[go: up one dir, main page]

CN115896479B - Method and system for separating strontium from trivalent lanthanoid and actinoid in solution - Google Patents

Method and system for separating strontium from trivalent lanthanoid and actinoid in solution Download PDF

Info

Publication number
CN115896479B
CN115896479B CN202211380450.9A CN202211380450A CN115896479B CN 115896479 B CN115896479 B CN 115896479B CN 202211380450 A CN202211380450 A CN 202211380450A CN 115896479 B CN115896479 B CN 115896479B
Authority
CN
China
Prior art keywords
solution
extractant
preset volume
tbp
preset
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.)
Active
Application number
CN202211380450.9A
Other languages
Chinese (zh)
Other versions
CN115896479A (en
Inventor
柴游奇
赵俏紫
石秀高
王健
牟凌
农淑英
袁志凌
詹龙龙
杨利
柳启文
王标
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
404 Co Ltd China National Nuclear Corp
Original Assignee
404 Co Ltd China National Nuclear Corp
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by 404 Co Ltd China National Nuclear Corp filed Critical 404 Co Ltd China National Nuclear Corp
Priority to CN202211380450.9A priority Critical patent/CN115896479B/en
Publication of CN115896479A publication Critical patent/CN115896479A/en
Application granted granted Critical
Publication of CN115896479B publication Critical patent/CN115896479B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02PCLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P10/00Technologies related to metal processing
    • Y02P10/20Recycling

Landscapes

  • Extraction Or Liquid Replacement (AREA)

Abstract

The invention provides a method and a system for separating strontium from trivalent lanthanoid and actinoid in a solution, and relates to the field of spent fuel aftertreatment. The method comprises the following steps: obtaining a first preset volume of a first solution containing strontium and trivalent lanthanides and actinides; obtaining a second preset volume of extractant; the acidity of the first solution is regulated to a preset value to obtain a second solution, wherein the preset value is 2.5-3mol/L; and (3) placing the extractant and the second solution into extraction equipment, and extracting the second solution by the extractant to obtain a target solution. The scheme of the invention realizes the separation of strontium and trivalent lanthanoid and actinoid in the solution.

Description

Method and system for separating strontium from trivalent lanthanoid and actinoid in solution
Technical Field
The invention relates to the field of spent fuel aftertreatment, in particular to a method and a system for separating strontium from trivalent lanthanoid and actinoid in a solution.
Background
In the post-treatment process flow of the spent fuel, the high-emission waste liquid is the waste liquid with high radioactivity level and extremely strong toxicity, more than 95 percent of radioactivity in the spent fuel is concentrated, potential harm is formed to human beings and the environment, and the treatment and disposal problems of the waste liquid become one of key factors restricting the sustainable development of nuclear energy. 90 Sr and its daughter 90 Y are all pure beta emitters, are ideal materials for manufacturing beta radiation sources and nuclear batteries, have special applications in the fields of national defense, environmental science, biomedicine and the like, and have high practical value and economic significance. The high-level radioactive waste liquid contains a large amount of trivalent lanthanoid and actinoid, and in order to obtain a strontium solution with certain purity, the trivalent lanthanoid and actinoid in the strontium solution need to be separated.
Disclosure of Invention
The invention aims to provide a method and a system for separating strontium from trivalent lanthanoid and actinoid in a solution, which realize the separation of strontium from trivalent lanthanoid and actinoid in the solution.
In order to solve the technical problems, the technical scheme of the invention is as follows:
embodiments of the present invention provide a method of separating strontium from trivalent lanthanides, actinides in a solution, comprising:
obtaining a first preset volume of a first solution containing strontium and trivalent lanthanides and actinides;
obtaining a second preset volume of extractant;
The acidity of the first solution is regulated to a preset value to obtain a second solution, wherein the preset value is 2.5-3mol/L;
and (3) placing the extractant and the second solution into extraction equipment, and extracting the second solution by the extractant to obtain a target solution.
Optionally, obtaining the second preset volume of extractant includes:
Acquiring a third preset volume of TODGA solution and a fourth preset volume of TBP solution;
And mixing the TODGA solution and the TBP solution, and diluting and fixing the volume through kerosene to obtain a second preset volume of extractant.
Wherein the TODGA is N, N, N ', N' -tetraoctyl-3-oxaglutaramide, the TBP is tributyl phosphate, and the extractant is a mixed solution of TODGA, TBP and kerosene.
Alternatively, byCalculating a third preset volume of the TODGA solution;
Wherein V1 is the third preset volume, V is the second preset volume, C1 is the concentration of TODGA in the extractant, and the value range is 0.03-0.05mol/L.
Alternatively, byCalculating a fourth preset volume of the TBP solution;
wherein V2 is the fourth preset volume, V is the second preset volume, C2 is the concentration of TBP in the extractant, and 0.5mol/L is taken.
Optionally, adjusting the acidity of the first solution to a preset value to obtain a second solution, including:
And obtaining the initial acidity of the first solution, adding a fifth preset volume of nitric acid solution into the first solution, and regulating the acidity of the first solution to a preset value through the nitric acid solution to obtain a second solution.
Alternatively, byCalculating a fifth preset volume of the nitric acid solution;
Wherein V4 is the fifth preset volume, V3 is the first preset volume, C3 is the acidity of the first solution, b is the acidity of the second solution, and C4 is the concentration of nitric acid to be added.
Optionally, the extracting agent and the second solution are both placed in an extracting device, and the second solution is extracted by the extracting agent to obtain a target solution, which includes:
Filling the extraction device with an extractant;
And introducing the second solution into extraction equipment, setting the two-phase flow ratio of the extractant to the second solution to be 1:1, carrying out extraction reaction on two phases in the extraction equipment, and obtaining the target solution after the reaction reaches equilibrium.
Embodiments of the present invention also provide a system for separating strontium from trivalent lanthanides and actinides in a solution, comprising:
The acquisition module is used for acquiring a first preset volume of a first solution containing strontium, trivalent lanthanoid and actinoid elements and acquiring a second preset volume of an extractant;
The adjusting module is used for adjusting the acidity of the first solution to a preset value to obtain a second solution, and the preset value is 2.5-3mol/L;
And the processing module is used for placing the extractant and the second solution into extraction equipment, and extracting the second solution through the extractant to obtain a target solution.
Optionally, the obtaining module is specifically configured to obtain a third preset volume of the TODGA solution and a fourth preset volume of the TBP solution when obtaining the second preset volume of the extractant; mixing the TODGA solution and the TBP solution, and diluting and fixing the volume through kerosene to obtain an extractant; wherein the TODGA is N, N, N ', N' -tetraoctyl-3-oxaglutaramide, the TBP is tributyl phosphate, and the extractant is a mixed solution of TODGA, TBP and kerosene.
The scheme of the invention at least comprises the following beneficial effects:
The method for separating strontium from trivalent lanthanoid and actinoid in the solution comprises the following steps: obtaining a first preset volume of a first solution containing strontium and trivalent lanthanides and actinides; obtaining a second preset volume of extractant; the acidity of the first solution is regulated to a preset value to obtain a second solution, wherein the preset value is 2.5-3mol/L; and (3) placing the extractant and the second solution into extraction equipment, and extracting the second solution by the extractant to obtain a target solution. Realizes the separation of strontium from trivalent lanthanoid and actinoid in the solution.
Drawings
FIG. 1 is a schematic flow chart of a method of separating strontium from trivalent lanthanides and actinides in a solution according to the invention.
Detailed Description
Exemplary embodiments of the present disclosure will be described in more detail below with reference to the accompanying drawings. While exemplary embodiments of the present disclosure are shown in the drawings, it should be understood that the present disclosure may be embodied in various forms and should not be limited to the embodiments set forth herein. Rather, these embodiments are provided so that this disclosure will be thorough and complete, and will fully convey the scope of the disclosure to those skilled in the art.
As shown in fig. 1, an embodiment of the present invention proposes a method for separating strontium from trivalent lanthanoid and actinoid elements in a solution, comprising:
Step 11, obtaining a first solution containing strontium and trivalent lanthanoid and actinoid elements in a first preset volume;
Step 12, obtaining a second preset volume of extractant;
step 13, adjusting the acidity of the first solution to a preset value to obtain a second solution, wherein the preset value is 2.5-3mol/L;
And 14, placing the extractant and the second solution into extraction equipment, and extracting the second solution by the extractant to obtain a target solution.
Obtaining a second predetermined volume of extractant, comprising:
Acquiring a third preset volume of TODGA solution and a fourth preset volume of TBP solution;
And mixing the TODGA solution and the TBP solution, and diluting and fixing the volume through kerosene to obtain a second preset volume of extractant.
Wherein the TODGA is N, N, N ', N' -tetraoctyl-3-oxaglutaramide, the TBP is tributyl phosphate, and the extractant is a mixed solution of TODGA, TBP and kerosene.
In this embodiment, the acidity of the first solution is adjusted to a preset value, then the mixture solution of TODGA, TBP and kerosene is used as an extractant, the strontium in the first solution is retained in the raffinate phase after extraction in an extraction mode, the trivalent lanthanoid and actinoid elements in the first solution enter the extract phase, and then the target solution is obtained by separating the solution, wherein the target solution is the raffinate phase solution.
In an alternative embodiment of the invention, the method comprises the steps ofCalculating a third preset volume of the TODGA solution;
Wherein V1 is the third preset volume, V is the second preset volume, C1 is the concentration of TODGA in the extractant, the value range is 0.03-0.05, the unit is mol per liter, 580.97 is the relative molecular mass of TODGA, and 0.91 is the TODGA density.
In an alternative embodiment of the invention, the method comprises the steps ofCalculating a fourth preset volume of the TBP solution;
wherein V2 is the fourth preset volume, V is the second preset volume, C2 is the concentration of TBP in the extractant, 0.5 is taken, the unit is mol per liter, 266.37 is the relative molecular mass of TBP, and 0.97 is the TBP density.
In an alternative embodiment of the present invention, the acidity of the first solution is adjusted to a preset value to obtain a second solution, including:
And obtaining the initial acidity of the first solution, adding a fifth preset volume of nitric acid solution into the first solution, and regulating the acidity of the first solution to a preset value through the nitric acid solution to obtain a second solution.
In an alternative embodiment of the invention, the method comprises the steps ofCalculating a fifth preset volume of the nitric acid solution;
Wherein V4 is the fifth preset volume, V3 is the first preset volume, C3 is the acidity of the first solution, b is the acidity of the second solution, and C4 is the concentration of nitric acid to be added.
In an alternative embodiment of the present invention, the extracting agent and the second solution are both placed in an extracting device, and the second solution is extracted by the extracting agent to obtain a target solution, including:
Filling the extraction device with an extractant;
And introducing the second solution into extraction equipment, setting the two-phase flow ratio of the extractant to the second solution to be 1:1, carrying out extraction reaction on two phases in the extraction equipment, and obtaining the target solution after the reaction reaches equilibrium.
In the following, a specific implementation of the above method is described, and in one possible example, the method for separating strontium from trivalent lanthanoid and actinoid in a solution includes:
1. preparation of extractant
The required TODGA volume is calculated according to the required extractant volume, and the calculation formula is as follows:
Wherein V1 is the volume of TODGA, V is the volume of the required extractant, and c is the concentration of TODGA in the extractant, and the value range is 0.03-0.05, and the unit is mol per liter;
the required TBP volume is calculated according to the required extractant volume, and the calculation formula is as follows:
wherein V2 is the volume of TBP, the unit is liter, V is the volume of the required extractant, the unit is liter, C2 is the concentration of TBP in the extractant, and 0.5 is taken, the unit is mol per liter;
measuring a required volume of TODGA and a required volume of TBP, putting the TODGA and the TBP into a container, adding kerosene into the container for constant volume, and preparing a mixed solution of the TODGA, the TBP and the kerosene as an extracting agent, wherein the concentration of the TODGA in the extracting agent is in the range of 0.03-0.05mol/L, TBP mol/L.
2. Acidity adjustment of the first solution
Detecting the initial acidity of a first solution, adding a certain volume of nitric acid solution into the first solution according to a detection result, and adjusting the acidity of the first solution to 2.5-3mol/L through the nitric acid solution, wherein the volume calculation formula of the nitric acid solution to be added is as follows: Wherein V4 is the volume of nitric acid to be added, V3 is the initial volume of the first solution, C3 is the initial acidity of the first solution, mol/liter, b is the acidity to be regulated of the first solution, 2.5-3mol/L is taken, mol/liter is taken, and C4 is the concentration of nitric acid to be added, mol/liter is taken.
3. Extraction separation
Filling the extraction equipment with the prepared extractant, introducing the first solution with the adjusted acidity into the extraction equipment, setting the two-phase flow ratio of the extractant to the first solution with the adjusted acidity to be 1:1, carrying out extraction reaction on two phases in the extraction equipment, and separating liquid to obtain the target solution after the reaction reaches equilibrium.
According to the embodiment of the invention, the mixed solution of 0.03-0.05mol/L TODGA, 0.5mol/L TBP and kerosene is used as an extractant, and the strontium in the first solution with the acidity of 2.5-3mol/L can be separated from trivalent lanthanides and actinides by an extraction mode, so that all trivalent lanthanides and actinides in the first solution are removed, and the single-stage extraction separation coefficient of the strontium on the trivalent lanthanides and actinides is more than 99 when the extraction is carried out by the method.
Embodiments of the present invention also provide a system for separating strontium from trivalent lanthanides and actinides in a solution, comprising:
The acquisition module is used for acquiring a first preset volume of a first solution containing strontium, trivalent lanthanoid and actinoid elements and acquiring a second preset volume of an extractant;
The adjusting module is used for adjusting the acidity of the first solution to a preset value to obtain a second solution, and the preset value is 2.5-3mol/L;
And the processing module is used for placing the extractant and the second solution into extraction equipment, and extracting the second solution through the extractant to obtain a target solution.
In an alternative embodiment of the present invention, the obtaining module is specifically configured to obtain a third preset volume of the TODGA solution and a fourth preset volume of the TBP solution when obtaining the second preset volume of the extractant; mixing the TODGA solution and the TBP solution, and diluting and fixing the volume through kerosene to obtain an extractant; wherein the TODGA is N, N, N ', N' -tetraoctyl-3-oxaglutaramide, the TBP is tributyl phosphate, and the extractant is a mixed solution of TODGA, TBP and kerosene.
Alternatively, byCalculating a third preset volume of the TODGA solution;
Wherein V1 is the third preset volume, V is the second preset volume, C1 is the concentration of TODGA in the extractant, and the value range is 0.03-0.05mol/L.
Alternatively, byCalculating a fourth preset volume of the TBP solution;
wherein V2 is the fourth preset volume, V is the second preset volume, C2 is the concentration of TBP in the extractant, and 0.5mol/L is taken.
Optionally, adjusting the acidity of the first solution to a preset value to obtain a second solution, including:
And obtaining the initial acidity of the first solution, adding a fifth preset volume of nitric acid solution into the first solution, and regulating the acidity of the first solution to a preset value through the nitric acid solution to obtain a second solution.
Alternatively, byCalculating a fifth preset volume of the nitric acid solution;
Wherein V4 is the fifth preset volume, V3 is the first preset volume, C3 is the acidity of the first solution, b is the acidity of the second solution, and C4 is the concentration of nitric acid to be added.
Optionally, the extracting agent and the second solution are both placed in an extracting device, and the second solution is extracted by the extracting agent to obtain a target solution, which includes:
Filling the extraction device with an extractant;
And introducing the second solution into extraction equipment, setting the two-phase flow ratio of the extractant to the second solution to be 1:1, carrying out extraction reaction on two phases in the extraction equipment, and obtaining the target solution after the reaction reaches equilibrium.
It should be noted that all implementation manners of the above method embodiments are applicable to the embodiments of the system, and the same technical effects can be achieved.
While the foregoing is directed to the preferred embodiments of the present invention, it will be appreciated by those skilled in the art that various modifications and adaptations can be made without departing from the principles of the present invention, and such modifications and adaptations are intended to be comprehended within the scope of the present invention.

Claims (2)

1. A method for separating strontium from trivalent lanthanides and actinides in a solution comprising:
obtaining a first preset volume of a first solution containing strontium and trivalent lanthanides and actinides;
obtaining a second preset volume of extractant;
The acidity of the first solution is regulated to a preset value to obtain a second solution, wherein the preset value is 2.5-3mol/L;
Placing the extractant and the second solution into extraction equipment, and extracting the second solution by the extractant to obtain a target solution;
obtaining a second predetermined volume of extractant, comprising:
Acquiring a third preset volume of TODGA solution and a fourth preset volume of TBP solution;
Mixing the TODGA solution and the TBP solution, and diluting and fixing the volume through kerosene to obtain a second preset volume of extractant;
wherein the TODGA is N, N, N ', N' -tetraoctyl-3-oxaglutaramide, the TBP is tributyl phosphate, and the extractant is a mixed solution of TODGA, TBP and kerosene;
By passing through Calculating a third preset volume of the TODGA solution;
Wherein V1 is the third preset volume, V is the second preset volume, C1 is the concentration of TODGA in the extractant, and the value range is 0.03-0.05mol/L;
By passing through Calculating a fourth preset volume of the TBP solution;
Wherein V2 is the fourth preset volume, V is the second preset volume, C2 is the concentration of TBP in the extractant, 0.5mol/L is taken, 266.37 is the relative molecular mass of TBP, and 0.97 is the TBP density;
adjusting the acidity of the first solution to a preset value to obtain a second solution, wherein the second solution comprises the following components:
Obtaining initial acidity of a first solution, adding a fifth preset volume of nitric acid solution into the first solution, and adjusting the acidity of the first solution to a preset value through the nitric acid solution to obtain a second solution;
By passing through Calculating a fifth preset volume of the nitric acid solution;
Wherein V4 is the fifth preset volume, V3 is the first preset volume, C3 is the acidity of the first solution, b is the acidity of the second solution, and C4 is the concentration of nitric acid to be added;
the extractant and the second solution are both placed in extraction equipment, the second solution is extracted by the extractant, and a target solution is obtained, and the method comprises the following steps:
Filling the extraction device with an extractant;
And introducing the second solution into extraction equipment, setting the two-phase flow ratio of the extractant to the second solution to be 1:1, carrying out extraction reaction on two phases in the extraction equipment, and obtaining the target solution after the reaction reaches equilibrium.
2. A system for separating strontium from trivalent lanthanides and actinides in a solution, comprising:
The acquisition module is used for acquiring a first preset volume of a first solution containing strontium, trivalent lanthanoid and actinoid elements and acquiring a second preset volume of an extractant;
The adjusting module is used for adjusting the acidity of the first solution to a preset value to obtain a second solution, and the preset value is 2.5-3mol/L;
The processing module is used for placing the extractant and the second solution into extraction equipment, and extracting the second solution through the extractant to obtain a target solution;
wherein obtaining a second predetermined volume of extractant comprises:
Acquiring a third preset volume of TODGA solution and a fourth preset volume of TBP solution;
Mixing the TODGA solution and the TBP solution, and diluting and fixing the volume through kerosene to obtain a second preset volume of extractant;
wherein the TODGA is N, N, N ', N' -tetraoctyl-3-oxaglutaramide, the TBP is tributyl phosphate, and the extractant is a mixed solution of TODGA, TBP and kerosene;
By passing through Calculating a third preset volume of the TODGA solution;
Wherein V1 is the third preset volume, V is the second preset volume, C1 is the concentration of TODGA in the extractant, and the value range is 0.03-0.05mol/L;
By passing through Calculating a fourth preset volume of the TBP solution;
Wherein V2 is the fourth preset volume, V is the second preset volume, C2 is the concentration of TBP in the extractant, 0.5mol/L is taken, 266.37 is the relative molecular mass of TBP, and 0.97 is the TBP density;
adjusting the acidity of the first solution to a preset value to obtain a second solution, wherein the second solution comprises the following components:
Obtaining initial acidity of a first solution, adding a fifth preset volume of nitric acid solution into the first solution, and adjusting the acidity of the first solution to a preset value through the nitric acid solution to obtain a second solution;
By passing through Calculating a fifth preset volume of the nitric acid solution;
Wherein V4 is the fifth preset volume, V3 is the first preset volume, C3 is the acidity of the first solution, b is the acidity of the second solution, and C4 is the concentration of nitric acid to be added;
the extractant and the second solution are both placed in extraction equipment, the second solution is extracted by the extractant, and a target solution is obtained, and the method comprises the following steps:
Filling the extraction device with an extractant;
And introducing the second solution into extraction equipment, setting the two-phase flow ratio of the extractant to the second solution to be 1:1, carrying out extraction reaction on two phases in the extraction equipment, and obtaining the target solution after the reaction reaches equilibrium.
CN202211380450.9A 2022-11-04 2022-11-04 Method and system for separating strontium from trivalent lanthanoid and actinoid in solution Active CN115896479B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202211380450.9A CN115896479B (en) 2022-11-04 2022-11-04 Method and system for separating strontium from trivalent lanthanoid and actinoid in solution

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202211380450.9A CN115896479B (en) 2022-11-04 2022-11-04 Method and system for separating strontium from trivalent lanthanoid and actinoid in solution

Publications (2)

Publication Number Publication Date
CN115896479A CN115896479A (en) 2023-04-04
CN115896479B true CN115896479B (en) 2024-09-20

Family

ID=86487123

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202211380450.9A Active CN115896479B (en) 2022-11-04 2022-11-04 Method and system for separating strontium from trivalent lanthanoid and actinoid in solution

Country Status (1)

Country Link
CN (1) CN115896479B (en)

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101529528A (en) * 2006-10-23 2009-09-09 法国原子能委员会 Grouped separation of actinides from a highly acidic aqueous composition a solvating extractant in a salting medium

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5169609A (en) * 1991-06-19 1992-12-08 The United States Of America As Represented By The United States Department Of Energy Combined transuranic-strontium extraction process
CN108611490A (en) * 2018-05-08 2018-10-02 中国原子能科学研究院 The method extracted the extractant of strontium from high activity liquid waste and extract strontium
CN109517992A (en) * 2018-12-28 2019-03-26 中国原子能科学研究院 A kind of separation method of trivalent actinium series and lanthanide series

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101529528A (en) * 2006-10-23 2009-09-09 法国原子能委员会 Grouped separation of actinides from a highly acidic aqueous composition a solvating extractant in a salting medium

Also Published As

Publication number Publication date
CN115896479A (en) 2023-04-04

Similar Documents

Publication Publication Date Title
Suzuki et al. Extraction and separation of Am (III) and Sr (II) by N, N, N, N-tetraoctyl-3-oxapentanediamide (TODGA)
Maxwell III et al. Rapid column extraction method for actinides in soil
CN107245588B (en) A method of the extraction and recovery neptunium from spentnuclear fuel post-processing waste liquid
CN107177744A (en) A kind of method of extract and separate group of the lanthanides and actinides
CN115896479B (en) Method and system for separating strontium from trivalent lanthanoid and actinoid in solution
Landgren et al. Extraction behaviour of technetium and actinides in the aliquat-336/nitric acid system
CN109517992A (en) A kind of separation method of trivalent actinium series and lanthanide series
CN115985542A (en) Method for separating strontium ions and barium ions in high-level radioactive waste liquid
CN115627354A (en) Method and system for separating strontium ions and calcium ions in high-level radioactive solution
Krajko et al. Development of a versatile sample preparation method and its application for rare-earth pattern and Nd isotope ratio analysis in nuclear forensics
JP5354586B2 (en) N, N, N ′, N′-tetraalkyl-3,6-dioxaoctane-1,8-diamide and N, N, N ′, N′-tetraalkyl-3,6-dioxaoctane-1, Extractant for solvent extraction of actinide and lanthanide elements from high-level radioactive liquid waste consisting of 8-diamide
CN105825904B (en) A kind of presurized water reactor recovery uranium is applied to the method for PHWR
CN116178137B (en) A method for separating and purifying rare earth elements in high-level radioactive liquid waste
Ochab et al. Carrier-free {sup 139} Ce obtaining and separation from lanthanum target
Trofimov et al. Supercritical fluid extraction of uranium and fission products in reprocessing of simulated spent nuclear fuel in weakly acidic solutions of Fe (III) nitrate in the presence of tributyl phosphate
Kubota Development of the partitioning process at JAERI
Chen et al. A pilot test of partitioning for the simulated highly saline high level waste
CN117248115A (en) Process flow for integrally extracting strontium and americium from high-level radioactive waste liquid
Ueno et al. Separation of transplutonium elements from neutron irradiated americium-241
Akatsu et al. Some Complexes of Americium and Curium with Oxine, Cupferron and N-Benzoylphenyl-hydroxylamine
Musikas New extractants for the nuclear hydro-metallurgy
RU2499308C2 (en) Extraction mixture for separating actinides from liquid radioactive wastes
Nishizawa et al. Isotopie enrichment of tritium by using host-guest chemistry
Landgren et al. The extraction of some trivalent elements with Aliquat‐336
Pathak et al. Synergistic extraction behaviour of americium from simulated acidic waste solutions

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant