁇ m filter. The filtrate was then analysed for Tc, Sr and Cs.
- Figure 1 illustrates a time dependence for Tc DF with good removal for a period of up to 3 hours and thereafter a gradual reduction in DF. This reduction is brought about by the re-oxidation of precipitated Tc0 2 .
- Tables 2 to 4 show that the Tc DF can be maintained for long periods by the use of a nitrogen sparge or blanket. Alternatively, repeat doses of dithionite can be added to the mixture to maintain the reductive environment without the use of a nitrogen sparge or blanket.
- Figure 4 shows that the bigger the volume to surface area ratio of the solution exposed to air, the longer the DF lasts because the concentration of oxygen in solution is reduced. That is the dithionite lasts longer.
- the significance of this is that the EARP plant itself is large with a large volume/surface area ratio and extrapolation from this data to the volume/surface area of the EARP plant (circled point) means that a dosing rate of only once every 60 hours would be required. There appears to be no adverse effect on the DFs for other radionuclides due to the use of dithionite.
- Table 1 Typical Activity Levels in the Reaction Mixture (MAC diluted 3 times)
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma & Fusion (AREA)
- Removal Of Specific Substances (AREA)
- Treatment Of Water By Oxidation Or Reduction (AREA)
Abstract
Description
Claims
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| AU35791/01A AU3579101A (en) | 2000-03-01 | 2001-02-28 | Waste treatment |
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB0004751.4 | 2000-03-01 | ||
| GB0004751A GB0004751D0 (en) | 2000-03-01 | 2000-03-01 | Waste treatment |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| WO2001065570A2 true WO2001065570A2 (en) | 2001-09-07 |
| WO2001065570A3 WO2001065570A3 (en) | 2001-12-20 |
Family
ID=9886595
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| PCT/GB2001/000845 Ceased WO2001065570A2 (en) | 2000-03-01 | 2001-02-28 | Treatment for waste containing technetium |
Country Status (3)
| Country | Link |
|---|---|
| AU (1) | AU3579101A (en) |
| GB (1) | GB0004751D0 (en) |
| WO (1) | WO2001065570A2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US9388478B1 (en) | 2014-12-19 | 2016-07-12 | Savannah River Nuclear Solutions, Llc | Technetium recovery from high alkaline solution |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4528165A (en) * | 1984-06-13 | 1985-07-09 | The United States Of America As Represented By The United States Department Of Energy | Separation of uranium from technetium in recovery of spent nuclear fuel |
| JPS63284189A (en) * | 1987-05-15 | 1988-11-21 | Nippon Mejifuijitsukusu Kk | Technetium-99m-labeled diagnosticum for cancer |
| JPH08508500A (en) * | 1993-03-31 | 1996-09-10 | マリンクロット・メディカル・インコーポレイテッド | Radiopharmaceutical with non-stannous reducing agent |
| GB9814785D0 (en) * | 1998-07-09 | 1998-09-09 | British Nuclear Fuels Plc | Waste treatment method |
-
2000
- 2000-03-01 GB GB0004751A patent/GB0004751D0/en not_active Ceased
-
2001
- 2001-02-28 WO PCT/GB2001/000845 patent/WO2001065570A2/en not_active Ceased
- 2001-02-28 AU AU35791/01A patent/AU3579101A/en not_active Abandoned
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US9388478B1 (en) | 2014-12-19 | 2016-07-12 | Savannah River Nuclear Solutions, Llc | Technetium recovery from high alkaline solution |
Also Published As
| Publication number | Publication date |
|---|---|
| GB0004751D0 (en) | 2000-04-19 |
| AU3579101A (en) | 2001-09-12 |
| WO2001065570A3 (en) | 2001-12-20 |
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