CN106932423A - A kind of analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample - Google Patents

A kind of analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample Download PDF

Info

Publication number
CN106932423A
CN106932423A CN201511016813.0A CN201511016813A CN106932423A CN 106932423 A CN106932423 A CN 106932423A CN 201511016813 A CN201511016813 A CN 201511016813A CN 106932423 A CN106932423 A CN 106932423A
Authority
CN
China
Prior art keywords
plutonium
uranium
neptunium
standard
sample
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
CN201511016813.0A
Other languages
Chinese (zh)
Inventor
吉永超
汪南杰
赵爱
马精德
牟凌
刘雷明
姜国杜
陈强
蒋军清
曹希
龚焱平
王卫斌
夏钢建
杨松涛
何南玲
张红英
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
404 Co Ltd China National Nuclear Corp
Original Assignee
404 Co Ltd China National Nuclear Corp
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by 404 Co Ltd China National Nuclear Corp filed Critical 404 Co Ltd China National Nuclear Corp
Priority to CN201511016813.0A priority Critical patent/CN106932423A/en
Publication of CN106932423A publication Critical patent/CN106932423A/en
Pending legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G01MEASURING; TESTING
    • G01NINVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N23/00Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00
    • G01N23/22Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by measuring secondary emission from the material
    • G01N23/223Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by measuring secondary emission from the material by irradiating the sample with X-rays or gamma-rays and by measuring X-ray fluorescence

Landscapes

  • Physics & Mathematics (AREA)
  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Chemical & Material Sciences (AREA)
  • Analytical Chemistry (AREA)
  • Biochemistry (AREA)
  • General Health & Medical Sciences (AREA)
  • General Physics & Mathematics (AREA)
  • Immunology (AREA)
  • Pathology (AREA)
  • Sampling And Sample Adjustment (AREA)

Abstract

The invention belongs to spentnuclear fuel post-processing technology field, and in particular to a kind of analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample.Comprise the following steps:It is prepared by nitrate acid and hydrofluoric acid;Plutonium standard substance is sampled and the sampling of uranium standard substance;Standard substance powder dissolves;It is prepared by uranium and plutonium standard reserving solution;It is prepared by uranium, neptunium, plutonium series standard;Measurement series standard.A kind of analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample that the present invention is provided, the need for waste minimization and spent fuel reprocessing process control analysis can be met.

Description

A kind of analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample
Technical field
The invention belongs to spentnuclear fuel post-processing technology field, and in particular to a kind of analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample.
Background technology
External power reactor spentnuclear fuel post processing starting is relatively early, and reprocessing analysis technology has obtained tremendous development and raising, and classical radiochemical analysis is increasingly replaced by modern instrumental method;Be applied to the pre- diffraction X-fluorescence technology of graphite crystal in reprocessing plant industrial analysis by the Areva factories of France.But because the analytical technology of external uranium, neptunium, plutonium is blocked, the analysis method for directly measure uranium, neptunium, plutonium has not been reported.
The country common are extract and separate α counting methods, AAS, extract and separate alpha energy spectrum method etc. for slightly enriched uranium, neptunium, the analysis method of plutonium, but the above method belongs to destructive method of analysis, have the shortcomings that cumbersome, sample analysis time is long, personnel's exposure dosage is big.China Atomic Energy Science Research Institute develops graphite crystal diffracting X-rays fluorescence analyser, the research in terms of having carried out single uranium, plutonium with the instrument.The above method can not simultaneously determine uranium, neptunium, plutonium in process sample.
The content of the invention
It is an object of the invention to provide a kind of analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample, the need for meeting waste minimization and spent fuel reprocessing process control analysis.
To reach above-mentioned purpose, the technical solution used in the present invention is:
A kind of analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample, comprises the following steps:
(1) prepared by nitrate acid and hydrofluoric acid:In pipetting the pure nitric acid of analysis to the volumetric flask demarcated with pipette, then with pipette pipette analytically pure hydrofluoric acid to the volumetric flask, be prepared into concentration of nitric acid for 8mol/L~12mol/L, hydrofluoric acid concentration is the nitration mixture of 0.05mol/L~0.10mol/L;
(2) plutonium standard substance sampling:Plutonium dioxide standard substance is accurately weighed using a ten thousandth balance to put into high pressure counteracting tank, nitrate acid and hydrofluoric acid nitration mixture 4mL obtained by step (1)~5mL is added into high-pressure digestion tank, close the lid, high-pressure digestion tank is put into supporting stainless steel cylinder, stainless steel cylinder puts to the electric furnace with graphite cake heating;Uranium standard substance is sampled:Triuranium octoxide standard substance is accurately weighed using a ten thousandth balance to put into high pressure counteracting tank, nitrate acid and hydrofluoric acid nitration mixture 4mL obtained by step (1)~5mL is added into high-pressure digestion tank, close the lid, high-pressure digestion tank is put into supporting stainless steel cylinder, stainless steel cylinder puts to the electric furnace with graphite cake heating;
(3) standard substance powder dissolving:The stainless steel cylinder that step (2) holds sample is heated into 4h~8h at 160~180 DEG C, high-pressure digestion cover is opened, confirms that the uranium in high-pressure digestion tank and the solid powder of plutonium are completely dissolved;
(4) prepared by uranium and plutonium standard reserving solution:During two samples of step (3) are moved into two volumetric flasks with glue head dropper, with the nitric acid constant volume of 1mol/L~4mol/L, that is, the uranium and plutonium standard reserving solution of water phase are obtained;
(5) prepared by uranium, neptunium, plutonium series standard:Uranium, plutonium standard reserving solution and the neptunium standard liquid of accurate removing step (4) are distinguished in 6 10ml volumetric flasks, with the salpeter solution constant volume of 1mol/L~4mol/L, you can obtain serial uranium, neptunium, plutonium mixed standard solution;
(6) series standard is measured:The series standard solution 1.0mL~1.2mL of removing step (5) determines 600s~1000s in bottle is measured with the pre- diffracting X-rays fluorescence analyser of graphite crystal respectively, and the measuring condition of instrument is:Voltage -50kV, electric current 4mA, preserve measurement spectrogram.
Plutonium dioxide standard substance is GBW 04201 in the step (2).
Triuranium octoxide standard substance is GBW 04201 in the step (2).
Step (2) the mesohigh counteracting tank material is polytetrafluoroethylene (PTFE).
Neptunium standard liquid is United Kingdom National physics laboratory in the step (5), and activity is 148.2kBq.g-1, expanded uncertainty is ± 1.6kBq.g-1Solution.
After described step (6), following steps are also carried out:(7) drawing curve:Using the spectrogram of step (6) using deduction background, peak height method drawing curve;(8) add-back yield checking again:Optional step (7) working curve determines unknown aqueous process sample 6 times, and water phase uranium, neptunium, plutonium standard liquid are separately added into the unknown process sample, uranium, neptunium, the content addition of plutonium standard is prepared respectively and is 10.00 × 10-6g、10.00×10-6g、10.00×10-6Three 1mL aqueous samples of g, the uranium of the addition of measure, neptunium, the average of the measurement result of the standard of plutonium are respectively 9.99 × 10-6g、10.28×10-6g、10.02×10-6G, then add-back yield is respectively 99.9%, 102.8%, 100.2% again.
Having the beneficial effect that acquired by the present invention:
Determined while slightly enriched uranium, neptunium, plutonium content in the achievable radioactive liquid sample of the present invention, and 5 × 10-3When in the range of g/L~1.00g/L, the relative standard deviation of measurement result is better than 5%, and add-back yield is 95%~110% again, can meet the requirement of control analysis.
Specific embodiment
With reference to specific embodiment, the present invention is described in detail.
The analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample of the present invention comprises the following steps:
(1) prepared by nitrate acid and hydrofluoric acid:In the pure nitric acid of a certain amount of analysis to the volumetric flask demarcated being pipetted with pipette, in pipetting a certain amount of analytically pure hydrofluoric acid to the volumetric flask with pipette again, it is the nitration mixture of 0.05mol/L~0.10mol/L for 8mol/L~12mol/L- hydrofluoric acid concentrations to be prepared into concentration of nitric acid.
(2) plutonium standard substance sampling:A certain amount of plutonium dioxide standard substance (GBW 04201) is accurately weighed using a ten thousandth balance to put into the high-pressure digestion tank of polytetrafluoroethylene (PTFE) material, nitrate acid and hydrofluoric acid nitration mixture 4mL obtained by step (1)~5mL is added into high-pressure digestion tank, close the lid, high-pressure digestion tank is put into supporting stainless steel cylinder, stainless steel cylinder puts to the electric furnace with graphite cake heating.
Uranium standard substance is sampled:A certain amount of triuranium octoxide standard substance (GBW 04201) is accurately weighed using a ten thousandth balance to put into the high-pressure digestion tank of polytetrafluoroethylene (PTFE) material, nitrate acid and hydrofluoric acid nitration mixture 4mL obtained by step (1)~5mL is added into high-pressure digestion tank, close the lid, high-pressure digestion tank is put into supporting stainless steel cylinder, stainless steel cylinder puts to the electric furnace with graphite cake heating.
(3) standard substance powder dissolving:The stainless steel cylinder for holding sample of step (2) is heated into 4h~8h at 160~180 DEG C, counteracting tank lid is opened, confirms that the uranium in high-pressure digestion tank and the solid powder of plutonium are completely dissolved.
(4) prepared by uranium and plutonium standard reserving solution:During two samples of step (3) are moved into two volumetric flasks with glue head dropper, with the nitric acid constant volume of 1mol/L~4mol/L, that is, the uranium and plutonium standard reserving solution of water phase are obtained.
(5) prepared by uranium, neptunium, plutonium series standard:(United Kingdom National physics laboratory, activity is 148.2kBq.g accurately to pipette uranium, plutonium standard reserving solution and the neptunium standard liquid of a certain amount of step (4) respectively-1, expanded uncertainty is ± 1.6kBq.g-1) in 6 10ml volumetric flasks, with the salpeter solution constant volume of 1mol/L~4mol/L, you can obtain serial uranium, neptunium, plutonium mixed standard solution.
(6) series standard is measured:In bottle is measured, the measuring condition for determining 600s~1000s instruments with the pre- diffracting X-rays fluorescence analyser of graphite crystal is the series standard 1.0mL~1.2mL of removing step (5) respectively:Voltage is -50kV, and electric current is 4mA, preserves measurement spectrogram.
(7) drawing curve:Using the spectrogram of step (6) using deduction background, peak height method drawing curve.
(8) add-back yield checking again:Optional step (7) working curve determines unknown aqueous process sample 6 times, and water phase uranium, neptunium, plutonium standard liquid are separately added into the unknown process sample, uranium, neptunium, the content addition of plutonium standard is prepared respectively and is 10.00 × 10-6g、10.00×10-6g、10.00×10-6Three 1mL aqueous samples of g, the uranium of the addition of measure, neptunium, the average of the measurement result of the standard of plutonium are respectively 9.99 × 10-6g、10.28×10-6g、10.02×10-6G, then add-back yield is respectively 99.9%, 102.8%, 100.2% again.

Claims (6)

1. a kind of analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample, it is characterised in that:Bag Include following steps:
(1) prepared by nitrate acid and hydrofluoric acid:In the pure nitric acid of analysis to the volumetric flask demarcated being pipetted with pipette, then In pipetting analytically pure hydrofluoric acid to the volumetric flask with pipette, be prepared into concentration of nitric acid for 8mol/L~ 12mol/L, hydrofluoric acid concentration is the nitration mixture of 0.05mol/L~0.10mol/L;
(2) plutonium standard substance sampling:Using a ten thousandth balance accurately weigh plutonium dioxide standard substance put to In high-pressure digestion tank, the nitrate acid and hydrofluoric acid nitration mixture 4mL obtained by step (1)~5mL is added into high-pressure digestion Tank, is closed the lid, and high-pressure digestion tank is put into supporting stainless steel cylinder, and stainless steel cylinder is put to graphite cake Heated on electric furnace;Uranium standard substance is sampled:Triuranium octoxide reference material is accurately weighed using a ten thousandth balance Matter is put into high pressure counteracting tank, the nitrate acid and hydrofluoric acid nitration mixture 4mL obtained by step (1)~5mL is added high Pressure counteracting tank, is closed the lid, and high-pressure digestion tank is put into supporting stainless steel cylinder, and stainless steel cylinder is put to band stone Heated on the electric furnace of black plate;
(3) standard substance powder dissolving:Step (2) is held into the stainless steel cylinder of sample at 160~180 DEG C Lower heating 4h~8h, opens high-pressure digestion cover, confirms the solid powder of the uranium and plutonium in high-pressure digestion tank It is completely dissolved;
(4) prepared by uranium and plutonium standard reserving solution:Two samples of step (3) are moved to two with glue head dropper In individual volumetric flask, with the nitric acid constant volume of 1mol/L~4mol/L, that is, the uranium and plutonium standard reserving solution of water phase are obtained;
(5) prepared by uranium, neptunium, plutonium series standard:The uranium of accurate removing step (4), the storage of plutonium standard respectively Standby liquid and neptunium standard liquid in 6 10ml volumetric flasks, with the salpeter solution constant volume of 1mol/L~4mol/L, Can obtain serial uranium, neptunium, plutonium mixed standard solution;
(6) series standard is measured:Respectively removing step (5) series standard solution 1.0mL~1.2mL in In measurement bottle, 600s~1000s, the measurement of instrument are determined with the pre- diffracting X-rays fluorescence analyser of graphite crystal Condition is:Voltage -50kV, electric current 4mA, preserve measurement spectrogram.
2. the analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample according to claim 1, It is characterized in that:Plutonium dioxide standard substance is GBW 04201 in the step (2).
3. the analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample according to claim 1, It is characterized in that:Triuranium octoxide standard substance is GBW 04201 in the step (2).
4. the analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample according to claim 1, It is characterized in that:Step (2) the mesohigh counteracting tank material is polytetrafluoroethylene (PTFE).
5. the analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample according to claim 1, It is characterized in that:Neptunium standard liquid is United Kingdom National physics laboratory in the step (5), and activity is 148.2kBq.g-1, expanded uncertainty is ± 1.6kBq.g-1Solution.
6. the analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample according to claim 1, It is characterized in that:After described step (6), following steps are also carried out:(7) drawing curve: Using the spectrogram of step (6) using deduction background, peak height method drawing curve;(8) add-back yield is tested again Card:Optional step (7) working curve determines unknown aqueous process sample 6 times, by water phase uranium, neptunium, plutonium mark Quasi- solution is separately added into the unknown process sample, prepare respectively uranium, neptunium, plutonium standard content addition it is equal It is 10.00 × 10-6g、10.00×10-6g、10.00×10-6Three 1mL aqueous samples of g, the addition of measure Uranium, neptunium, the average of the measurement result of the standard of plutonium are respectively 9.99 × 10-6g、10.28×10-6g、10.02×10-6G, Then add-back yield is respectively 99.9%, 102.8%, 100.2% again.
CN201511016813.0A 2015-12-29 2015-12-29 A kind of analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample Pending CN106932423A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201511016813.0A CN106932423A (en) 2015-12-29 2015-12-29 A kind of analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201511016813.0A CN106932423A (en) 2015-12-29 2015-12-29 A kind of analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample

Publications (1)

Publication Number Publication Date
CN106932423A true CN106932423A (en) 2017-07-07

Family

ID=59441412

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201511016813.0A Pending CN106932423A (en) 2015-12-29 2015-12-29 A kind of analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample

Country Status (1)

Country Link
CN (1) CN106932423A (en)

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107449789A (en) * 2017-07-31 2017-12-08 四川新先达测控技术有限公司 Sample concentration detection means and system
CN107843640A (en) * 2017-11-01 2018-03-27 广西壮族自治区食品药品检验所 The assessment method of 20 kinds of constituent content uncertainties in honeysuckle
CN108152850A (en) * 2017-12-18 2018-06-12 中核四0四有限公司 Multinuclear element rapid analysis method in a kind of radioactive pollution soil
CN108303306A (en) * 2017-12-21 2018-07-20 中核四0四有限公司 Spentnuclear fuel post-processes high-content uranium, neptunium, the direct method for measuring of plutonium in feed liquid
CN110455843A (en) * 2019-09-16 2019-11-15 核工业二三O研究所 A kind of method that strontium internal standard-XRF solwution method measures uranium element in natural uranium product
CN110530906A (en) * 2019-08-14 2019-12-03 中国原子能科学研究院 The measuring method of plutonium concentration in a kind of spent fuel solution
CN112697777A (en) * 2021-01-20 2021-04-23 中国核动力研究设计院 Method for determining content of lithium, sodium, magnesium and calcium in uranium compound
CN112763449A (en) * 2020-12-14 2021-05-07 中国原子能科学研究院 Method for simultaneously determining neptunium and plutonium concentrations in nitric acid-containing solution
CN112924518A (en) * 2019-12-05 2021-06-08 中核四0四有限公司 Method for analyzing neptunium content in neptunium dioxide sample

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101504380A (en) * 2009-03-12 2009-08-12 中国原子能科学研究院 X-ray fluorescence analyzer
CN106342216B (en) * 2005-11-07 2010-11-10 中国原子能科学研究院 Energy-dispersive X-ray fluorescence (EDXRF) analytical system
CN103900990A (en) * 2014-02-28 2014-07-02 中国原子能科学研究院 Method for simultaneously and rapidly measuring content of plutonium and nitric acid in organic phase
CN104007461A (en) * 2014-05-29 2014-08-27 中国原子能科学研究院 Method for analyzing solution sample in hot cell

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106342216B (en) * 2005-11-07 2010-11-10 中国原子能科学研究院 Energy-dispersive X-ray fluorescence (EDXRF) analytical system
CN101504380A (en) * 2009-03-12 2009-08-12 中国原子能科学研究院 X-ray fluorescence analyzer
CN103900990A (en) * 2014-02-28 2014-07-02 中国原子能科学研究院 Method for simultaneously and rapidly measuring content of plutonium and nitric acid in organic phase
CN104007461A (en) * 2014-05-29 2014-08-27 中国原子能科学研究院 Method for analyzing solution sample in hot cell

Non-Patent Citations (3)

* Cited by examiner, † Cited by third party
Title
吉永超等: "石墨晶体预衍射x射线荧光法同时测定工艺样品中的低浓铀和低浓钚", 《核化学与放射化学》 *
宋游等: "石墨晶体预衍射x射线荧光法测量微量U、Np、Pu", 《中国原子能科学研究院年报》 *
陶苗苗等: "1AF中镎的XRF分析前预处理方法研究", 《中国原子能科学研究院年报》 *

Cited By (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107449789A (en) * 2017-07-31 2017-12-08 四川新先达测控技术有限公司 Sample concentration detection means and system
CN107843640A (en) * 2017-11-01 2018-03-27 广西壮族自治区食品药品检验所 The assessment method of 20 kinds of constituent content uncertainties in honeysuckle
CN108152850A (en) * 2017-12-18 2018-06-12 中核四0四有限公司 Multinuclear element rapid analysis method in a kind of radioactive pollution soil
CN108303306A (en) * 2017-12-21 2018-07-20 中核四0四有限公司 Spentnuclear fuel post-processes high-content uranium, neptunium, the direct method for measuring of plutonium in feed liquid
CN110530906A (en) * 2019-08-14 2019-12-03 中国原子能科学研究院 The measuring method of plutonium concentration in a kind of spent fuel solution
CN110455843A (en) * 2019-09-16 2019-11-15 核工业二三O研究所 A kind of method that strontium internal standard-XRF solwution method measures uranium element in natural uranium product
CN110455843B (en) * 2019-09-16 2022-04-05 核工业二三O研究所 Method for determining uranium element in natural uranium product by strontium internal standard-XRF solution method
CN112924518A (en) * 2019-12-05 2021-06-08 中核四0四有限公司 Method for analyzing neptunium content in neptunium dioxide sample
CN112924518B (en) * 2019-12-05 2023-02-21 中核四0四有限公司 Method for analyzing neptunium content in neptunium dioxide sample
CN112763449A (en) * 2020-12-14 2021-05-07 中国原子能科学研究院 Method for simultaneously determining neptunium and plutonium concentrations in nitric acid-containing solution
CN112697777A (en) * 2021-01-20 2021-04-23 中国核动力研究设计院 Method for determining content of lithium, sodium, magnesium and calcium in uranium compound

Similar Documents

Publication Publication Date Title
CN106932423A (en) A kind of analysis method directly determined for slightly enriched uranium, neptunium, plutonium in sample
CN106093002B (en) Device and method that is a kind of while measuring sulfate radical and phosphate radical in high activity liquid waste
Lizin et al. PuF3, AmF3, CeF3, and NdF3 solubility in LiF–NaF–KF melt
CN108303306A (en) Spentnuclear fuel post-processes high-content uranium, neptunium, the direct method for measuring of plutonium in feed liquid
Nair et al. Development of an internal monostandard instrumental neutron activation analysis method based on in situ detection efficiency for analysis of large and nonstandard geometry samples
Liu et al. Dissolution behavior of irradiated fuels in nitric acid and characteristics of insoluble residue
CN106932421B (en) A kind of preparation method of organic phase plutonium and organic phase neptunium standard solution
CN106405617B (en) The test method of strontium -89 and Strontium-90 activity concentration in a kind of nuclear power plant's liquid effluent
CN108226327A (en) LC-MS measure uranium in PUREX post processings flow 1AW, neptunium, plutonium content method
Pandey et al. Determination of trace amounts of uranium in plutonium oxide by wavelength dispersive X-ray fluorescence spectrometry
CN115755146A (en) In high-level radioactive waste liquid 243 Am content analysis method
Yu-Fu et al. Improvement for α-energy resolution in determination of low level plutonium by liquid scintillation counting
Chichester et al. In-field alpha spectrometry to assess uranium enrichment in uranium hexafluoride
CN202256162U (en) Portable atomic fluorescence spectrograph
CN108318612A (en) A method of silver-colored impurity content in MOX pellets is measured using TBP extration resins
CN114689617A (en) Method for measuring gamma energy emissivity of fission product in neptunium dioxide sample
Chand et al. Rapid estimation of the isotopic composition and total mass fraction of boron in enriched B4C samples for Indian fast reactor technology using external (in air) particle induced gamma-ray emission technique
Ferlay et al. From the Phenix irradiation end to the analytical results: PROFIL R target destructive characterization
RU2785061C1 (en) METHOD FOR DETERMINATION OF ACTIVITY OF 238,239+240,241Pu RADIONUCLIDES IN AEROSOL SAMPLES AND PRECIPITATIONS
Lizin et al. Pu [F. sub. 3], Am [F. sub. 3], Ce [F. Sub. 3], and Nd [F. sub. 3] solubility in LiF-NaF-KF melt
CN117111133A (en) Method for rapidly determining plutonium content and total alpha activity concentration based on liquid source method
Yoon et al. The Capability of isotopic uranium analysis in nuclear material at KINAC
Noviarty et al. Determination of the optimal parameters for the separation of neodymium from cesium in U3Si2/Al fuel plate solution using precipitation method with HClO4
KR101646912B1 (en) Device and method for measuring of fissile materials in the pyro-process
TWI543939B (en) Automatic extraction analysis method of trans-uranium element

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
RJ01 Rejection of invention patent application after publication

Application publication date: 20170707

RJ01 Rejection of invention patent application after publication