CN112710776A - Oxidation-reduction titration detection method for uranium content in uranium tetrachloride - Google Patents

Oxidation-reduction titration detection method for uranium content in uranium tetrachloride Download PDF

Info

Publication number
CN112710776A
CN112710776A CN202011345574.4A CN202011345574A CN112710776A CN 112710776 A CN112710776 A CN 112710776A CN 202011345574 A CN202011345574 A CN 202011345574A CN 112710776 A CN112710776 A CN 112710776A
Authority
CN
China
Prior art keywords
sample
uranium
solution
weighing
weighing bottle
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.)
Pending
Application number
CN202011345574.4A
Other languages
Chinese (zh)
Inventor
纪秋宇
贾凌宇
申亚男
侯丽楠
安宁
张雨虹
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.)
China North Nuclear Fuel Co Ltd
Original Assignee
China North Nuclear Fuel Co Ltd
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 China North Nuclear Fuel Co Ltd filed Critical China North Nuclear Fuel Co Ltd
Priority to CN202011345574.4A priority Critical patent/CN112710776A/en
Publication of CN112710776A publication Critical patent/CN112710776A/en
Pending legal-status Critical Current

Links

Images

Classifications

    • GPHYSICS
    • G01MEASURING; TESTING
    • G01NINVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N31/00Investigating or analysing non-biological materials by the use of the chemical methods specified in the subgroup; Apparatus specially adapted for such methods
    • G01N31/16Investigating or analysing non-biological materials by the use of the chemical methods specified in the subgroup; Apparatus specially adapted for such methods using titration
    • G01N31/162Determining the equivalent point by means of a discontinuity
    • G01N31/164Determining the equivalent point by means of a discontinuity by electrical or electrochemical means
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01NINVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N27/00Investigating or analysing materials by the use of electric, electrochemical, or magnetic means
    • G01N27/26Investigating or analysing materials by the use of electric, electrochemical, or magnetic means by investigating electrochemical variables; by using electrolysis or electrophoresis

Landscapes

  • Health & Medical Sciences (AREA)
  • Chemical & Material Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Electrochemistry (AREA)
  • Molecular Biology (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Analytical Chemistry (AREA)
  • Biochemistry (AREA)
  • General Health & Medical Sciences (AREA)
  • General Physics & Mathematics (AREA)
  • Immunology (AREA)
  • Pathology (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Investigating Or Analyzing Non-Biological Materials By The Use Of Chemical Means (AREA)

Abstract

The invention belongs to the technical field of titration detection methods, and particularly relates to an oxidation-reduction titration detection method for uranium content in uranium tetrachloride, which comprises the steps of firstly, storing and weighing samples, secondly, dissolving the samples, thirdly, adding reagents, fourthly, titrating the samples, fifthly, calculating results; the invention establishes an oxidation-reduction titration detection method for uranium content in uranium tetrachloride, and the uranium content in the uranium tetrachloride can be accurately determined by using experimental conditions listed in the content of the invention, and the determination precision of the method is superior to 0.6%. The method can be used for determining the uranium content in the uranium tetrachloride, and is effectively matched with the special production.

Description

Oxidation-reduction titration detection method for uranium content in uranium tetrachloride
Technical Field
The invention belongs to the technical field of titration detection methods, and particularly relates to an oxidation-reduction titration detection method for uranium content in uranium tetrachloride.
Background
The uranium tetrachloride is chloride with the oxidation state of uranium being +4, can be used for separating electromagnetic elements in the uranium enrichment process, and is also a main raw material of organic uranium chemistry. Can be obtained by reacting uranium dioxide with a chlorinating agent under appropriate conditions.
At present, the standard of uranium content determination in uranium tetrachloride is temporarily absent, and the current detection method of the uranium content in uranium tetrafluoride is that concentrated phosphoric acid and potassium dichromate are used for dissolving a sample, uranium (VI) is reduced to uranium (IV) by using excessive ferrous sulfate in a concentrated phosphoric acid medium, the excessive ferrous sulfate is oxidized by nitric acid by using molybdenum (VI) as a catalyst, vanadyl sulfate is added, the uranium (IV) to the uranium (VI) are titrated by using a potassium dichromate standard solution, and the titration end point is determined by a potentiometric method.
The sample storage mode, the sample weighing mode and the sample dissolving mode of the method are not suitable for determining the uranium content in the uranium tetrachloride.
Disclosure of Invention
In view of the above disadvantages, the present invention aims to provide a method for detecting uranium tetrafluoride in uranium tetrachloride by redox titration, which is suitable for detecting the uranium content in uranium tetrafluoride, wherein uranium tetrafluoride is stable in nature in air and insoluble in water, uranium tetrachloride has strong hygroscopicity, is easy to deliquesce and is easy to dissolve in water, and storage, weighing, dissolving methods and detection conditions of a uranium tetrafluoride sample in the existing method are not suitable for the uranium tetrachloride sample.
The technical scheme of the invention is as follows:
a redox titration detection method for uranium tetrachloride uranium content comprises a first step of storing and weighing samples, a second step of dissolving the samples, a third step of adding reagents, a fourth step of titrating the samples, and a fifth step of calculating results;
step one, sample storage and weighing, including sample storage and sample weighing;
step two, sample dissolution
Adding 1-3mL of deionized water along the wall of a beaker, adding 5mL of concentrated nitric acid, heating and dissolving on an electric heating plate at 180 ℃, adding 1-3mL of deionized water and 5mL of concentrated nitric acid again after the solution is evaporated to dryness, repeatedly evaporating to dryness for three times, adding 30mL of concentrated phosphoric acid along the wall of the beaker, covering a watch glass, heating and dissolving on the electric heating plate, frequently shaking the beaker during the process, and dissolving the sample for 40-50min to completely dissolve the sample; taking down the beaker after complete dissolution, and cooling to room temperature;
step three, adding a reagent;
placing the dissolved sample solution on an electromagnetic stirrer, adding a stirrer, vertically adding 4.0mL of ferrous sulfate solution under stirring, inserting a thermometer, and reducing for at least 2 min; regulating the temperature of the solution to 35 +/-2 ℃, and sequentially adding 5mL of sulfuric acid solution, 5mL of sulfamic acid solution and 6mL of oxidant solution, wherein the solution is changed from light green to brown and then light green; continuing stirring for 2.5min, standing for 0.5min, adding 10mL vanadium sulfate acyl solution, and adding 90mL deionized water along the cup wall;
step four, titrating the sample;
inserting an electrode, stirring, keeping the potential at 350-400 mV, weighing the mass of a titration flask filled with a potassium dichromate A solution with the concentration of 9.7mg/g before titration, and accurately measuring the mass to 0.1mg, and dripping the potassium dichromate A solution from the titration flask to the potential of 450-480 mV; recording the mass of a titration bottle filled with the potassium dichromate A solution after titration is finished, and accurately measuring the mass to 0.1 mg;
continuously dropwise adding 0.5mg/mL potassium dichromate B solution into a 2mL micro burette, adding 0.10mL each time, after dropwise adding the B solution each time, washing the end part of the burette with water, and recording a potential value and a corresponding volume reading when the potential reading does not change more than 1mV within 5 s; dripping until the potential change is maximum, dripping 0.10mL of B solution after the potential exceeds the end point, and recording the corresponding potential value; calculating the volume V of the solution of the potassium dichromate B consumed by reaching an equivalent point by second-order derivative;
step five, calculating results;
measuring result of uranium content in sample by mass fraction WUExpressed in percent (%) and calculated according to formula (1):
Figure BDA0002799718640000031
in the formula:
ρa-mass fraction of potassium dichromate a solution in milligrams per gram (mg/g);
m5——m5=m6-m7the titration amount of the potassium dichromate a solution is in grams (g);
m6the mass of a titration flask filled with the potassium dichromate A solution before titration is in grams (g);
m7the mass of the titration flask filled with the potassium dichromate A solution after titration is in gram (g);
ρb-the concentration of potassium dichromate B solution in milligrams per milliliter (mg/mL);
v — volume of potassium dichromate B solution consumed at endpoint in milliliters (mL);
k-conversion factor of potassium dichromate to natural uranium (K-2.4273);
g-enrichment factor for uranium-the relative atomic weight of uranium in the sample/238.029;
m4mass of sample in grams (g).
And storing the samples, namely placing a weighing bottle with the specification of 25mm multiplied by 40mm in an oven to be dried for 1h at 100 ℃, cooling and transferring to a dryer, quickly placing the uranium tetrachloride samples to be analyzed into the weighing bottle after sampling is finished, placing the weighing bottle into the dryer for temporary storage, and detecting the samples stored in the weighing bottle stored in the dryer at the first time after the preparation work before detection is finished.
And weighing 0.19900-0.20100 g of sample by a weight reduction method, accurately measuring the sample to 0.01mg, and recording the actual mass.
Putting a high waist beaker with the sample dissolved on a balance plate, peeling, putting a weighing bottle and the sample on another balance plate, and recording the mass m of the weighing bottle and the sample1Then taking the weighing bottle down from the balance, slowly leveling the weighing bottle above the high-waist beaker to ensure that the sample is uniformly distributed on the side wall of the weighing bottle, opening the cover of the weighing bottle, tapping the upper part of the bottle mouth by using the cover of the weighing bottle to ensure that the sample slowly falls into the high-waist beaker, and pouring out the sampleWhen the quantity of the sample is close to the required quantity, the bottle cap is used for tapping the upper part of the bottle opening, the weighing bottle is slowly erected while the bottle cap is used for tapping, the sample adhered on the bottle opening falls back into the weighing bottle, the bottle cap is quickly covered, and the mass m of the weighing bottle and the sample is weighed2(ii) a Wherein the mass of the sample is m1-m2
In the second step, after the sample is dissolved for 40-50min, if the sample is not completely dissolved, the time can be prolonged until the sample is completely dissolved.
The invention has the beneficial effects that:
the invention establishes an oxidation-reduction titration detection method for uranium content in uranium tetrachloride, and the uranium content in the uranium tetrachloride can be accurately determined by using experimental conditions listed in the content of the invention, and the determination precision of the method is superior to 0.6%. The method can be used for determining the uranium content in the uranium tetrachloride, and is effectively matched with the special production.
Drawings
FIG. 1 is a schematic flow diagram of the process of the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
A redox titration detection method for uranium tetrachloride uranium content comprises a first step of storing and weighing samples, a second step of dissolving the samples, a third step of adding reagents, a fourth step of titrating the samples, and a fifth step of calculating results;
step one, storing and weighing samples
1. Sample storage
And (3) placing a weighing bottle with the specification of 25mm multiplied by 40mm into an oven, drying for 1h at 100 ℃, cooling and transferring into a dryer, quickly placing a uranium tetrachloride sample to be analyzed into the weighing bottle after sampling, and placing the weighing bottle into the dryer for temporary storage. After the preparation before the detection is completed, the sample stored in the weighing bottle stored in the dryer is detected for the first time.
2. Sample weighing
0.19900 g-0.20100 g of sample is weighed by a decrement method, the precision is 0.01mg, and the actual mass is recorded.
Putting a high waist beaker with the sample dissolved on a balance plate, peeling, putting a weighing bottle and the sample on another balance plate, and recording the mass m of the weighing bottle and the sample1Then taking the weighing bottle down from the balance, slowly laying the weighing bottle flat above the high-waist beaker to enable the samples to be uniformly distributed on the side wall of the weighing bottle, opening the cover of the weighing bottle, tapping the upper part of the bottle opening by using the cover of the weighing bottle to enable the samples to slowly fall into the high-waist beaker, tapping the upper part of the bottle opening by using the cover of the weighing bottle while enabling the weighing bottle to be vertical when the amount of the poured samples is close to the required amount, enabling the samples adhered on the bottle opening to fall back into the weighing bottle, quickly covering the cover of the weighing bottle, and weighing the mass m of the weighing bottle and the samples2
Wherein the mass of the sample is m1-m2
Step two, sample dissolution
Adding 1-3mL of deionized water along the wall of a beaker, adding 5mL of concentrated nitric acid, heating and dissolving at 180 ℃ on an electric heating plate, adding 1-3mL of deionized water and 5mL of concentrated nitric acid again after the solution is evaporated to dryness, repeatedly evaporating to dryness for three times, adding 30mL of concentrated phosphoric acid along the wall of the beaker, covering a watch glass, heating and dissolving on the electric heating plate, frequently shaking the beaker during the process, and dissolving the sample for 40-50min to completely dissolve the sample. If the dissolution is incomplete, the time can be prolonged until the sample is completely dissolved. And taking down the beaker after complete dissolution and cooling to room temperature.
Step three, adding reagent
And (3) placing the dissolved sample solution on an electromagnetic stirrer, adding a stirrer, vertically adding 4.0mL of ferrous sulfate solution under the stirring condition, inserting a thermometer, and reducing for not less than 2 min. The temperature of the solution is adjusted to 35 +/-2 ℃, 5mL of sulfuric acid solution, 5mL of sulfamic acid solution and 6mL of oxidant solution are added in sequence, and the solution is changed from light green to brown and then light green. After stirring for 2.5min, standing for 0.5min, adding 10mL vanadyl sulfate solution, and adding 90mL deionized water along the cup wall.
Step four, sample titration
Inserting an electrode, stirring, keeping the potential at 350-400 mV, weighing the mass of a titration flask filled with a potassium dichromate A solution with the concentration of 9.7mg/g before titration, and accurately measuring the mass to 0.1mg, and dripping the potassium dichromate A solution from the titration flask to the potential of 450-480 mV; and recording the mass of the titration flask filled with the potassium dichromate A solution after titration is finished, and accurately measuring the mass to 0.1 mg.
And continuously dropwise adding 0.5mg/mL potassium dichromate B solution into a 2mL micro burette, adding 0.10mL of the solution B each time, washing the end part of the burette with water after dropwise adding the solution B each time, and recording a potential value and a corresponding volume reading when the potential reading does not change more than 1mV within 5 s. Dropping the solution until the potential changes to the maximum, dropping 0.10mL of B solution after the potential exceeds the end point, and recording the corresponding potential value. The volume V of potassium dichromate B solution consumed to reach the equivalence point was calculated as the second derivative.
Step five, calculating the result
Measuring result of uranium content in sample by mass fraction WUExpressed in percent (%) and calculated according to formula (1):
Figure BDA0002799718640000061
in the formula:
ρa-mass fraction of potassium dichromate a solution in milligrams per gram (mg/g);
m5——m5=m6-m7the titration amount of the potassium dichromate a solution is in grams (g);
m6the mass of a titration flask filled with the potassium dichromate A solution before titration is in grams (g);
m7the mass of the titration flask filled with the potassium dichromate A solution after titration is in gram (g);
ρbconcentration of the potassium dichromate B solutionIn milligrams per milliliter (mg/mL);
v — volume of potassium dichromate B solution consumed at endpoint in milliliters (mL);
k-conversion factor of potassium dichromate to natural uranium (K-2.4273);
g-enrichment factor for uranium-the relative atomic weight of uranium in the sample/238.029;
m4mass of sample in grams (g).
The precision after using the method is as follows:
6 parts of the same sample are weighed respectively, analyzed according to the method, and subjected to precision experiments, and the results are shown in table 1.
TABLE 1 precision test
Figure BDA0002799718640000071
In the drawings of the disclosed embodiments of the invention, only methods related to the disclosed embodiments are referred to, other methods can refer to common design, and the same embodiment and different embodiments of the invention can be combined with each other without conflict;
the above description is only for the purpose of illustrating the preferred embodiments of the present invention and is not to be construed as limiting the invention, and any modifications, equivalents, improvements and the like that are within the spirit and principle of the present invention are intended to be included in the scope of the present invention.

Claims (7)

1. A redox titration detection method for uranium tetrachloride uranium content comprises a first step of storing and weighing samples, a second step of dissolving the samples, a third step of adding reagents, a fourth step of titrating the samples, and a fifth step of calculating results; the method is characterized in that:
step one, sample storage and weighing, including sample storage and sample weighing;
step two, sample dissolution
Adding 1-3mL of deionized water along the wall of a beaker, adding 5mL of concentrated nitric acid, heating and dissolving on an electric heating plate at 180 ℃, adding 1-3mL of deionized water and 5mL of concentrated nitric acid again after the solution is evaporated to dryness, repeatedly evaporating to dryness for three times, adding 30mL of concentrated phosphoric acid along the wall of the beaker, covering a watch glass, heating and dissolving on the electric heating plate, frequently shaking the beaker during the process, and dissolving the sample for 40-50min to completely dissolve the sample; taking down the beaker after complete dissolution, and cooling to room temperature;
step three, adding a reagent;
placing the dissolved sample solution on an electromagnetic stirrer, adding a stirrer, vertically adding 4.0mL of ferrous sulfate solution under stirring, inserting a thermometer, and reducing for at least 2 min; regulating the temperature of the solution to 35 +/-2 ℃, and sequentially adding 5mL of sulfuric acid solution, 5mL of sulfamic acid solution and 6mL of oxidant solution, wherein the solution is changed from light green to brown and then light green; continuing stirring for 2.5min, standing for 0.5min, adding 10mL vanadium sulfate acyl solution, and adding 90mL deionized water along the cup wall;
step four, titrating the sample;
inserting an electrode, stirring, keeping the potential at 350-400 mV, weighing the mass of a titration flask filled with a potassium dichromate A solution with the concentration of 9.7mg/g before titration, and accurately measuring the mass to 0.1mg, and dripping the potassium dichromate A solution from the titration flask to the potential of 450-480 mV; recording the mass of a titration bottle filled with the potassium dichromate A solution after titration is finished, and accurately measuring the mass to 0.1 mg;
continuously dropwise adding 0.5mg/mL potassium dichromate B solution into a 2mL micro burette, adding 0.10mL each time, after dropwise adding the B solution each time, washing the end part of the burette with water, and recording a potential value and a corresponding volume reading when the potential reading does not change more than 1mV within 5 s; dripping until the potential change is maximum, dripping 0.10mL of B solution after the potential exceeds the end point, and recording the corresponding potential value; calculating the volume V of the solution of the potassium dichromate B consumed by reaching an equivalent point by second-order derivative;
step five, calculating results;
measuring result of uranium content in sample by mass fraction WUExpressed in percent (%) and calculated according to formula (1):
Figure FDA0002799718630000021
in the formula:
ρa-mass fraction of potassium dichromate a solution in milligrams per gram (mg/g);
m5——m5=m6-m7the titration amount of the potassium dichromate a solution is in grams (g);
m6the mass of a titration flask filled with the potassium dichromate A solution before titration is in grams (g);
m7the mass of the titration flask filled with the potassium dichromate A solution after titration is in gram (g);
ρb-the concentration of potassium dichromate B solution in milligrams per milliliter (mg/mL);
v — volume of potassium dichromate B solution consumed at endpoint in milliliters (mL);
k-conversion factor of potassium dichromate to natural uranium (K-2.4273);
g-enrichment factor for uranium-the relative atomic weight of uranium in the sample/238.029;
m4mass of sample in grams (g).
2. The redox titration detection method for uranium content in uranium tetrachloride according to claim 1, characterized in that: and storing the samples, namely placing a weighing bottle with the specification of 25mm multiplied by 40mm in an oven to be dried for 1h at 100 ℃, cooling and transferring to a dryer, quickly placing the uranium tetrachloride samples to be analyzed into the weighing bottle after sampling is finished, placing the weighing bottle into the dryer for temporary storage, and detecting the samples stored in the weighing bottle stored in the dryer at the first time after the preparation work before detection is finished.
3. The redox titration detection method for uranium content in uranium tetrachloride according to claim 1, characterized in that: and weighing 0.19900-0.20100 g of sample by a weight reduction method, accurately measuring the sample to 0.01mg, and recording the actual mass.
4. The redox titration detection method for uranium content in uranium tetrachloride according to claim 3, characterized in that: putting a high waist beaker with the sample dissolved on a balance plate, peeling, putting a weighing bottle and the sample on another balance plate, and recording the mass m of the weighing bottle and the sample1Then taking the weighing bottle down from the balance, slowly laying the weighing bottle flat above the high-waist beaker to enable the samples to be uniformly distributed on the side wall of the weighing bottle, opening the cover of the weighing bottle, tapping the upper part of the bottle opening by using the cover of the weighing bottle to enable the samples to slowly fall into the high-waist beaker, tapping the upper part of the bottle opening by using the cover of the weighing bottle while enabling the weighing bottle to be vertical when the amount of the poured samples is close to the required amount, enabling the samples adhered on the bottle opening to fall back into the weighing bottle, quickly covering the cover of the weighing bottle, and weighing the mass m of the weighing bottle and the samples2(ii) a Wherein the mass of the sample is m1-m2
5. The redox titration detection method for uranium content in uranium tetrachloride according to claim 1, characterized in that: in the second step, after the sample is dissolved for 40-50min, if the sample is not completely dissolved, the time can be prolonged until the sample is completely dissolved.
6. The redox titration detection method for uranium content in uranium tetrachloride according to claim 1, characterized in that: the sample storage comprises the steps of placing a weighing bottle with the specification of 25mm multiplied by 40mm in an oven to be dried for 1h at 100 ℃, cooling and transferring to a dryer, quickly placing a uranium tetrachloride sample to be analyzed into the weighing bottle after sampling is finished, placing the weighing bottle into the dryer for temporary storage, and detecting the sample stored in the weighing bottle stored in the dryer at the first time after preparation work before detection is finished;
and weighing 0.19900-0.20100 g of sample by a weight reduction method, accurately measuring the sample to 0.01mg, and recording the actual mass.
7. The redox titration detection method for uranium content in uranium tetrachloride according to claim 6, characterized in that: balancePutting a high waist beaker with the sample dissolved on a balance plate, peeling, putting a weighing bottle and the sample on another balance plate, and recording the mass m of the weighing bottle and the sample1Then taking the weighing bottle down from the balance, slowly laying the weighing bottle flat above the high-waist beaker to enable the samples to be uniformly distributed on the side wall of the weighing bottle, opening the cover of the weighing bottle, tapping the upper part of the bottle opening by using the cover of the weighing bottle to enable the samples to slowly fall into the high-waist beaker, tapping the upper part of the bottle opening by using the cover of the weighing bottle while enabling the weighing bottle to be vertical when the amount of the poured samples is close to the required amount, enabling the samples adhered on the bottle opening to fall back into the weighing bottle, quickly covering the cover of the weighing bottle, and weighing the mass m of the weighing bottle and the samples2(ii) a Wherein the mass of the sample is m1-m2
CN202011345574.4A 2020-11-26 2020-11-26 Oxidation-reduction titration detection method for uranium content in uranium tetrachloride Pending CN112710776A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202011345574.4A CN112710776A (en) 2020-11-26 2020-11-26 Oxidation-reduction titration detection method for uranium content in uranium tetrachloride

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202011345574.4A CN112710776A (en) 2020-11-26 2020-11-26 Oxidation-reduction titration detection method for uranium content in uranium tetrachloride

Publications (1)

Publication Number Publication Date
CN112710776A true CN112710776A (en) 2021-04-27

Family

ID=75542428

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202011345574.4A Pending CN112710776A (en) 2020-11-26 2020-11-26 Oxidation-reduction titration detection method for uranium content in uranium tetrachloride

Country Status (1)

Country Link
CN (1) CN112710776A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114544858A (en) * 2021-12-28 2022-05-27 中核二七二铀业有限责任公司 Method for analyzing and detecting content of uranium in uranium hexafluoride

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106507943B (en) * 2008-10-24 2012-04-18 中核陕西铀浓缩有限公司 A kind of method for determining uranium content in hex hydrolyzed solution
CN106409372A (en) * 2015-08-10 2017-02-15 中国科学院上海应用物理研究所 Dissolving method for uranium tetrafluoride
CN106932529A (en) * 2015-12-30 2017-07-07 中核北方核燃料元件有限公司 A kind of UO2The assay method of uranium content in-BeO pellets
CN108205009A (en) * 2017-12-18 2018-06-26 中核北方核燃料元件有限公司 The assay method of uranium content in a kind of spheric fuel element
CN109541126A (en) * 2018-12-19 2019-03-29 中核北方核燃料元件有限公司 The measuring method of uranium content in a kind of U-Mo Alloy

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106507943B (en) * 2008-10-24 2012-04-18 中核陕西铀浓缩有限公司 A kind of method for determining uranium content in hex hydrolyzed solution
CN106409372A (en) * 2015-08-10 2017-02-15 中国科学院上海应用物理研究所 Dissolving method for uranium tetrafluoride
CN106932529A (en) * 2015-12-30 2017-07-07 中核北方核燃料元件有限公司 A kind of UO2The assay method of uranium content in-BeO pellets
CN108205009A (en) * 2017-12-18 2018-06-26 中核北方核燃料元件有限公司 The assay method of uranium content in a kind of spheric fuel element
CN109541126A (en) * 2018-12-19 2019-03-29 中核北方核燃料元件有限公司 The measuring method of uranium content in a kind of U-Mo Alloy

Non-Patent Citations (8)

* Cited by examiner, † Cited by third party
Title
中华人民共和国国家质量监督检疫检疫总局: "《中华人民共和国国家标准 GB/T14501.6-2008》", 19 September 2008 *
国家技术监督局: "《中华人民共和国国家标准GB11841-89》", 21 October 1989 *
孙国禄等: "四氟化铀溶样方法的研究", 《铀矿冶》 *
杨裕生等: "重量法测定四氟化铀中总铀量", 《原子能科学技术》 *
栋灵英: "《铀的分析化学》", 28 February 1982, 原子能出版社 *
王秀鸾 等: "《冶金和金属材料 (化工百科全书)专业卷》", 30 January 2001, 化学工业出版社 *
胡嘉伸等: "四氟化铀中总铀量的测定", 《原子能科学技术》 *
苏莉: "浅谈电子天平的维护和使用方法", 《衡器》 *

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114544858A (en) * 2021-12-28 2022-05-27 中核二七二铀业有限责任公司 Method for analyzing and detecting content of uranium in uranium hexafluoride

Similar Documents

Publication Publication Date Title
CN105699472B (en) Flat tea place of production method of discrimination based on stable isotope proportional difference
CN103308646A (en) Method for measuring zinc and cadmium in copper slag and copper-cadmium slag by using EDTA (Ethylene Diamine Tetraacetic Acid) volumetric method
CN112710776A (en) Oxidation-reduction titration detection method for uranium content in uranium tetrachloride
CN111735907B (en) Method for measuring chloride ion content in industrial lanthanum oxide by potentiometric titration
CN107132263A (en) The method of testing of aluminium composition in aluminium etching solution
CN112710775A (en) Method for determining content of uranium in uranium-carbon-oxygen
CN106226192A (en) A kind of method of content of niobium in gravimetric detemination titanium-niobium alloy
CN103115920A (en) Method for measuring iron/calcium ratio in iron-calcium core-spun yarn
CN103776953A (en) Determination method of content of cobalt in lithium battery ternary positive electrode material
CN102288726A (en) Method for determining acidity of vanadium redox battery electrolyte by virtue of pH titration quantitative determination and application thereof
Wengert Photometric determination of zirconium in magnesium alloys
CN104655473A (en) Method for detecting trace mercury in water
CN106932529A (en) A kind of UO2The assay method of uranium content in-BeO pellets
CN109541126A (en) The measuring method of uranium content in a kind of U-Mo Alloy
CN105044275B (en) The method of testing of alumina content in aluminium metaphosphate
CN108240984B (en) Method for determining purity of bis (chlorosulfonyl) imide by chemical method
CN114323867A (en) Method for analyzing and detecting uranium content in natural triuranium octoxide
CN101158648A (en) Detecting method of titration measuring saccharin sodium neutralize liquid content
CN101344504A (en) Method for measuring fluorine content in system containing multiple cations
CN101907550A (en) Method for measuring degree of oxidation of lead powder
Jagner et al. A standard addition titration method for the determination of fluorine in silicate rocks
CN105651843B (en) The assay method of chlorinity in a kind of thorium tetrafluoride
CN109781928A (en) Accelerate the method for reaction speed when a kind of sodium oxalate calibration liquor potassic permanganate
CN117191774A (en) Detection method for determining iron content in copper slag concentrate by potassium borohydride reduction method
CN112924518B (en) Method for analyzing neptunium content in neptunium dioxide sample

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
WD01 Invention patent application deemed withdrawn after publication

Application publication date: 20210427

WD01 Invention patent application deemed withdrawn after publication