CN103424767A - Method for measuring content of 235U and 239Pu in U-Pu mixture - Google Patents

Method for measuring content of 235U and 239Pu in U-Pu mixture Download PDF

Info

Publication number
CN103424767A
CN103424767A CN2012101583982A CN201210158398A CN103424767A CN 103424767 A CN103424767 A CN 103424767A CN 2012101583982 A CN2012101583982 A CN 2012101583982A CN 201210158398 A CN201210158398 A CN 201210158398A CN 103424767 A CN103424767 A CN 103424767A
Authority
CN
China
Prior art keywords
delayed neutron
content
potpourri
time
mixture
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.)
Granted
Application number
CN2012101583982A
Other languages
Chinese (zh)
Other versions
CN103424767B (en
Inventor
肖才锦
张贵英
倪邦发
刘存兄
王平生
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 Institute of Atomic of Energy
Original Assignee
China Institute of Atomic of Energy
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 Institute of Atomic of Energy filed Critical China Institute of Atomic of Energy
Priority to CN201210158398.2A priority Critical patent/CN103424767B/en
Publication of CN103424767A publication Critical patent/CN103424767A/en
Application granted granted Critical
Publication of CN103424767B publication Critical patent/CN103424767B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention discloses a method for measuring the content of 235U and 239Pu in a U-Pu mixture. The method carries out measuring in a delayed neutron mode and comprises the following steps that (1) a reactor is used for irradiating a 235U sample, a 239Pu sample and the mixture, and the count of a delayed neutron along with time is measured; (2) according to the count, measured in the step (1), of the delayed neutron along with time variation, an exponential damping function is used for carrying out fitting on a decay characteristic curve of the delayed neutron along with time variation; (3) according to the decay curve characteristic pattern, a time period before delayed neutron counting rate changing and a time period after delayed neutron counting rate changing are selected, wherein obvious change differences exist in the two time periods, and then unit mass delayed neutron counts of the two time periods are computed to be used as quantitative coefficients of the 235U and the 239Pu in the U-Pu mixture; (4) a system of linear equations is built, and the content of the 235U and the 239Pu is computed through the system of the linear equations. The method for measuring the content of the 235U and the 239Pu in the U-Pu mixture is accurate and rapid in measurement and wide in application range.

Description

In a kind of mensuration U-Pu potpourri 235U and 239The method of Pu content
Technical field
The present invention relates to nuclear physics, nuclear engineering technical field, particularly a kind of delayed neutron counting method of utilizing is measured in the U-Pu potpourri 235U and 239The method of Pu content.
 
Background technology
In IAEA " illicit trafficking and dealing database ", 1993～calendar year 2001 of record in more than 550 event, approximately has half to relate to nuclear material.This illicit trafficking and dealing nuclear material are global problems, prevent just needs of illicit trafficking and dealing nuclear material 235U, 239Pu identification and quantitatively detection.Contain special nuclear material in nuclear warhead, in following degree of depth nuclear disarmament, nuclear warhead is surveyed also needs 235U, 239Pu identification and quantitatively detection.
Identify by the radioactivity of fissioner itself that the passive detection mode of nuclear warhead or nuclear material is more difficult provides clear and definite conclusion.Under the neutron external source is irradiated, the secondary that the measurement nuclear warhead produces or the active probe mode that penetrates the ray of nuclear warhead are to measure the effective ways of the nuclear materials such as high-enriched uranium, plutonium.Determine whether nuclear material of hiding article, differentiate that nuclear material is highly enricked uranium or plutonium, nuclear fuel cycle aftertreatment etc. all needs a kind of quick, sensitive lossless detection method, due to utilization 235U, 239The delayed neutron that the fission fragment that the Pu fission produces discharges has the different half life period and yield can can't harm, fast, not need Chemical Decomposition ground to carry out in potpourri 235U and 239The mensuration of Pu content is in a kind of effectively quantitatively U-Pu potpourri so bring out the fission delayed neutron measurement 235U and 239The method of Pu content.
The document great majority that can find are at present measured the quality of single fissilenuclide by the delayed neutron counting method, for example: " GEOLOGICAL AND GEOCHEMICAL " 57-59 page of publishing in February, 1989 discloses name and has been called: " measuring the content of uranium thorium with delay fission neutron technique ", the 2nd phase of Nuclear Technology magazine of publishing in 1985 discloses name and has been called: articles such as " measurement mechanisms of surveying uranium by the delayed neutron counting method " is mainly to adopt the delayed neutron measurement method to measure the content of Uranium In Geological Samples.
In 246～251 pages of " Nuclear Instruments and Methods in Physics Research B " the 215th volumes of publishing in 2004, " Rapid determination of uranium and plutonium content in mixtures through measurement of the intensity-time curve of delayed neutrons " discloses a kind of available units quality 235U and 239The counting rate of Pu delayed neutron is set up equation and can be drawn in the U-Pu potpourri 235U and 239Pu concentration, the method is to adopt time point to carry out analytical calculation, data processing complex, accuracy rate is low as a result.
Summary of the invention
The present invention has overcome deficiency of the prior art, provide a kind of and measured accurately, fast, in the mensuration U-Pu potpourri of applied range 235U and 239The method of Pu content.
In order to solve the problems of the technologies described above, the present invention is achieved by the following technical solutions:
In a kind of mensuration U-Pu potpourri 235U and 239The method of Pu content, the method utilizes delayed neutron method to be measured, and comprises the following steps: (1) utilizes reactor irradiation 235U, 239Pu sample and potpourri, measure delayed neutron counting in time; (2) the delayed neutron temporal evolution recorded according to step (1), with decaying exponential function matching delayed neutron decay temporal evolution characteristic curve; (3) choose according to decay curve two time periods that the delayed neutron counting rate changes the obvious front and back of difference, calculate the unit mass delayed neutron counting of two time periods as measuring quantitative coefficient in the U-Pu potpourri; (4) set up system of linear equations, by system of linear equations, try to achieve content.
The present invention is all right:
The time period of choosing in described step (3) is two time periods before and after 10s.
Described two time periods are 1～10s and 11～20s.
Compared with prior art, the invention has the beneficial effects as follows:
The present invention utilizes the delayed neutron counting method, chooses two time periods that the delayed neutron counting rate changes the obvious front and back of difference, calculates the unit mass delayed neutron counting of two time periods as in potpourri 235U and 239The quantitative coefficient of Pu, set up linear equation, calculates in potpourri 235U and 239The content of Pu is more accurate, and finding speed is fast.The present invention is in the quantitative measurement potpourri 235U and 239The content of Pu provides a kind of new thinking and method.
 
The accompanying drawing explanation
Fig. 1 235U, 239Pu, U-Pu potpourri delayed neutron fall time curve
Embodiment
Below in conjunction with accompanying drawing and embodiment, the present invention is described in further detail:
Embodiment 1
Will be containing 13.1 μ g 235U, 11.9 μ g 235U+10.2 μ g 239Pu and 10.2 μ g 239Three tygon boxes of Pu sample are placed in and run the rabbit system, and the vertical channel of squeezing into 30kW micro reactor (being called for short micro-heap) irradiates 30s, after cooling about 2s, sample is sent back in delayed neutron detector and measures delayed neutron.The DSA-1000 digital spectrum instrument is operated in multi channel scaling (MCS) pattern, and MCS is made as 1s interval time, measures 100s.Fig. 1 is 235U, 239The delayed neutron fall time curvilinear characteristic figure of Pu and composition thereof sample.
The delayed neutron fall time curve of three samples has at the 10s anterioposterior curve by dispersing the feature that is converted to gradually convergence, therefore selects unit mass delayed neutron counting between 1-10s and 11-20s as in potpourri 235U and 239The quantitative coefficient of Pu, suppose in potpourri 235The quality of U is x1, 239The quality of Pu is y1, sets up linear equation:
Figure 894230DEST_PATH_IMAGE001
Solving equation obtains: x1=12.0 μ g, y1=9.5 μ g
Draw in the U-Pu potpourri 235U and 239Pu content is respectively 12.0 and 9.5 μ g, and uncertainty is respectively 0.8% and 6.9% relatively.Table 1 has provided this three sample delayed neutron counting results.
 
Table 1 13.1 μ g 235U, 11.9 μ g 235U+10.2 μ g 239Pu and 10.2 μ g 239Tri-sample measurement data of Pu
Figure 631242DEST_PATH_IMAGE002
Embodiment 2
Will be containing 13.1 μ g 235U, 20.2 μ g 235U+10.2 μ g 239Pu and 10.2 μ g 239Three tygon boxes of Pu sample are placed in and run the rabbit system, and the vertical channel of squeezing into 30kW micro reactor (being called for short micro-heap) irradiates 30s, after cooling about 2s, sample is sent back in delayed neutron detector and measures delayed neutron.The DSA-1000 digital spectrum instrument is operated in multi channel scaling (MCS) pattern, and MCS is made as 1s interval time, measures 100s.Unit mass delayed neutron counting between selection 2-8s and 11-17s is as in potpourri 235U and 239The quantitative coefficient of Pu, suppose in potpourri 235The quality of U is x1, 239The quality of Pu is y1, sets up linear equation:
Figure 216944DEST_PATH_IMAGE003
Solving equation obtains: x1=5.0 μ g, y1=10.5 μ g
Draw in the U-Pu potpourri 235U and 239Pu content is respectively 5.0 and 10.5 μ g, and uncertainty is respectively 1.9% and 2.9% relatively.Table 2 has provided this three sample delayed neutron counting results.
 
Table 2 5.1 μ g 235U, 5.1 μ g 235U+10.2 μ g 239Pu and 10.2 μ g 239Tri-sample measurement data of Pu
Figure 646788DEST_PATH_IMAGE004

Claims (3)

1. measure in the U-Pu potpourri for one kind 235U and 239The method of Pu content, is characterized in that, the method utilizes delayed neutron method to be measured, and comprises the following steps: (1) utilizes reactor irradiation 235U, 239Pu sample and potpourri, measure delayed neutron counting in time; (2) the delayed neutron temporal evolution recorded according to step (1), with decaying exponential function matching delayed neutron decay temporal evolution characteristic curve; (3) choose according to the decay curve characteristic pattern two time periods that the delayed neutron counting rate changes the obvious front and back of difference, calculate the unit mass delayed neutron counting of two time periods as measuring quantitative coefficient in the U-Pu potpourri; (4) set up system of linear equations, by system of linear equations, try to achieve content.
2. in a kind of mensuration U-Pu potpourri according to claim 1 235U and 239The method of Pu content, is characterized in that, the time period of choosing in described step (3) is two time periods before and after 10s.
3. in a kind of mensuration U-Pu potpourri according to claim 2 235U and 239The method of Pu content, is characterized in that, described two time periods are 1～10s and 11～20s.
CN201210158398.2A 2012-05-22 2012-05-22 In a kind of mensuration U-Pu potpourri 235u and 239the method of Pu content Active CN103424767B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201210158398.2A CN103424767B (en) 2012-05-22 2012-05-22 In a kind of mensuration U-Pu potpourri 235u and 239the method of Pu content

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201210158398.2A CN103424767B (en) 2012-05-22 2012-05-22 In a kind of mensuration U-Pu potpourri 235u and 239the method of Pu content

Publications (2)

Publication Number Publication Date
CN103424767A true CN103424767A (en) 2013-12-04
CN103424767B CN103424767B (en) 2016-03-30

Family

ID=49649783

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201210158398.2A Active CN103424767B (en) 2012-05-22 2012-05-22 In a kind of mensuration U-Pu potpourri 235u and 239the method of Pu content

Country Status (1)

Country Link
CN (1) CN103424767B (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104035118A (en) * 2014-06-25 2014-09-10 中国原子能科学研究院 Uranium content detection method
CN108828651A (en) * 2018-08-08 2018-11-16 中国原子能科学研究院 A kind of active neutron assay method of uranium plutonium content in cladding waste
CN111175334A (en) * 2020-01-09 2020-05-19 中国原子能科学研究院 Automatic graphite crystal pre-diffraction X-ray fluorescence instrument system

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101335061A (en) * 2008-08-06 2008-12-31 中国原子能科学研究院 Fuel Damage Delayed Neutron Detection Device
CN101833116A (en) * 2004-03-01 2010-09-15 瓦润医药系统公司 Existence by neutron and delayed neutron identification special nuclear material

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101833116A (en) * 2004-03-01 2010-09-15 瓦润医药系统公司 Existence by neutron and delayed neutron identification special nuclear material
CN101335061A (en) * 2008-08-06 2008-12-31 中国原子能科学研究院 Fuel Damage Delayed Neutron Detection Device

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
X.LI ET AL.: "Rapid determination of uranium and plutonium content in mixtures through measurement of the intensity-time curve of delayed neutrons", 《NUCLEAR INSTRUMENTS AND METHODS IN PHYSICS RESEARCH B》, vol. 215, 31 December 2004 (2004-12-31), pages 246 - 251, XP004484287, DOI: 10.1016/S0168-583X(03)01822-6 *

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104035118A (en) * 2014-06-25 2014-09-10 中国原子能科学研究院 Uranium content detection method
CN108828651A (en) * 2018-08-08 2018-11-16 中国原子能科学研究院 A kind of active neutron assay method of uranium plutonium content in cladding waste
CN108828651B (en) * 2018-08-08 2020-08-21 中国原子能科学研究院 Active neutron analysis method for uranium plutonium content in waste cladding
CN111175334A (en) * 2020-01-09 2020-05-19 中国原子能科学研究院 Automatic graphite crystal pre-diffraction X-ray fluorescence instrument system
CN111175334B (en) * 2020-01-09 2021-11-02 中国原子能科学研究院 Automatic graphite crystal pre-diffraction X-ray fluorescence instrument system

Also Published As

Publication number Publication date
CN103424767B (en) 2016-03-30

Similar Documents

Publication Publication Date Title
CN102175704B (en) Uranium isotope abundance analysis method
Ren et al. The C 6 D 6 detector system on the Back-n beam line of CSNS
Alnour et al. New approach for calibration the efficiency of HpGe detectors
Britton et al. Preliminary simulations of NaI (Tl) detectors, and coincidence analysis using event stamping
CN103424767B (en) In a kind of mensuration U-Pu potpourri 235u and 239the method of Pu content
CN109557575A (en) A kind of neutron multiplicity measuring device and its application method
Baccolo et al. Development of a low background alpha–beta/gamma coincidence detector
CN107238856A (en) A kind of determination method of high flux deuterium tritium accelerator for neutron production average neutron energy
Wu et al. Standard spectrum measurement and simulation of elemental capture spectroscopy log
Bergaoui et al. Prompt gamma-ray neutron activation analysis of boron using Deuterium–Deuterium (D–D) neutron generator
Kalinnikov et al. Investigation of LYSO and GSO crystals and simulation of the calorimeter for COMET experiment
KR20110091264A (en) Unified non-destructive assay system to measure a given nuclide amount in the mixed nuclear material sample, which is composed of a measurement part and a unified analysis part
Jiang et al. Geant4 simulation of multi-sphere spectrometer response function and the detection of 241 Am–Be neutron spectrum
Xiao et al. Delayed neutron counting at CIAE
Ali et al. Benchmarking Neutron Counting System for Passive Measurements and Active Interrogation of Unknown Objects for Fissile and Fissionable Materials Determination
Qiao et al. Determination of 235U isotopic abundance by fission-yield difference method
Romodanov et al. Monitoring of 235 U content of fuel assemblies for nuclear reactors based on neutron and γ-ray scintillation detector systems
Yang et al. A 235U mass measurement method for UO2 rod assembly based on the n/γ joint measurement system
Hahn et al. Detector Calibration to Quantify Random Summing in HPGe Spectroscopy
Frame Neutron Multiplicity Analysis
Langford et al. PROSPECT–A precision oscillation and spectrum experiment
Adeleye et al. Calibration of a gamma-ray spectrometer using electronic spreadsheet package and dedicated spectral analysis software.
Putman RECENT DEVELOPMENTS IN THE USE OF RADIOISOTOPES FOR INDUSTRIAL RESEARCH AND PROCESS CONTROL
CN102590251B (en) Method for measuring oxidation percentage of metallic plutonium
Kulisek et al. Hybrid Enrichment Verification Array: Investigations of the High-Energy Gamma-Ray Signature Origin and Use for Partial Defect Detection

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
C14 Grant of patent or utility model
GR01 Patent grant