CN112593081A - Method for leaching plutonium in plutonium-containing activated carbon - Google Patents
Method for leaching plutonium in plutonium-containing activated carbon Download PDFInfo
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- CN112593081A CN112593081A CN202011240417.7A CN202011240417A CN112593081A CN 112593081 A CN112593081 A CN 112593081A CN 202011240417 A CN202011240417 A CN 202011240417A CN 112593081 A CN112593081 A CN 112593081A
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B7/00—Working up raw materials other than ores, e.g. scrap, to produce non-ferrous metals and compounds thereof; Methods of a general interest or applied to the winning of more than two metals
- C22B7/006—Wet processes
- C22B7/007—Wet processes by acid leaching
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/04—Obtaining plutonium
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- 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
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P10/00—Technologies related to metal processing
- Y02P10/20—Recycling
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- Environmental & Geological Engineering (AREA)
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Abstract
The invention belongs to the technical field of nuclear facility decommissioning and three-waste treatment, and particularly relates to a method for leaching plutonium from plutonium-containing activated carbon. Weighing a plutonium-containing activated carbon sample in a plastic extraction tube; adding a nitric acid solution, shaking, centrifuging and splitting phases; and adding scintillation liquid into the supernatant, fully shaking uniformly, and measuring on a liquid scintillation counter. The invention makes more than 90% plutonium in the activated carbon transfer to the water phase.
Description
Technical Field
The invention belongs to the technical field of nuclear facility decommissioning and three-waste treatment, and particularly relates to a method for leaching plutonium from plutonium-containing activated carbon.
Background
In the processes of nuclear science and technology test, reactor spent fuel post-treatment, military nuclear facility decommissioning, nuclear leakage accident emergency treatment and the like, more transuranic long-life alpha wastes can be generated, and the alpha wastes are various in types, including metal wastes, non-metal non-combustible wastes and non-metal combustible wastes. At present, the alpha waste treatment at home and abroad lacks corresponding technical means, and is mainly temporary storage, which undoubtedly causes resource waste, because the long-life alpha waste has recyclable nuclear weapon equipment important raw materials, such as plutonium, which can be used as nuclear reactor fuel (MOX) and fission material raw materials of nuclear weapons, and can also be used as fuels of aircraft carriers, submarines, space rockets and the like.
The literature for enriching and recovering plutonium in alpha residual waste, namely activated carbon, is rarely reported at home and abroad, the only literature for guiding plutonium recovery is the extraction and separation of plutonium in a typical high-level waste liquid separation process and a nuclear fuel post-treatment process, the extraction and separation object is liquid, the recovery of plutonium in solid activated carbon is not reported, the research on the plutonium recovery process can refer to a plutonium extraction and separation method in the high-level waste liquid separation process and the nuclear fuel post-treatment process, and the technical difficulty which is mainly solved is how to transfer the plutonium in the activated carbon to an aqueous phase.
Disclosure of Invention
The invention aims to provide a method for leaching plutonium in plutonium-containing activated carbon, which enables more than 90% of plutonium in the activated carbon to be transferred to an aqueous phase.
In order to achieve the purpose, the technical scheme adopted by the invention is as follows:
a method for leaching plutonium from plutonium-containing activated carbon,
weighing a plutonium-containing activated carbon sample in a plastic extraction tube;
adding a nitric acid solution, shaking, centrifuging and splitting phases;
adding scintillation liquid into the supernatant, shaking thoroughly, and measuring on a liquid scintillation counter;
calculation formula of plutonium-containing activated carbon leaching rate
In the formula: theta is the leaching rate of plutonium in the plutonium-containing activated carbon, unit%;
c0-the concentration of the radioactivity of the plutonium in the plutonium-containing activated carbon sample before leaching, in Bq/g;
c, the radioactive activity concentration of plutonium in the leaching solution after leaching is unit Bq/mL;
m represents the mass of the plutonium-containing activated carbon sample in unit g;
v-volume of the extract in mL.
Weighing 0.8-1.0 g of plutonium-containing activated carbon sample in a 50mL plastic extraction tube.
Adding 30mL of 2.5mol/L nitric acid solution, shaking for 15min, and centrifuging for phase separation.
0.20mL of the supernatant was added to 10mL of scintillation fluid, shaken well and measured on a liquid scintillation counter.
The beneficial effects obtained by the invention are as follows:
among radioactive alpha wastes, there are recyclable nuclear weapon important raw materials such as plutonium, plutonium-239 can be used as nuclear reactor fuel (MOX) and nuclear weapon fissile material raw materials, and can also be used as fuel of aircraft carriers, submarines, space rockets and the like; plutonium-238 can release energy by decay and is the power source for deep space exploration. In addition, because the radioactive alpha waste has long half-life period and great biological hazard and great environmental hazard, the alpha waste generated in the processes of operation, overhaul, decommissioning and the like of the military nuclear facility is recycled or treated, the reutilization of nuclides such as plutonium and the like in the alpha waste and the waste degradation are realized, and a feasible treatment measure is provided for the treatment and disposal of the alpha waste.
The method is adopted to leach more than 90% of plutonium in the alpha residual waste, namely the active carbon, to transfer the plutonium to a water phase, so that the problem of the active carbon sample pretreatment process in the research of the plutonium recovery process is solved.
Detailed Description
The present invention will be described in detail with reference to specific examples.
The method for leaching plutonium from the plutonium-containing activated carbon comprises the following steps:
weighing 0.8-1.0 g of plutonium-containing activated carbon sample in a 50mL plastic extraction tube;
adding 30mL of 2.5mol/L nitric acid solution, shaking for 15min, and centrifugally separating the phases;
taking 0.20mL of supernatant, adding 10mL of scintillation liquid, fully shaking up, and measuring on a liquid scintillation counter;
calculation formula of plutonium-containing activated carbon leaching rate
In the formula: theta is the leaching rate of plutonium in the plutonium-containing activated carbon, unit%;
c0-the concentration of the radioactivity of the plutonium in the plutonium-containing activated carbon sample before leaching, in Bq/g;
c, the radioactive activity concentration of plutonium in the leaching solution after leaching is unit Bq/mL;
m represents the mass of the plutonium-containing activated carbon sample in unit g;
v-volume of the extract in mL.
Claims (4)
1. A method for leaching plutonium from plutonium-containing activated carbon is characterized in that:
weighing a plutonium-containing activated carbon sample in a plastic extraction tube;
adding a nitric acid solution, shaking, centrifuging and splitting phases;
adding scintillation liquid into the supernatant, shaking thoroughly, and measuring on a liquid scintillation counter;
calculation formula of plutonium-containing activated carbon leaching rate
In the formula: theta is the leaching rate of plutonium in the plutonium-containing activated carbon, unit%;
c0-the concentration of the radioactivity of the plutonium in the plutonium-containing activated carbon sample before leaching, in Bq/g;
c, the radioactive activity concentration of plutonium in the leaching solution after leaching is unit Bq/mL;
m represents the mass of the plutonium-containing activated carbon sample in unit g;
v-volume of the extract in mL.
2. The method of leaching plutonium from plutonium-containing activated carbon according to claim 1, characterized in that: weighing 0.8-1.0 g of plutonium-containing activated carbon sample in a 50mL plastic extraction tube.
3. The method of leaching plutonium from plutonium-containing activated carbon according to claim 1, characterized in that: adding 30mL of 2.5mol/L nitric acid solution, shaking for 15min, and centrifuging for phase separation.
4. The method of leaching plutonium from plutonium-containing activated carbon according to claim 1, characterized in that: 0.20mL of the supernatant was added to 10mL of scintillation fluid, shaken well and measured on a liquid scintillation counter.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202011240417.7A CN112593081B (en) | 2020-11-09 | 2020-11-09 | Method for leaching plutonium in plutonium-containing activated carbon |
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| Application Number | Priority Date | Filing Date | Title |
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| CN202011240417.7A CN112593081B (en) | 2020-11-09 | 2020-11-09 | Method for leaching plutonium in plutonium-containing activated carbon |
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| CN112593081A true CN112593081A (en) | 2021-04-02 |
| CN112593081B CN112593081B (en) | 2023-01-03 |
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Citations (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5154899A (en) * | 1991-06-28 | 1992-10-13 | Sturcken Edward F | Metal recovery from porous materials |
| CN1078923A (en) * | 1992-03-03 | 1993-12-01 | 核燃料公司 | Handle the method for separating some element the aqueous solution that produces again from exhausting nuclear fuel |
| CN1081530A (en) * | 1992-04-23 | 1994-02-02 | 核燃料公司 | The method of dissolving plutonium and/or other radioelement and device thereof |
| US5422084A (en) * | 1992-03-05 | 1995-06-06 | Commissariat Energie Atomique | Process for dissolving plutonium dioxide by means of OH- radicals produced by the radiolysis of water usable for the treatment of dissolving fines and plutoniferous waste |
| CN102776372A (en) * | 2012-08-21 | 2012-11-14 | 中国原子能科学研究院 | Method for coextracting uranium, plutonium and neptunium |
| CN103103369A (en) * | 2011-11-14 | 2013-05-15 | 中国原子能科学研究院 | Catalytic oxidation method of plutonium in nitric acid system |
| CN103263849A (en) * | 2013-05-31 | 2013-08-28 | 西北核技术研究所 | Rapid separation method of activated product gallium in fission product |
| CN103420347A (en) * | 2012-05-17 | 2013-12-04 | 中国原子能科学研究院 | Defluorination method and device in nitric acid evaporation recovery process |
| CN105110487A (en) * | 2015-09-06 | 2015-12-02 | 中国人民解放军63653部队 | Method for removing and recovering plutonium in acid wastewater with microorganisms |
| CN109735711A (en) * | 2018-12-27 | 2019-05-10 | 中核四0四有限公司 | The leaching method of plutonium in a kind of concrete |
| CN111863300A (en) * | 2020-06-10 | 2020-10-30 | 中国原子能科学研究院 | Method for eluting retained plutonium in PUREX process waste solvent |
-
2020
- 2020-11-09 CN CN202011240417.7A patent/CN112593081B/en active Active
Patent Citations (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5154899A (en) * | 1991-06-28 | 1992-10-13 | Sturcken Edward F | Metal recovery from porous materials |
| CN1078923A (en) * | 1992-03-03 | 1993-12-01 | 核燃料公司 | Handle the method for separating some element the aqueous solution that produces again from exhausting nuclear fuel |
| US5422084A (en) * | 1992-03-05 | 1995-06-06 | Commissariat Energie Atomique | Process for dissolving plutonium dioxide by means of OH- radicals produced by the radiolysis of water usable for the treatment of dissolving fines and plutoniferous waste |
| CN1081530A (en) * | 1992-04-23 | 1994-02-02 | 核燃料公司 | The method of dissolving plutonium and/or other radioelement and device thereof |
| CN103103369A (en) * | 2011-11-14 | 2013-05-15 | 中国原子能科学研究院 | Catalytic oxidation method of plutonium in nitric acid system |
| CN103420347A (en) * | 2012-05-17 | 2013-12-04 | 中国原子能科学研究院 | Defluorination method and device in nitric acid evaporation recovery process |
| CN102776372A (en) * | 2012-08-21 | 2012-11-14 | 中国原子能科学研究院 | Method for coextracting uranium, plutonium and neptunium |
| CN103263849A (en) * | 2013-05-31 | 2013-08-28 | 西北核技术研究所 | Rapid separation method of activated product gallium in fission product |
| CN105110487A (en) * | 2015-09-06 | 2015-12-02 | 中国人民解放军63653部队 | Method for removing and recovering plutonium in acid wastewater with microorganisms |
| CN109735711A (en) * | 2018-12-27 | 2019-05-10 | 中核四0四有限公司 | The leaching method of plutonium in a kind of concrete |
| CN111863300A (en) * | 2020-06-10 | 2020-10-30 | 中国原子能科学研究院 | Method for eluting retained plutonium in PUREX process waste solvent |
Non-Patent Citations (1)
| Title |
|---|
| 邓继勇等: "核废物的分离及处理技术研究进展", 《材料科学与工程》 * |
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