CN104865283B - Mineral stantardless argon-argon dating method - Google Patents
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- 229910052500 inorganic mineral Inorganic materials 0.000 title claims abstract description 62
- 239000011707 mineral Substances 0.000 title claims abstract description 62
- XMPZLAQHPIBDSO-UHFFFAOYSA-N argon dimer Chemical compound [Ar].[Ar] XMPZLAQHPIBDSO-UHFFFAOYSA-N 0.000 title claims abstract description 45
- 238000000034 method Methods 0.000 title claims abstract description 30
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 claims abstract description 48
- 230000004907 flux Effects 0.000 claims abstract description 36
- 238000006243 chemical reaction Methods 0.000 claims abstract description 33
- 239000007789 gas Substances 0.000 claims abstract description 31
- 229910052759 nickel Inorganic materials 0.000 claims abstract description 18
- 238000002844 melting Methods 0.000 claims abstract description 8
- 230000008018 melting Effects 0.000 claims abstract description 8
- 238000005259 measurement Methods 0.000 claims description 13
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 claims description 6
- 229910052782 aluminium Inorganic materials 0.000 claims description 6
- 239000011888 foil Substances 0.000 claims description 6
- 238000000746 purification Methods 0.000 claims description 6
- 238000001228 spectrum Methods 0.000 claims description 5
- 229910052732 germanium Inorganic materials 0.000 claims description 4
- GNPVGFCGXDBREM-UHFFFAOYSA-N germanium atom Chemical compound [Ge] GNPVGFCGXDBREM-UHFFFAOYSA-N 0.000 claims description 4
- 238000006467 substitution reaction Methods 0.000 claims description 3
- 229910052756 noble gas Inorganic materials 0.000 claims 5
- 230000004992 fission Effects 0.000 abstract description 4
- 238000010438 heat treatment Methods 0.000 abstract description 3
- 239000005030 aluminium foil Substances 0.000 abstract 1
- 238000001514 detection method Methods 0.000 abstract 1
- 230000000155 isotopic effect Effects 0.000 abstract 1
- 230000002285 radioactive effect Effects 0.000 description 4
- 230000004048 modification Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000008569 process Effects 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 239000012677 causal agent Substances 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 229910052805 deuterium Inorganic materials 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 239000010453 quartz Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000005258 radioactive decay Effects 0.000 description 1
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N silicon dioxide Inorganic materials O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
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- Analysing Materials By The Use Of Radiation (AREA)
Abstract
The invention discloses a kind of pair of mineral to carry out the method that Unmarked word argon-argon determines year,It include: that mineral samplers are rolled into sample strip with aluminium foil,And one high-purity nickel sheet of each patch before and after sample strip,It is then placed in accelerator neutron generator and carries out neutron exposure; Nickel sheet after detection irradiation,Determine the value of cross-section σ,And the neutron flux N of computation accelerator neutron source; Mineral samplers after irradiation are loaded into rare gas measuring system,After heating melting sample,The Ar isotopic content of mineral samplers is measured with rare gas mass spectrograph,Required 40Ar*/39ArK is calculated by data; By the neutron flux N of accelerator neutron generator,Reaction cross-section σ and 40Ar*/39ArK substitute into formula
Calculate the Ar-Ar age of mineral samplers. The present invention solves the problems, such as that traditional argon-argon determines that year J value relevant to the neutron flux of 235U fission reactor etc. must be corrected using the standard sample at known age, it can be achieved with argon-argon without using any geological criteria sample and determine year, improve the precision that argon-argon determines year method.
Description
Technical Field
The invention relates to the technical field of argon-argon dating, in particular to a method for non-standard sample argon-argon dating of minerals.
Background
The basic principle of argon-argon dating is as follows: according to the radioactive decay law, the mineral age can be calculated according to the following formula 1 as long as the content of radioactive parent and radioactive causal agent is measured:
equation 1
Wherein t is mineral age, and λ is40K overall decay constant, λ 5.543(± 0.010) × 10-10a-1，λe、λ′eAre respectively as40K decays to40Decay constant, λ, of two branches of Are＝0.572(±0.004)×10-10a-1,λ′e＝0.0088(±0.0017)×10-10a-1，40K is the content of the radioactive parent substance,40ar is the content of radioactive causative body.
A modification to equation 1 can result:
equation 2
According to nuclear reactions39K(n,p)39Ar，
39ArK＝39K Δ ^ Φ (E) σ (E) dE formula 3
Wherein,39ArKis formed by39K produced by neutron irradiation39Ar and Δ denote irradiation times, Φ (E) denotes a neutron flux with energy E, and σ (E) denotes a neutron reaction cross section with energy E.
According to the above formula, and order
Equation 4
Then:
equation 5
Equation 5 is the basic equation for argon-argon dating. According to equation 5, the argon-argon age of a sample is determined by determining J value and40Ar*/39ArK。
based on formula 5, the existing argon-argon dating method is to place the mineral sample to be measured and the standard sample at intervals, seal the mineral sample and place the mineral sample in a quartz tube235Neutron irradiation of the U fission reactor39K is converted into39Ar。
As can be derived from the equation 5,
equation 6
By measuring standard samples of known age40Ar*/39ArKCorrecting the J value of the irradiation parameter, and measuring the sample to be measured40Ar*/39ArKThe argon-argon age of the sample to be measured was calculated according to formula 5 together with the J value corrected from the standard sample.
As can be seen from the above description, the current argon-argon dating method must correct the J value of the sample to be tested by measuring standard samples of known age. However, with the change of the fuel period and the sample position, the unknown parameters are more, the accurate J value is difficult to obtain, and a larger J value gradient is caused.
Disclosure of Invention
Technical problem to be solved
Accordingly, the primary objective of the present invention is to provide a method for non-standard argon-argon dating of minerals, so as to solve the problem that the conventional argon-argon dating must use standard samples of known ages for calibration and calibration235The neutron flux of the U fission reactor and other related J value problems achieve the purpose of argon-argon dating without using any geological standard sample and improve the precision of the argon-argon dating method.
(II) technical scheme
In order to achieve the above object, the present invention provides a method for non-standard argon-argon dating of minerals, which comprises:
step 1: wrapping a mineral sample into sample pieces by using aluminum foil, respectively attaching high-purity nickel pieces to the front and the back of each sample piece, and then putting the sample pieces into an accelerator neutron source for neutron irradiation;
step 2: detecting the irradiated nickel sheet, determining the value of a neutron reaction section sigma, and calculating the neutron flux N of an accelerator neutron source;
and step 3: loading the irradiated mineral sample into a rare gas measurement system, heating and melting the sample, and measuring the Ar isotope of the mineral sample by a rare gas mass spectrometer (40Ar，39Ar，36Ar) content, the desired one is obtained by data calculation40Ar*/39ArK；
And 4, step 4: neutron flux N, reaction cross section sigma and of accelerator neutron source40Ar*/39ArKSubstitution formulaCalculating the argon-argon age of the mineral sample;
wherein t is the argon-argon age of the mineral sample and λ is40K overall decay constant, λ 5.543(± 0.010) × 10- 10a-1，λe、λ′eAre respectively as40K decays to40Decay constant, λ, of two branches of Are＝0.572(±0.004)×10-10a-1 xλ′e＝0.0088(±0.0017)×10-10a-1，40Ar*/39ArKIs a cause of radioactivity40Ar and is derived from39K produced by neutron irradiation39ArKN is the neutron flux of the accelerator neutron source, and σ is the reaction cross section, which is the integral function of the neutron energy spectrum.
In the above scheme, the step 1 includes: taking a mineral sample, wrapping the mineral sample into sample pieces of 1cm multiplied by 1cm by using aluminum foil, respectively attaching high-purity nickel pieces with the thickness of 1 mm to the front and the back of each sample piece, and then placing the sample pieces into an accelerator neutron source to be as close to a target center as possible for neutron irradiation, wherein the position of the accelerator neutron source as close to the target center as possible is a position which is less than 3.5cm away from the target center.
In the scheme, the high-purity nickel sheet is a nickel sheet with the mass percentage of more than 99.99%.
In the scheme, the irradiated nickel sheet is detected in the step 2, and the nuclear data measurement of the neutron generator is completed by adopting an ultralow background high-purity germanium gamma spectrometer.
In the above scheme, in the step 2, the value of the reaction cross section σ of the mineral sample is determined, and since the neutron energy of the accelerator neutron source is single and 2.45MeV, the reaction cross section σ of the mineral sample is 0.18 target-en (b), where 1b is 10-24cm2。
In the above scheme, the step 2 of calculating the neutron flux N of the accelerator neutron source is based on the nuclear reaction58Ni(n,p)58Co completes the neutron flux calculation.
In the above scheme, the irradiated mineral sample is loaded into a rare gas measurement system in step 3, the rare gas measurement system includes a high temperature furnace, a gas purification system and a Helix MC Plus rare gas mass spectrometer, wherein the sample is melted by using the high temperature furnace, the gas released by melting is purified by the gas purification system, the active gas is removed, and then the Helix MC Plus rare gas mass spectrometer is used for measuring the Ar isotope.
In the above scheme, the step 3 of measuring the content of the Ar isotope in the mineral sample by using a rare gas mass spectrometer comprises measuring the content of the Ar isotope by using a Helix MC Plus rare gas mass spectrometer: (40Ar、39Ar、36Ar) content.
In the above scheme, the required data is obtained through data calculation in step 340Ar*/39ArK，39Ar is all composed of39K is produced by neutron irradiation, thus39ArKIs measured39Ar，40Ar*＝40Ar-40AraWherein40AraIs air40Ar，40Ara＝295.5×36Ar。
(III) advantageous effects
According to the technical scheme, the invention has the following beneficial effects:
1. the method for carrying out non-standard sample argon-argon dating on the mineral provided by the invention does not need to use a standard sample with known age to correct the J value determined by parameters such as neutron flux, reaction section and the like of the position of the sample to be detected, and only needs to measure the neutron flux and40Ar*/39ArKthereby avoiding the influence of J value gradient caused by sample position and the like, and solving the problem that the conventional argon-argon dating must use standard samples with known age to correct and235the J value problem related to the neutron flux of the U fission reactor and the like achieves the purpose of argon-argon dating without using any geological standard sample, and the method leads the argon-argon dating to be from 'relative dating' (the age of the sample is compared with that of a standard sample) to 'absolute dating' (no standard sample is needed).
2. The method for carrying out non-standard sample argon-argon dating on the mineral provided by the invention does not need to use a standard sample with known age to correct the J value determined by parameters such as neutron flux, reaction section and the like of the position of the sample to be detected, and only needs to measure the neutron flux and40Ar*/39ArKthereby avoiding the influence of J value gradient caused by sample position and the like, and improving the precision of the argon-argon dating method.
Drawings
FIG. 1 is a flow chart of a method for non-standard argon-argon dating of minerals according to an embodiment of the present invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is described in further detail below with reference to specific embodiments and the accompanying drawings.
In order to accurately calculate the neutron flux, the embodiment of the invention is that high-purity (the mass percentage is more than 99.99%) nickel sheets with the same size as the sample are respectively stuck to the front and the back of the mineral sample to be measured, the thickness is about 1 mm, so that the neutron flux is accurately calculated and the influence of neutron flux gradient is eliminated, and the annual precision is improved.
In the embodiment of the invention, the accelerator adopts a deuterium-deuterium (D-D) accelerator neutron source which only generates 2.45MeV single-energy neutrons to irradiate the mineral sample, and then the neutrons strike the mineral sample39K is converted into39Ar, satisfying the following formula,
equation 7
The reaction cross section σ is the number of reaction-generating nuclei per unit time and unit area (for example:39ArK) The ratio of the number of incident particles, N, to the number of target nuclei (for example:39K) in units of target-en (b,1 b-10)-24cm2)。
As can be seen from the equation 7,
equation 8
Of which 1.255 × 10-4Is in nature40K/39The value of K, N the neutron flux, and σ the reaction cross-section, is the integral function of the neutron energy spectrum.
As can be seen from equations 1, 7, and 8,
equation 9
Wherein t is the argon-argon age of the mineral sample and λ is40K has an overall decay constant, λ ═ 5.543(±0.010)×10- 10a-1，λe、λ′eAre respectively as40K decays to40Decay constant, λ, of two branches of Are＝0.572(±0.004)×10-10a-1,λ′e＝0.0088(±0.0017)×10-10a-1，40Ar*/39ArKIs a cause of radioactivity40Ar and is derived from39K produced by neutron irradiation39ArKN is the neutron flux of the accelerator neutron source, and σ is the reaction cross section, which is the integral function of the neutron energy spectrum.
Therefore, only the age of the sample needs to be determined to accurately determine the age40Ar*/39ArKN and σ.
In order to accurately measure the neutron flux N and the reaction section sigma, the embodiment of the invention adopts the reaction with the nuclear39K(n,p)39Neutron nuclear reaction of Ar nearest nickel (58Ni(n,p)58Co) was monitored. Because the neutron source of the accelerator is adopted to generate neutrons with single energy, the reaction section is constant, and the accurate neutron flux sum recorded by the nickel sheet is combined39The Ar content can be calculated39K content and sample age, and realizing argon-argon dating without a standard sample.
Based on the above analysis, fig. 1 shows a flow chart of a method for non-standard argon-argon dating of minerals according to an embodiment of the present invention, the method comprising:
step 1: wrapping a mineral sample into sample pieces by using aluminum foil, respectively sticking high-purity (99.99%) nickel pieces at the front and the back of each sample piece, and then putting the sample pieces into an accelerator neutron source for neutron irradiation;
step 2: detecting the irradiated nickel sheet, determining the value of a neutron reaction section sigma, and calculating the neutron flux N of an accelerator neutron source;
and step 3: loading the irradiated mineral sample into a rare gas measurement system, heating and melting the sample, and measuring the Ar isotope of the mineral sample by a rare gas mass spectrometer (40Ar，39Ar，36Ar) content, the desired one is obtained by data calculation40Ar*/39ArK；
And 4, step 4: neutron flux N, reaction cross section sigma and of accelerator neutron source40Ar*/39ArKSubstitution formulaCalculating the argon-argon age of the mineral sample;
wherein t is the argon-argon age of the mineral sample and λ is40K overall decay constant, λ 5.543(± 0.010) × 10- 10a-1，λe、λ′eAre respectively as40K decays to40Decay constant, λ, of two branches of Are＝0.572(±0.004)×10-10a-1,λ′e＝0.0088(±0.0017)×10-10a-1，40Ar*/39ArKIs a cause of radioactivity40Ar and is derived from39K produced by neutron irradiation39ArKN is the neutron flux of the accelerator neutron source, and σ is the reaction cross section, which is the integral function of the neutron energy spectrum.
Wherein, step 1 includes: taking a mineral sample, wrapping the mineral sample into sample pieces of 1cm multiplied by 1cm by using aluminum foil, respectively attaching high-purity nickel pieces with the thickness of 1 mm to the front and the back of each sample piece, and then placing the sample pieces into an accelerator neutron source to be as close to a target center as possible for neutron irradiation, wherein the position of the accelerator neutron source as close to the target center as possible is a position which is less than 3.5cm away from the target center.
And 2, detecting the irradiated nickel sheet, and completing nuclear data measurement of a neutron generator by adopting an ultralow background high-purity germanium gamma spectrometer, wherein the nuclear data measurement is mainly generated after the nickel sheet is irradiated by neutrons of a neutron source58Co。
Determining the value of the neutron reaction cross section sigma in step 2, wherein the neutron reaction cross section sigma of the accelerator neutron source is 0.18 target en (b) because the neutron energy of the neutron source is single and 2.45MeV, and 1b is 10-24cm2。
The neutron flux N of the accelerator neutron source is calculated in the step 2 according to nuclear reaction58Ni(n,p)58Co completes the calculation of neutron flux, and the specific calculation process is as follows:
according to nuclear reactions58Ni(n,p)58Co, then
Equation 10
Wherein, sigma is a reaction section, N is neutron flux of an accelerator neutron source,58co being measured by high-purity germanium gamma spectrometer58The number of atoms of Co is more than one,58with Ni as high-purity nickel flakes58The number of Ni atoms. The reaction cross section sigma is constant due to the neutron energy,58the number of Co atoms can be measured by a gamma spectrometer,58the Ni atom number can be calculated by the mass, purity and molar mass of the high-purity nickel sheet, and the neutron flux N of the accelerator neutron source can be calculated by substituting the mass, purity and molar mass into a formula 10.
And 3, loading the irradiated mineral sample into a rare gas measurement system, wherein the rare gas measurement system comprises a high-temperature furnace, a gas purification system and a Helix MC Plus rare gas mass spectrometer. And 3, measuring the Ar isotope content of the mineral sample by using a rare gas mass spectrometer, wherein the specific measuring process is as follows: melting the sample with a high temperature furnace, purifying the gas released by melting with a purification system, removing active gas, etc., measuring Ar isotope with Helix MC Plus rare gas mass spectrometer, and respectively receiving with a Faraday cup and an electron multiplier equipped on the rare gas mass spectrometer40Ar、39Ar、36Ar signal, measured40Ar、39Ar、36And (4) Ar content.
The required data are obtained through data calculation in step 340Ar*/39ArK，39Ar is all composed of39Neutron irradiation of K channelGenerated by radiation, thus39ArKIs measured39Ar，40Ar*＝40Ar-40AraWherein40AraIs air40Ar，40Ara＝295.5×36Ar, and therefore,40Ar*/39ArK＝(40Ar-295.5*36Ar)/39ar; the specific calculation is to be measured40Ar、39Ar、36Ar is respectively substituted into the above formula to obtain40Ar*/39ArKThe value is obtained.
The method for non-standard sample argon-argon dating of the mineral provided by the embodiment of the invention does not need to use a standard sample with known age to correct the J value determined by parameters such as neutron flux, reaction cross section and the like of the position of the sample to be detected, and only needs to measure the neutron flux and40Ar*/39ArKthereby avoiding the influence of J value gradient caused by sample position and the like, and improving the precision of the argon-argon dating method.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are only exemplary embodiments of the present invention, and are not intended to limit the present invention, and any modifications, equivalents, improvements and the like made within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (9)
1. A method for non-standard argon-argon dating of a mineral, comprising:
step 1: wrapping a mineral sample into sample pieces by using aluminum foil, respectively attaching high-purity nickel pieces to the front and the back of each sample piece, and then putting the sample pieces into an accelerator neutron source for neutron irradiation;
step 2: detecting the irradiated nickel sheet, determining the value of a neutron reaction section sigma, and calculating the neutron flux N of an accelerator neutron source;
and step 3: loading the irradiated mineral sample into a rare gas measurement system, and heatingAfter melting the sample, the Ar isotope of the mineral sample was determined by a rare gas mass spectrometer40Ar，39Ar and36ar content, calculated from the data to give the desired40Ar*/39ArK；
And 4, step 4: neutron flux N, reaction cross section sigma and of accelerator neutron source40Ar*/39ArKSubstitution formulaCalculating the argon-argon age of the mineral sample;
wherein t is the argon-argon age of the mineral sample and λ is40K overall decay constant, λ 5.543(± 0.010) × 10-10a-1，λe、λ′eAre respectively as40K decays to40Decay constant, λ, of two branches of Are＝0.572(±0.004)×10-10a-1,λ′e＝0.0088(±0.0017)×10-10a-1，40Ar*/39ArKIs a cause of radioactivity40Ar and is derived from39K produced by neutron irradiation39ArKN is the neutron flux of the accelerator neutron source, and σ is the reaction cross section, which is the integral function of the neutron energy spectrum.
2. The method of claim 1 for non-standard argon-argon dating of minerals, wherein step 1 comprises:
taking a mineral sample, wrapping the mineral sample into sample pieces of 1cm multiplied by 1cm by using aluminum foil, respectively attaching high-purity nickel pieces with the thickness of 1 mm to the front and the back of each sample piece, and then placing the sample pieces into an accelerator neutron source to be as close to a target center as possible for neutron irradiation, wherein the position of the accelerator neutron source as close to the target center as possible is a position which is less than 3.5cm away from the target center.
3. The method for non-standard argon-argon dating of minerals according to claim 1 or 2, wherein said high purity nickel flakes are nickel flakes with a mass percentage > 99.99%.
4. The method of claim 1, wherein the irradiated nickel pieces are detected in step 2 and neutron generator nuclear data measurements are performed using an ultra low background high purity germanium gamma spectrometer.
5. The method for non-standard argon-argon dating of minerals according to claim 1, wherein said determining in step 2 the value of the reaction cross section σ of the mineral sample, which is 0.18 target en (b) due to the single neutron energy of the accelerator neutron source and 2.45MeV, wherein 1 target en is 10-24cm2。
6. The method for non-standard argon-argon dating of minerals as claimed in claim 1, wherein said calculating neutron flux N of accelerator neutron source in step 2 is based on nuclear reaction58Ni(n,p)58Co completes the neutron flux calculation.
7. The method for non-standard sample argon-argon dating of mineral according to claim 1, wherein said step 3 of loading the irradiated mineral sample into a noble gas measurement system comprising a high temperature furnace, a gas purification system and a Helix MC Plus noble gas mass spectrometer, wherein the sample is melted using the high temperature furnace, the gas released from the melting is purified by the gas purification system, the active gas is removed, and the measurement of Ar isotope is performed by the Helix MC Plus noble gas mass spectrometer.
8. The method for non-standard sample argon-argon dating of mineral according to claim 1, wherein said determining Ar isotope content of mineral sample with noble gas mass spectrometer in step 3 is performed by using Helix MC Plus noble gas mass spectrometer40Ar、39Ar and36the content of Ar.
9. The method for non-standard argon-argon dating of minerals according to claim 1, wherein said step 3 is characterized by calculating the data to obtain the required time40Ar*/39ArK，39Ar is all composed of39K is produced by neutron irradiation, thus39ArKIs measured39Ar，40Ar*＝40Ar-40AraWherein40AraIs air40Ar，40Ara＝295.5×36Ar。
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| CN106124602B (en) * | 2016-06-17 | 2017-09-15 | 中国科学院地质与地球物理研究所 | A kind of geology rock sample nitrogen isotope measure method |
| CN108036979B (en) * | 2017-11-15 | 2018-12-21 | 中国科学院地质与地球物理研究所 | Mineral samplers target based on electrostatic force and preparation method thereof |
| CN107979911B (en) | 2017-12-26 | 2024-06-14 | 同方威视技术股份有限公司 | Pull-out support for an accelerator and accelerator cabin structure |
| CN107884425A (en) * | 2017-12-26 | 2018-04-06 | 同方威视技术股份有限公司 | System and method for mineral products constituent analysis |
| CN108982558B (en) * | 2018-07-09 | 2021-07-06 | 中国科学院地质与地球物理研究所 | Method for obtaining crust argon isotope composition |
| CN113125483B (en) * | 2021-03-10 | 2022-07-12 | 中国科学院国家空间科学中心 | Light and small extraterrestrial planet in-situ dating instrument and dating method thereof |
| CN113325458B (en) * | 2021-08-02 | 2021-10-29 | 中国科学院地质与地球物理研究所 | Combined measurement method for argon-argon age and cosmic exposure age of extra-terrestrial sample |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102141539A (en) * | 2010-02-01 | 2011-08-03 | 中国科学院地质与地球物理研究所 | Method for uranium lead dating of baddeleyite by using secondary ion mass spectroscopy |
| CN102175704A (en) * | 2011-02-18 | 2011-09-07 | 中国原子能科学研究院 | Uranium isotope abundance analysis method |
| CN104217775A (en) * | 2014-08-14 | 2014-12-17 | 西京学院 | Method for measuring neutron flux density of nuclear reactor through thermal analysis technology |
-
2015
- 2015-04-30 CN CN201510214712.8A patent/CN104865283B/en active Active
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102141539A (en) * | 2010-02-01 | 2011-08-03 | 中国科学院地质与地球物理研究所 | Method for uranium lead dating of baddeleyite by using secondary ion mass spectroscopy |
| CN102175704A (en) * | 2011-02-18 | 2011-09-07 | 中国原子能科学研究院 | Uranium isotope abundance analysis method |
| CN104217775A (en) * | 2014-08-14 | 2014-12-17 | 西京学院 | Method for measuring neutron flux density of nuclear reactor through thermal analysis technology |
Non-Patent Citations (2)
| Title |
|---|
| （极）年轻火山岩激光熔蚀40Ar/39Ar定年;周晶 等;《岩石学报》;20130831(第8期);第2811-2825页 * |
| 40Ar/39Ar测年法表观年龄计算中的误差分析;高洪林;《第四纪研究》;20120531;第32卷(第3期);第547页-558页 * |
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