EP3736819A1 - Procédé de retraitement de déchets radioactifs liquides - Google Patents
Procédé de retraitement de déchets radioactifs liquides Download PDFInfo
- Publication number
- EP3736819A1 EP3736819A1 EP18890167.2A EP18890167A EP3736819A1 EP 3736819 A1 EP3736819 A1 EP 3736819A1 EP 18890167 A EP18890167 A EP 18890167A EP 3736819 A1 EP3736819 A1 EP 3736819A1
- Authority
- EP
- European Patent Office
- Prior art keywords
- lrw
- radioactive waste
- sorbent
- treatment
- radionuclides
- 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.)
- Withdrawn
Links
- 239000010857 liquid radioactive waste Substances 0.000 title claims abstract description 55
- 238000000034 method Methods 0.000 title claims abstract description 28
- 238000012958 reprocessing Methods 0.000 title 1
- 239000002594 sorbent Substances 0.000 claims abstract description 42
- 238000001914 filtration Methods 0.000 claims abstract description 17
- 230000003647 oxidation Effects 0.000 claims abstract description 15
- 238000007254 oxidation reaction Methods 0.000 claims abstract description 15
- 238000000746 purification Methods 0.000 claims abstract description 8
- 238000001471 micro-filtration Methods 0.000 claims abstract description 6
- 239000000706 filtrate Substances 0.000 claims abstract description 4
- 230000001590 oxidative effect Effects 0.000 claims abstract 2
- 239000002901 radioactive waste Substances 0.000 abstract description 5
- 238000005516 engineering process Methods 0.000 abstract description 3
- 239000007791 liquid phase Substances 0.000 description 14
- 238000006385 ozonation reaction Methods 0.000 description 14
- 239000002699 waste material Substances 0.000 description 13
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 12
- 239000010802 sludge Substances 0.000 description 10
- CBENFWSGALASAD-UHFFFAOYSA-N Ozone Chemical compound [O-][O+]=O CBENFWSGALASAD-UHFFFAOYSA-N 0.000 description 8
- 239000002245 particle Substances 0.000 description 8
- 239000000725 suspension Substances 0.000 description 8
- 230000000694 effects Effects 0.000 description 7
- 229910052792 caesium Inorganic materials 0.000 description 6
- TVFDJXOCXUVLDH-UHFFFAOYSA-N caesium atom Chemical compound [Cs] TVFDJXOCXUVLDH-UHFFFAOYSA-N 0.000 description 6
- 229910052759 nickel Inorganic materials 0.000 description 6
- 230000007423 decrease Effects 0.000 description 5
- 238000003756 stirring Methods 0.000 description 5
- 229910052500 inorganic mineral Inorganic materials 0.000 description 4
- 239000011707 mineral Substances 0.000 description 4
- 239000000843 powder Substances 0.000 description 4
- 238000012545 processing Methods 0.000 description 4
- 239000000701 coagulant Substances 0.000 description 3
- 238000001704 evaporation Methods 0.000 description 3
- 230000008020 evaporation Effects 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 230000002285 radioactive effect Effects 0.000 description 3
- 238000000926 separation method Methods 0.000 description 3
- 239000007787 solid Substances 0.000 description 3
- 239000000084 colloidal system Substances 0.000 description 2
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 230000007774 longterm Effects 0.000 description 2
- 239000012528 membrane Substances 0.000 description 2
- 229910000000 metal hydroxide Inorganic materials 0.000 description 2
- 150000004692 metal hydroxides Chemical class 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 229910052723 transition metal Inorganic materials 0.000 description 2
- 150000003624 transition metals Chemical class 0.000 description 2
- GUTLYIVDDKVIGB-OUBTZVSYSA-N Cobalt-60 Chemical compound [60Co] GUTLYIVDDKVIGB-OUBTZVSYSA-N 0.000 description 1
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 description 1
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 description 1
- 229910021486 amorphous silicon dioxide Inorganic materials 0.000 description 1
- 239000007900 aqueous suspension Substances 0.000 description 1
- 230000015556 catabolic process Effects 0.000 description 1
- 239000000919 ceramic Substances 0.000 description 1
- TVFDJXOCXUVLDH-RNFDNDRNSA-N cesium-137 Chemical compound [137Cs] TVFDJXOCXUVLDH-RNFDNDRNSA-N 0.000 description 1
- 230000001143 conditioned effect Effects 0.000 description 1
- 238000002425 crystallisation Methods 0.000 description 1
- 238000005202 decontamination Methods 0.000 description 1
- 230000003588 decontaminative effect Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000001035 drying Methods 0.000 description 1
- 239000008187 granular material Substances 0.000 description 1
- 230000000977 initiatory effect Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 239000010808 liquid waste Substances 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 239000008239 natural water Substances 0.000 description 1
- LGQLOGILCSXPEA-UHFFFAOYSA-L nickel sulfate Chemical compound [Ni+2].[O-]S([O-])(=O)=O LGQLOGILCSXPEA-UHFFFAOYSA-L 0.000 description 1
- 150000002894 organic compounds Chemical class 0.000 description 1
- 239000011148 porous material Substances 0.000 description 1
- 238000005086 pumping Methods 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- 239000011780 sodium chloride Substances 0.000 description 1
- 239000007790 solid phase Substances 0.000 description 1
- 238000001179 sorption measurement Methods 0.000 description 1
- 238000012546 transfer Methods 0.000 description 1
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
-
- 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
-
- 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
-
- 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
Definitions
- the invention relates to a liquid radioactive waste (LRW) treatment technology and can be used for processing of radioactive substances at various nuclear industry facilities.
- LGW liquid radioactive waste
- This method can be used at various nuclear industry facilities, including nuclear power plants, for low-level and intermediate-level LRW treatment, for treatment of solutions generated during decontamination of buildings, structures, equipment, vehicles etc., for treatment of natural water contaminated with radionuclides.
- LRW treatment is aimed at solving two main problems: purifying the bulk of the waste from radionuclides and concentrating the latter in a minimal volume.
- Disadvantages of the method include low coefficients of purification from radionuclides remaining in the liquid phase after oxidation in the ionic state, namely, from radionuclides of caesium.
- Disadvantage of the method is that there is no guarantee of full ozone saturation of the liquid under conditions of the flow treatment. This leads to the slip of the complex form of radionuclides into the purified liquid phase through a selective sorbent, because neither separation of condensed sludge nor selective sorption can trap out complex radionuclides, that reduces overall LRW treatment effectiveness.
- the waste flow is purified from suspended particles by filtration on a mesh filter material before ozone treatment.
- Ozone treatment is carried out in a circulating mode.
- the oxidized flow is separated to a condensed sludge and a liquid phase by filtration on a mesh filter material.
- Membrane microfiltration is carried out to separate the liquid phase from radionuclides in colloidal form to return them to the stream of liquid radioactive waste after ozone is applied (Invention patent of the Russian Federation No 2268513 "Method for liquid radioactive waste treatment", 7 IPC G21F 9/06, G21F 9/20, priority date 28/12/2004, published 20/01/2006).
- caesium radionuclides in ionic form contributing the most to the total activity of LRW are removed only at the final stage of the process - by selective sorbents placed in filter containers.
- initial activity of caesium radionuclides in LRW is 3.7 ⁇ 10 8 Bq/l (10 Ci/m 3 )
- the suspension consisting of the sorbent, suspended particles from the LRW and the coagulant was fed to Corebrick F (position 2) with two filter elements, and after that the solution purified from the suspension was sent to ozonation (position 3) to destroy organic compounds and complexes.
- 5 kg of the same sorbent as in the tank (position 1) was added to the suspension formed during oxidation, and the resulting suspension was sent to Corebrick F (position 4) with two filter elements.
- the solution purified from suspension was passed through Corebricks C (positions 5 and 6) connected in series with granular selective sorbent based on nickel ferrocyanide.
- the main disadvantage of the prototype is that using the sorbent before ozonation lets trace amounts of transition metals included in the sorbent enter the ozonation system after filtration, and catalytically destroy ozone. This leads to a significant decrease in the efficiency of ozonation, an increase in the time of ozonation, and, in some cases, to inability to purify LRW from a number of radionuclides.
- Technical result of the claimed invention is to increase effectiveness of the method by reducing the volume of radioactive waste requiring special storage and to reduce the dose of radiation exposure of the staff during the LRW treatment.
- the claimed technical result is achieved by the fact that the LRW treatment method includes filtration, oxidation of LRW to obtain an oxidized flow, its filtration, microfiltration and purification from radionuclides by supplying the filtrate into a container with granular selective sorbents. Moreover, after oxidation, a selective sorbent is added to the oxidized stream before filtration, and the sorbent is added to the LRW only after the oxidation stage.
- the novelty of the claimed invention consists in the addition of the sorbent to the liquid radioactive waste only after the stage of oxidation.
- One or more selective sorbents are added to the oxidized stream during the LRW treatment.
- the selective sorbent is introduced into the oxidized stream in the form of a paste or suspension, or in the form of a powder, or in the form of granules
- Adding a selective sorbent after oxidation to the oxidized flow before filtration makes it possible to transfer the main amount of radionuclides, including caesium radionuclides, to the sludge that is separated at the filtration and microfiltration stages.
- the activity of caesium radionuclides in the liquid phase after filtration decreases to 10 -4 -10 -5 Ci/m 3 . Therefore one filter container can be used to treat not 12 m 3 , as in the analogue method, but up to 10,000 m 3 of LRW. Accordingly, the effective waste volume reduction factor will increase to at least 100.
- the number of expensive filter containers required for LRW processing and the costs of their special storage will also decrease by at least 100 times.
- the resource of the filter container currently used at nuclear power plants will be at least 1,000 m 3 . If there is no stage of applying the powder sorbent, the Cs-137 content in the purified solution will be 1.1 ⁇ 10 -2 Ci/l, and the resource of the filter container will be less than 10 m 3 of LRW.
- Example 1 100 g of an aqueous suspension of nickel ferrocyanide sorbent (containing 50 g (0.5% of LRW weight) of the colloidal nickel ferrocyanide sorbent) were added to the same LRW as in Example 1 after ozonation.
- the solution was filtered after two hours of stirring likewise.
- the activity of the solution became lower than 0.4 ⁇ 10 -10 Ci/l. Based on radiation safety standards, such a solution does not require further purification using filter containers. After evaporation of the solution, the resulting melt can be stored in landfills with non-radioactive chemical materials.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| RU2017144738A RU2675787C1 (ru) | 2017-12-19 | 2017-12-19 | Способ переработки жидких радиоактивных отходов |
| PCT/RU2018/000831 WO2019125216A1 (fr) | 2017-12-19 | 2018-12-17 | Procédé de retraitement de déchets radioactifs liquides |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| EP3736819A1 true EP3736819A1 (fr) | 2020-11-11 |
| EP3736819A4 EP3736819A4 (fr) | 2021-11-24 |
Family
ID=64753577
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| EP18890167.2A Withdrawn EP3736819A4 (fr) | 2017-12-19 | 2018-12-17 | Procédé de retraitement de déchets radioactifs liquides |
Country Status (3)
| Country | Link |
|---|---|
| EP (1) | EP3736819A4 (fr) |
| RU (1) | RU2675787C1 (fr) |
| WO (1) | WO2019125216A1 (fr) |
Family Cites Families (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| BE859028A (fr) * | 1977-09-26 | 1978-03-28 | Belgonucleaire Sa | Procede de decontamination de l'eau |
| RU2066493C1 (ru) | 1995-11-13 | 1996-09-10 | Товарищество с ограниченной ответственностью "Лаборатория технологий водоочистки - Наука-LTD" | Способ обработки жидких радиоактивных отходов аэс |
| US5960368A (en) * | 1997-05-22 | 1999-09-28 | Westinghouse Savannah River Company | Method for acid oxidation of radioactive, hazardous, and mixed organic waste materials |
| RU2131627C1 (ru) * | 1997-06-10 | 1999-06-10 | Производственное объединение "МАЯК" | Способ переработки сточных вод, содержащих перманганаты щелочных металлов |
| RU2122753C1 (ru) | 1997-10-30 | 1998-11-27 | Товарищество с ограниченной ответственностью "Лаборатория технологий водоочистки - Наука Ltd." | Способ переработки жидких отходов, содержащих радионуклиды |
| RU2256965C2 (ru) * | 2003-05-27 | 2005-07-20 | ФГУП "Производственное объединение "Маяк" | Способ переработки жидких радиоактивных отходов низкого уровня активности |
| RU2268513C1 (ru) | 2004-12-28 | 2006-01-20 | Закрытое акционерное общество "РАОТЕХ" | Способ переработки жидких радиоактивных отходов |
| US8262185B2 (en) * | 2009-08-05 | 2012-09-11 | Canon Kabushiki Kaisha | Recording apparatus and processing method executed by the recording apparatus |
| RU2473145C1 (ru) * | 2012-01-20 | 2013-01-20 | Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" | Способ переработки жидких радиоактивных отходов от применения дезактивирующих растворов |
| RU2577512C1 (ru) | 2014-12-29 | 2016-03-20 | Общество с ограниченной ответственностью "Научно-Производственное предприятие "Эксорб" | Способ переработки жидких радиоактивных отходов и их утилизации |
| RU2608968C1 (ru) * | 2016-03-09 | 2017-01-30 | Общество с ограниченной ответственностью Научно-производственное предприятие "Эксорб" | Способ переработки жидких радиоактивных отходов |
-
2017
- 2017-12-19 RU RU2017144738A patent/RU2675787C1/ru active
-
2018
- 2018-12-17 WO PCT/RU2018/000831 patent/WO2019125216A1/fr not_active Ceased
- 2018-12-17 EP EP18890167.2A patent/EP3736819A4/fr not_active Withdrawn
Also Published As
| Publication number | Publication date |
|---|---|
| WO2019125216A1 (fr) | 2019-06-27 |
| EP3736819A4 (fr) | 2021-11-24 |
| RU2675787C1 (ru) | 2018-12-25 |
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| A4 | Supplementary search report drawn up and despatched |
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| RIC1 | Information provided on ipc code assigned before grant |
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