CN102455429A - Method for measuring uranium in uranium ore - Google Patents
Method for measuring uranium in uranium ore Download PDFInfo
- Publication number
- CN102455429A CN102455429A CN201010522787XA CN201010522787A CN102455429A CN 102455429 A CN102455429 A CN 102455429A CN 201010522787X A CN201010522787X A CN 201010522787XA CN 201010522787 A CN201010522787 A CN 201010522787A CN 102455429 A CN102455429 A CN 102455429A
- Authority
- CN
- China
- Prior art keywords
- uranium
- sample
- ore
- uranium ore
- source
- 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
Links
Abstract
The invention belongs to a method for measuring uranium in uranium ore, and in particular, relates to a method for quantitatively analyzing and measuring uranium in uranium ore. The method comprises the following steps of: 1) quickly dissolving the uranium ore; 2) directly separating and purifying the dissolved uranium ore solution; 3) preparing a uranium ore sample source; and 4) measuring the alpha counting rate of the sample source. The new method for measuring the uranium by a TOPO extraction-alpha measurement method, namely a closed acid dissolution method for quickly dissolving a sample, is researched by combining the nuclear property and the chemical property of the uranium. After the sample is dissolved, the solution is directly extracted without separation, so the method is easy and fast to operate, the extraction rate of the uranium is over 97 percent, the purification effect is good, and the extracted organic phase does not contain other alpha nuclide. When the sample is prepared by directly using the organic phase, the organic phase is easily dried, and the sample preparation is simple and fast. The uranium content is calculated according to the net alpha counting rate of the sample source.
Description
Technical field
The invention belongs to the measuring method of uranium in a kind of uranium ore, be specifically related to the quantitative test measuring method of uranium in a kind of uranium ore.
Background technology
Uranium resource is dual-use valuable source.Since " 15 " and the Eleventh Five-Year Plan, China has obtained major progress seeking can ground to soak in the sandrock-type uranium deposit process.In the face of the active demand of nuclear power developing to uranium resource, uranium geology investigation and prospecting task is still very heavy, and uranium ore probing workload also increases greatly.Relate to a large amount of surveying works at the uranium ore drilling process, comprise on-site editing, recording, on-the-spot well logging and send the laboratory sample analysis.On-the-spot in the open air, mainly be to utilize gamma-ray well logging appearance, editing recording instrument etc. to measure uranium content.These methods are to judge uranium content through measuring gamma activity, as waiting the data of obtaining uranium through the daughter Ra-226 that measures uranium.But because the complicacy of geological condition, radioelement such as uranium and radium often are in non-equilibrium state, thereby the result that the γ mensuration provides need carry out complicated technology correction (dynamic calibration, static shift correction etc.), and measurement result has significant limitation.For example same γ counting, the uranium content of quoting during radium partially is higher; And partially during uranium, the uranium content of quoting is on the low side.Therefore, on the basis of in-site measurement, need send most of sample back to laboratory and accurately analyze in the open air.Since transportation and lab analysis factor, its analysis result often can not in time instruct on-the-spot the probing, incurs loss through delay decision-making in-situ sometimes.Therefore, the uranium measurement method and apparatus seems particularly important in a kind of accurate measurement in scene in the open air of research uranium ore.
At present, the field condition analytical approach is mainly based on two types: one type is physical method such as XRF and gamma spectrometry etc.Though the key instrument that portable energy-dispersion X-ray fluorescence spectrometer also is a field condition to be analyzed is mainly used in main component analysis, very low to the mensuration sensitivity of uranium, disturb big.There are problems such as uranium radium imbalance and dead time in the γ measuring method of introducing above, and there is greater risk in the result to uranium measurement.Another kind of is chemical method; Survey uranium like MAK BY LASER EXCITED FLUORESCENCE; This method has higher sensitivity, once has the simple and easy laboratory of the laser fluorescence standard addition method of use to carry out uranium component measurement in the soil in the open air, but analysis process is still complicated; Bigger to high-load uranium measurement error, abandoned the simple and easy laboratory of this method afterwards in the open air and used.
Summary of the invention
The purpose of this invention is to provide a kind of measuring method that is fit to uranium in indoor and field studies, the uranium ore quick, accurate, simple to operate.
The present invention is achieved in that the measuring method of uranium in a kind of uranium ore, and it may further comprise the steps,
1) uranium ore is dissolved fast;
2) the uranium ore solution direct separation purifying after will dissolving;
3) preparation uranium ore sample source;
4) the α counting rate in measuring samples source.
Described step 1) comprises,
Uranium ore sample after the pulverizing is put into molten appearance irritate, add nitric acid, hydrofluorite and oxydol, heating for dissolving in automatic slaking apparatus, dissolution time was greater than 30 minutes, and temperature is controlled at and is higher than 160 ℃.
Described uranium ore consumption is less than 1.5g, and the density of nitric acid is 1.4g/cm
3The concentration of hydrofluorite is not less than 40%, and the concentration of oxydol is not less than 30%, and the ratio of uranium ore and nitric acid dosage is less than 1/3.5 (g/ml); The ratio of uranium ore and hydrofluorite consumption is 1/0.5～1/1 (g/ml), and the ratio of uranium ore and oxydol consumption is 1/0.5～1/1 (g/ml).
Described step 2) comprises; With the acidity Control of the nitric acid of solution at 0.5-2mol/L; Add Fluorinse, ascorbic acid and TOPO-cyclohexane solution, wherein the consumption of sodium fluoride is 100～200mg, and the ascorbic acid consumption is 50～100mg; The ratio of organic phase and water is greater than 1/10, and the concentration of TOPO-cyclohexane solution is greater than 3%.
Described step 3) is the uranium-bearing organic solution 1～2ml that gets behind the purifying, drops in the stainless steel sample disc that adds one deck lens wiping paper, on the low-temperature heat plate, sample is dried.
The α counting rate in described step 4) measuring samples source; With uranium standard solution preparation series of standards source, its sample making course such as step 1) to step 3 are said, and the α counting rate in measurement standard source; Do horizontal ordinate with standard source content; Net counting rate is done the ordinate curve of working, and according to the α net counting rate of working curve and sample source, draws the uranium content of sample source.
Advantage of the present invention is that the present invention utilizes the nulcear properties of uranium to combine with chemical property, has worked out the new method of TOPO extraction-α mensuration survey uranium, the molten fast instant appearance method of airtight acid.Dissolve the appearance back without separating directly extraction, percentage extraction simple to operate, quick, uranium reaches more than 97%, and purification effect is fine, and extraction back organic phase does not contain other αHe Su.Directly use the organic phase sample preparation, organic phase is easy to drying, and sample preparation is simple, quick.The α net counting rate in source calculates uranium content per sample.
Embodiment
Describe the present invention below in conjunction with embodiment:
The measuring method of uranium in a kind of uranium ore, it comprises following several steps:
1) uranium ore is dissolved fast;
Uranium ore is put into automatic slaking apparatus, the consumption 4ml of nitric acid, the usefulness of hydrofluorite is measured 0.5ml, and the consumption of oxydol is 0.5ml, dissolves after 30 minutes, takes out, and the separation and purification of uranium is waited in cooling; Wherein the uranium ore consumption is less than 1.5g; The ratio of uranium ore and nitric acid dosage is less than 1/3.5 (g/ml); The ratio of uranium ore and hydrofluorite consumption is 1/0.5～1/1 (g/ml), and the ratio of uranium ore and oxydol consumption is 1/0.5～1/1 (g/ml), and dissolution time was greater than 30 minutes; Temperature is controlled at and is higher than 160 ℃, selects 180 ℃ in the present embodiment.
Wherein automatic slaking apparatus, the place of production: Shanghai, model: X-15 type.
The uranium in the quick stripping uranium ore of method is dissolved in the airtight acid of quick dissolving----of uranium.In the laboratory, uranium ore dissolving method relatively commonly used has that the ore deposit methods are dissolved in three acid, ammonium salt dissolves ore deposit method etc., but these methods all are to carry out in open system, need carry out having under the condition of good ventilation.Under the condition, in order to protect the healthy of environment and staff, the present invention adopts airtight acid to dissolve fast instant appearance method in the open air.Dissolve the selection of batten spare: dissolve ore deposit equipment and adopted automatic slaking apparatus that sample is heated, this device loses naked light, and open-air use is safer, goes up the fluted sample-dissolving pot that supplies to place, and the efficiency of heating surface is high.Sample-dissolving pot has adopted translucent column perfluoroethylene-propylene jar of adding a cover; External diameter 30mm, volume 40ml, but 200 ℃ of the highest heatproof degree; The sample part can be put into the groove of automatic slaking apparatus; This device one is that to dissolve appearance efficient high, and to irritate material translucent owing to dissolve appearance in addition, observes sampling after making things convenient for abstraction purification.Dissolve the selection of appearance temperature, temperature is more than 160 ℃ the time, and so the stripping fully of the uranium in the sample is 180 ℃ of employings when dissolving the ore deposit.Reagent is selected; The reagent that adopts nitric acid, hydrofluorite and oxydol to form dissolves uranium ore; The consumption of nitric acid from 3.5ml～8ml all can, the consumption of hydrofluorite is generally got 0.5ml greater than the abstraction purification that 1.5ml promptly can influence uranium; The consumption of oxydol is 0.5ml～1.0ml, generally gets 0.5ml.The selection of sample weighting amount has tested taking by weighing 0.5g～2.0g sample, and with this method dissolving, the result proves that the sample of sample weighting amount below 1.5g can be by dissolving fully.Therefore when claiming appearance, the height of the content uranium ore that takes by weighing 0.1～1.5g experimentizes per sample.The molten ore deposit flow process of the uranium in the quick stripping uranium ore of method is dissolved in airtight acid: uranium ore is through after pulverizing, and takes by weighing sample about 1g in the cylindrical sample-dissolving pot of perfluoroethylene-propylene, and is wetting with little water; Add 4ml nitric acid, 0.5ml hydrofluorite, 0.5ml oxydol; Covered and enclosed dissolved 30 minutes with automatic slaking apparatus down at 180 ℃, took out; The separation and purification of uranium is waited in cooling.
2) separation and purification of uranium:
With the uranium ore sample direct separation purifying after the dissolving, in sample-dissolving pot, add 20ml water, the Fluorinse of 5ml2%, 50mg ascorbic acid, shake up, add the 4ml3.6%TOPO-cyclohexane solution, with 180 times/minute frequency ramps concussions 2 minutes, leave standstill; The acidity Control of nitric acid is at 0.5-2mol/L; Add Fluorinse and reductive agent; Wherein the consumption of sodium fluoride is 100～200mg, and reductive agent is selected ascorbic acid in this example, and its consumption is 50～100mg; The ratio of organic phase and water is greater than 1/10, and the concentration of TOPO-cyclohexane solution is greater than 3%.
Without the separating and purifying technology that separates the uranium that directly extracts, extractant has been selected for use the specific trioctylphosphine oxide (TOPO) of uranium extraction (TOPO) after the sample dissolution; The selection of extractant concentration, the TOPO-cyclohexane greater than 3%, the percentage extraction to a certain amount of uranium in the nitric acid medium of 0.5～2mol/L is comparatively stable, and all more than 97%, so the concentration of extractant is chosen to be 3.6%; The selection of acidity is under the certain situation of other conditions, in the nitric acid medium of 0.5～2mol/L; The percentage extraction of uranium all can reach requirement, but after the sample dissolution, in order to reduce the dilution volume; According to the size of sample-dissolving pot, we are employed in the 2mol/L nitric acid medium and extract uranium; The extraction time is 1～2 minute; The selection of loading capacity and extractant volume; The TOPO of 4ml3.6% can make the percentage extraction of 10mg uranium reach more than 97%, increases the volume of extractant, and the loading capacity of uranium also increases thereupon; But consider the sensitivity of sample preparation; We select to extract with the 4ml extractant, to the sample of high-load more, through reducing the extraction fully that sample weighting amount reaches uranium; In order to shelter the interference of thorium, add the sodium fluoride of 5ml2%, through the separation and purification of uranium, the nucleic that has alpha-decay in the organic phase has only uranium.The separation and purification flow process of uranium is: in sample-dissolving pot, add 20ml water, the sodium fluoride of 5ml2%, 50mg ascorbic acid, shake up, add the 4ml3.6%TOPO-cyclohexane solution, with 180 times/minute frequency ramps concussions 2 minutes, leave standstill, supply sample preparation.
3) preparation of sample source:
Get the uranium-bearing organic solution 1～2ml behind the purifying, drop in the stainless steel sample disc that adds one deck lens wiping paper, on the low-temperature heat plate, sample is dried, be equipped with and survey;
Through more directly with after organic phase sample preparation and the uranium solution back extraction with two kinds of methods of WS sample preparation, the organic phase sample preparation is simple, quick, but counting efficiency is low when measuring; Elder generation's back extraction sample preparation again; Counting efficiency is higher, but step is overelaborate, is not suitable for open-air the use; And, also can satisfy the requirement of sample measurement with the direct sample preparation of organic phase.So selected the direct organic phase sample preparation of using,, measured the α particle and require the sample source surfacing because uranium is alpha-decay; Good uniformity, therefore, we have selected on the stainless steel sample disc, to add one deck lens wiping paper; Drip organic phase sample again, the source of system shows evenly level and smooth like this.Concrete preparation flow is: get the uranium-bearing organic solution 1～2ml behind the purifying, drop in the stainless steel sample disc that adds one deck lens wiping paper, on the low-temperature heat plate, sample is dried, be equipped with and survey.
4) measurement of sample:
The α counting rate of the sample source that measuring process 3) obtains,
With uranium standard solution preparation series of standards source, its sample making course is identical with sample sample preparation flow process, and the content range of standard source is selected 0 microgram, 10 micrograms in this example; 50 micrograms, 100 micrograms, 200 micrograms, 400 micrograms; 800 micrograms, 1200 micrograms, 2000 micrograms, and the α counting rate in measurement standard source; Do horizontal ordinate with standard source content, net counting rate is the coordinate curve of working, and related coefficient is greater than 0.999; Can select in this example to measure its counting rate with the portable α measuring instrument of PC-1 type; During sample measurement, the sample source that makes is put into measuring disk, according to the content height; Select certain Measuring Time; Make measuring error reach measurement requirement, the counting rate in measuring samples source and working curve, the portable α measuring instrument of PC-1 type can directly provide sample size.
It detects method provided by the present invention and is limited to 2.55 μ g/g uranium, measurement range＞8.0 μ g/g, and the uranium measurement relative standard deviation, relative standard deviation is less than 15% when uranium content is 100 μ g/g.
Embodiment
At first take by weighing 0.1～1g sample in the cylindrical sample-dissolving pot of perfluoroethylene-propylene (copolymer), it is wetting to add little water, adds 4ml red fuming nitric acid (RFNA), 0.5ml hydrofluorite, 0.5ml oxydol, seals; Be positioned in the automatic slaking apparatus, be warming up to 180 ℃, dissolved 30 minutes, take out sample pot; Be cooled to room temperature, uncap adds the 20ml deionized water, the sodium fluoride of 5ml2%; The 50mg ascorbic acid shook up, and adds the TOPO-cyclohexane solution of 4ml3.6%, with 180 times/minute frequency ramps concussions 2 minutes; After leaving standstill 30 minutes, get upper organic phase 2ml and above φ 50mm, be added with in the stainless steel sample disc of one deck lens wiping paper,, make cyclohexane volatilization in the organic phase with infrared lamp or the heating of low-temperature heat plate; Stay sample thin film, measure its α counting rate, measure, can provide the content of uranium in the sample with the portable α measuring instrument of PC-1 type.Table 1 is that various standard substances utilize the testing result of TOPO extraction α mensuration to uranium in the laboratory.
The testing result of uranium in the various standard substances of table 1
Annotate: H-14*, H-2*, T-2*, H-7* are the sandstone standard substance of up-to-date development.
The measurement of field condition uranium
In Horqin Left Wing Rear Banner, Inner Mongol association and Soviet Union's uranium ore is on-the-spot and Benxi, Liaoning 753 uranium mines have carried out field test by the whole process of this method; The on-the-spot in the open air sample of selecting different content; Still can operate as normal when outdoor temperature reaches 40 degrees centigrade, method of the present invention can normally be used in the open air, and it is simple to operate, equipment needed thereby is easy to carry about with one; Measuring accuracy is higher; Can proofread and correct the uranium data error that open-air well logging causes owing to uranium radium imbalance, can on-the-spot measure the data of uranium fast, directly instruct and look for the ore deposit.
Claims (6)
1. the measuring method of uranium in the uranium ore, it is characterized in that: it may further comprise the steps,
1) the uranium ore sample is dissolved fast;
2) the uranium ore sample solution direct separation purifying after will dissolving;
3) preparation uranium ore sample source;
4) the α counting rate in measuring samples source.
2. the measuring method of uranium in a kind of uranium ore as claimed in claim 1 is characterized in that: described step 1) comprises,
Uranium ore is put into molten appearance irritate, add nitric acid, hydrofluorite and oxydol, covered and enclosed, with automatic slaking apparatus heating, dissolution time was greater than 30 minutes, and temperature is controlled at 160 ℃～190 ℃.
3. like the measuring method of uranium in claim 1 or the 2 described a kind of uranium ores; It is characterized in that: the uranium ore consumption described in the step 1) is less than 1.5g; The ratio of uranium ore and nitric acid dosage is less than 1/3.5 (g/ml); The ratio of uranium ore and hydrofluorite consumption is 1/0.5～1/1 (g/ml), and the ratio of uranium ore and oxydol consumption is 1/0.5～1/1 (g/ml).
4. the measuring method of uranium in a kind of uranium ore as claimed in claim 1; It is characterized in that: described step 2) comprise, the acidity Control of the nitric acid of solution at 0.5-2mol/L, is added Fluorinse and ascorbic acid and TOPO-cyclohexane solution; Wherein the consumption of sodium fluoride is 100～200mg; The ascorbic acid consumption is 50～100mg, and organic phase and water ratio are greater than 1/10, and the concentration of TOPO-cyclohexane solution is greater than 3%.
5. the measuring method of uranium in a kind of uranium ore as claimed in claim 1 is characterized in that: described step 3) is the uranium-bearing organic solution 1～2ml that gets behind the purifying, drops in the stainless steel sample disc that adds one deck lens wiping paper, on the low-temperature heat plate, sample is dried.
6. the quantitative analysis method of uranium in a kind of uranium ore as claimed in claim 1; It is characterized in that: the α counting rate in described step 4) measuring samples source, with uranium standard solution preparation series of standards source, its sample making course such as step 1) to step 3 are said; And the α counting rate in measurement standard source; Uranium content with standard source is done horizontal ordinate, and net counting rate is the coordinate curve of working, and draws the uranium content of sample source through the α net counting rate of sample source according to working curve.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201010522787XA CN102455429A (en) | 2010-10-27 | 2010-10-27 | Method for measuring uranium in uranium ore |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201010522787XA CN102455429A (en) | 2010-10-27 | 2010-10-27 | Method for measuring uranium in uranium ore |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN102455429A true CN102455429A (en) | 2012-05-16 |
Family
ID=46038836
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201010522787XA Pending CN102455429A (en) | 2010-10-27 | 2010-10-27 | Method for measuring uranium in uranium ore |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN102455429A (en) |
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103528868A (en) * | 2013-10-22 | 2014-01-22 | 核工业二四〇研究所 | Uranium isotope ratio analysis and source production method |
| CN106568785A (en) * | 2016-10-19 | 2017-04-19 | 中国核动力研究设计院 | Online measurement apparatus and measurement method of uranium content of uranium-containing liquid |
| CN106872556A (en) * | 2017-01-05 | 2017-06-20 | 中国原子能科学研究院 | A kind of measuring method of uranium product production time |
| CN106990124A (en) * | 2017-03-31 | 2017-07-28 | 中国核动力研究设计院 | The on-line measurement device and measuring method of uranium content in a kind of uranium-bearing liquid |
| CN110243778A (en) * | 2019-07-10 | 2019-09-17 | 福州大学 | The spectrophotometry of uranyl ion in a kind of measurement solution |
| CN110261210A (en) * | 2019-07-31 | 2019-09-20 | 核工业二三O研究所 | The alpha energy spectrum method of testing of the method for separating and concentrating of uranium and uranium in sample of sandstone |
| CN110715922A (en) * | 2019-11-20 | 2020-01-21 | 福州大学 | Br-PADAP-uranyl ion spectrophotometry |
| CN114280025A (en) * | 2021-12-28 | 2022-04-05 | 核工业北京地质研究院 | Device and method for measuring uranium content in solution |
| CN114280025B (en) * | 2021-12-28 | 2024-05-03 | 核工业北京地质研究院 | Device and method for measuring uranium content in solution |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1948526A (en) * | 2006-10-30 | 2007-04-18 | 北京斯帕顿矿产资源投资咨询有限公司 | Method of extracting radioactive uranium in phosphate |
| CN101619397A (en) * | 2009-07-17 | 2010-01-06 | 云南佰盾环保新技术咨询有限公司 | Method for recycling uranium from uranium extraction coal residue with wet method |
| CN101738628A (en) * | 2008-11-21 | 2010-06-16 | 中国辐射防护研究院 | Method for ensuring counting and measuring stability in long-life alpha aerosol monitoring |
-
2010
- 2010-10-27 CN CN201010522787XA patent/CN102455429A/en active Pending
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1948526A (en) * | 2006-10-30 | 2007-04-18 | 北京斯帕顿矿产资源投资咨询有限公司 | Method of extracting radioactive uranium in phosphate |
| CN101738628A (en) * | 2008-11-21 | 2010-06-16 | 中国辐射防护研究院 | Method for ensuring counting and measuring stability in long-life alpha aerosol monitoring |
| CN101619397A (en) * | 2009-07-17 | 2010-01-06 | 云南佰盾环保新技术咨询有限公司 | Method for recycling uranium from uranium extraction coal residue with wet method |
Non-Patent Citations (4)
| Title |
|---|
| 《矿床地质》 20100915 黄秋红等 TOPO萃取alpha 计数法快速测定铀矿钻探样品中的铀含量 135-136页 1-3 第29卷, * |
| R. WEBER ET. AL.: "Alpha-spectrometric analysis of uranium and thorium using solid-phase extraction for sample preparation", 《APPLIED RADIATION AND ISOTOPES》, vol. 50, 31 December 1999 (1999-12-31), pages 929 - 934, XP004160266, DOI: doi:10.1016/S0969-8043(98)00118-3 * |
| SUMAN KUMAR SINGH ET.AL.: "A fast and sensitive method for the determination of uranium in the Thorex Process streams", 《JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY》, vol. 280, no. 1, 31 December 2009 (2009-12-31), pages 33 - 39, XP019682854 * |
| 黄秋红等: "TOPO萃取α 计数法快速测定铀矿钻探样品中的铀含量", 《矿床地质》, vol. 29, 15 September 2010 (2010-09-15), pages 135 - 136 * |
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103528868A (en) * | 2013-10-22 | 2014-01-22 | 核工业二四〇研究所 | Uranium isotope ratio analysis and source production method |
| CN103528868B (en) * | 2013-10-22 | 2016-01-27 | 核工业二四〇研究所 | A kind of uranium isotope ratio analysis source side method |
| CN106568785A (en) * | 2016-10-19 | 2017-04-19 | 中国核动力研究设计院 | Online measurement apparatus and measurement method of uranium content of uranium-containing liquid |
| CN106872556A (en) * | 2017-01-05 | 2017-06-20 | 中国原子能科学研究院 | A kind of measuring method of uranium product production time |
| CN106990124A (en) * | 2017-03-31 | 2017-07-28 | 中国核动力研究设计院 | The on-line measurement device and measuring method of uranium content in a kind of uranium-bearing liquid |
| CN110243778A (en) * | 2019-07-10 | 2019-09-17 | 福州大学 | The spectrophotometry of uranyl ion in a kind of measurement solution |
| CN110261210A (en) * | 2019-07-31 | 2019-09-20 | 核工业二三O研究所 | The alpha energy spectrum method of testing of the method for separating and concentrating of uranium and uranium in sample of sandstone |
| CN110715922A (en) * | 2019-11-20 | 2020-01-21 | 福州大学 | Br-PADAP-uranyl ion spectrophotometry |
| CN114280025A (en) * | 2021-12-28 | 2022-04-05 | 核工业北京地质研究院 | Device and method for measuring uranium content in solution |
| CN114280025B (en) * | 2021-12-28 | 2024-05-03 | 核工业北京地质研究院 | Device and method for measuring uranium content in solution |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN102455429A (en) | Method for measuring uranium in uranium ore | |
| Kiliari et al. | Simplified alpha-spectroscopic analysis of uranium in natural waters after its separation by cation-exchange | |
| CN102621588A (en) | Gamma energy spectrum-based method for identifying clay shale reservoir and uranium ore occurrence on spot | |
| CN103344982A (en) | Radiochemical analyzing method of Sr-90 in soil | |
| Zheng et al. | Global fallout Pu recorded in lacustrine sediments in Lake Hongfeng, SW China | |
| Canducci et al. | Upgrade of the CO2 direct absorption method for low-level 14C liquid scintillation counting | |
| Jacquier et al. | The influence of mineral variability of Callovo-Oxfordian clay rocks on radionuclide transfer properties | |
| Brooks et al. | Directional anisotropy in organic scintillation crystals | |
| Maiti et al. | Determination of particulate and dissolved 228Th in seawater using a delayed coincidence counter | |
| Yeh et al. | Purification of lanthanides for large neutrino detectors: Thorium removal from gadolinium chloride | |
| Dias et al. | A new approach for electron microprobe zircon fission track thermochronology | |
| Lozano et al. | A sequential method for the determination of 210Pb, 226Ra, and uranium and thorium radioisotopes by LSC and alpha-spectrometry | |
| CN106405617B (en) | The test method of strontium -89 and Strontium-90 activity concentration in a kind of nuclear power plant's liquid effluent | |
| CN104849337A (en) | Analysis detection method for amount of tritium generated from liquid lead lithium alloy under neutron radiation | |
| Lin et al. | Evaluating practicability of an LSC method for routine monitoring gross alpha and beta activities in water samples in Taiwan | |
| Nazarkulova et al. | Species of uranium of the Kamyshanovskoe deposit (Kyrgyzstan) | |
| Hirose et al. | Improvement of 137 Cs analysis in small volume seawater samples using the Ogoya underground facility | |
| CN109297957A (en) | A kind of radioactivity inert gas radon self-test kit and its application method | |
| Plionis et al. | Evaluation of flow scintillation analysis for the determination of Sr-90 in bioassay samples | |
| CN107907493A (en) | The high sensitivity spectrophotometry of rhenium or technetium in a kind of measure solution and water environment | |
| CN101545875B (en) | Method for analyzing scattered element content in chloride type oilfield water by utilizing X-ray fluorescence spectra | |
| Plastino et al. | Uranium, radium and tritium groundwater monitoring at INFN-Gran Sasso National Laboratory, Italy | |
| KR101421986B1 (en) | Measurement method of uranium isotope in aqueous solution | |
| Forte et al. | Natural radionuclides monitoring in Lombardia drinking water by liquid scintillation technique | |
| Bettoli et al. | Distribution of 226Ra in the Ross Sea—Antarctica |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C02 | Deemed withdrawal of patent application after publication (patent law 2001) | ||
| WD01 | Invention patent application deemed withdrawn after publication |
Application publication date: 20120516 |