CN103424767B - In a kind of mensuration U-Pu potpourri 235u and 239the method of Pu content - Google Patents
In a kind of mensuration U-Pu potpourri 235u and 239the method of Pu content Download PDFInfo
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Abstract
The invention discloses a kind of mensuration in U-Pu potpourri
235u and
239the method of Pu content, the method utilizes delayed neutron method to measure, and comprises the following steps: (1) utilizes reactor irradiation
235u,
239pu sample and potpourri, measure delayed neutron counting in time; (2) delayed neutron recorded according to step (1) changes in time, to decay variation characteristic curve in time with decaying exponential function matching delayed neutron; (3) choose according to decay curve characteristic pattern two time periods that delayed neutron counting rate changes the obvious front and back of difference, calculate the unit mass delayed neutron counting of two time periods as quantitative coefficient in mensuration U-Pu potpourri; (4) set up system of linear equations, try to achieve content by system of linear equations.The invention provides a kind ofly to measure accurately, fast, in the mensuration U-Pu potpourri of applied range
235u and
239the method of Pu content.
Description
Technical field
The present invention relates to nuclear physics, nuclear engineering technical field, particularly one utilizes delayed neutron counting method to measure in U-Pu potpourri
235u and
239the method of Pu content.
Background technology
In " illicit trafficking and dealing database " of IAEA, 1993 ~ calendar year 2001 of record is in more than 550 event, about has half to relate to nuclear material.This illicit trafficking and dealing nuclear material are global problems, prevent illicit trafficking and dealing nuclear material just needs
235u,
239pu identifies and quantitatively detects.Containing special nuclear material in nuclear warhead, in future depth nuclear disarmament, nuclear warhead detection also needs
235u,
239pu identifies and quantitatively detects.
Identify that the passive detection mode of nuclear warhead or nuclear material is more difficult by the radioactivity of fissioner itself and provide clear and definite conclusion.Under neutron external source is irradiated, the active probe mode of the secondary measuring nuclear warhead generation or the ray penetrating nuclear warhead measures the effective ways of the nuclear material such as high-enriched uranium, plutonium.Determine hiding article whether nuclear material, 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, owing to utilizing
235u,
239the delayed neutron of the fission fragment release that Pu fission produces has the different half life period and yield can can't harm, fast, do not carry out in potpourri with needing Chemical Decomposition
235u and
239the mensuration of Pu content, so bringing out fission delayed neutron measurement is in a kind of effectively quantitatively U-Pu potpourri
235u and
239the method of Pu content.
The current document great majority that can find measure by the quality of delayed neutron counting method to single fissilenuclide, such as: " GEOLOGICAL AND GEOCHEMICAL " the 57-59 page published in February, 1989 discloses name and is called: " measuring the content of uranium thorium with delay fission neutron technique ", Nuclear Technology magazine the 2nd phase of publishing for 1985 discloses name and is called: articles such as " measurement mechanisms with delayed neutron counting method survey uranium ", mainly adopts delayed neutron measurement method to measure the content of Uranium In Geological Samples.
In " NuclearInstrumentsandMethodsinPhysicsResearchB " the 215th volume 246 ~ 251 pages published for 2004, " Rapiddeterminationofuraniumandplutoniumcontentinmixtures throughmeasurementoftheintensity-timecurveofdelayedneutr ons " 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 U-Pu potpourri
235u and
239pu concentration, the method adopts time point to carry out analytical calculation, data processing complex, and result accuracy rate is low.
Summary of the invention
Instant invention overcomes deficiency of the prior art, provide a kind ofly to measure 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 measure, and comprises the following steps: (1) utilizes reactor irradiation
235u,
239pu sample and potpourri, measure delayed neutron counting in time; (2) delayed neutron recorded according to step (1) changes in time, to decay variation characteristic curve in time with decaying exponential function matching delayed neutron; (3) choose according to decay curve two time periods that delayed neutron counting rate changes the obvious front and back of difference, calculate the unit mass delayed neutron counting of two time periods as quantitative coefficient in mensuration U-Pu potpourri; (4) set up system of linear equations, try to achieve content by system of linear equations.
The present invention is all right:
The time period chosen in described step (3) is two time periods before and after 10s.
Two described time periods are 1 ~ 10s and 11 ~ 20s.
Compared with prior art, the invention has the beneficial effects as follows:
The present invention utilizes delayed neutron counting method, chooses two time periods of the obvious front and back of delayed neutron counting rate change difference, calculates the unit mass delayed neutron counting of two time periods as in potpourri
235u and
239the quantitative coefficient of Pu, sets 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 quantitative measurement potpourri
235u and
239the content of Pu provides a kind of new thinking and countermeasure.
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 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 rabbit system, and the vertical channel 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.DSA-1000 digital spectrum instrument is operated in multi channel scaling (MCS) pattern, and MCS is set to 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 10s anterioposterior curve by dispersing the feature being converted to convergence gradually, and the unit mass delayed neutron counting therefore between selection 1-10s and 11-20s is as in potpourri
235u and
239the quantitative coefficient of Pu, supposes in potpourri
235the quality of U is x1,
239the quality of Pu is y1, sets up linear equation:
Solving equation obtains: x1=12.0 μ g, y1=9.5 μ g
Draw in U-Pu potpourri
235u and
239pu content is respectively 12.0 and 9.5 μ g, and relative uncertainty degree is respectively 0.8% and 6.9%.Table 1 gives this three sample delayed neutron counting results.
Table 113.1 μ g
235u, 11.9 μ g
235u+10.2 μ g
239pu and 10.2 μ g
239pu tri-sample measurement data
Embodiment 2
Will 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 rabbit system, and the vertical channel 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.DSA-1000 digital spectrum instrument is operated in multi channel scaling (MCS) pattern, and MCS is set to 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, supposes in potpourri
235the quality of U is x1,
239the quality of Pu is y1, sets up linear equation:
Solving equation obtains: x1=5.0 μ g, y1=10.5 μ g
Draw in U-Pu potpourri
235u and
239pu content is respectively 5.0 and 10.5 μ g, and relative uncertainty degree is respectively 1.9% and 2.9%.Table 2 gives this three sample delayed neutron counting results.
Table 25.1 μ g
235u, 5.1 μ g
235u+10.2 μ g
239pu and 10.2 μ g
239pu tri-sample measurement data
Claims (3)
1. one kind measures in U ?Pu potpourri
235u and
239the method of Pu content, is characterized in that, the method utilizes delayed neutron method to measure, and comprises the following steps: (1) utilizes reactor irradiation
235u,
239pu sample and potpourri, measure delayed neutron counting in time; (2) delayed neutron recorded according to step (1) changes in time, to decay variation characteristic curve in time with decaying exponential function matching delayed neutron; (3) choose according to the variation characteristic curve in time that decays two time periods that delayed neutron counting rate changes the obvious front and back of difference, calculate the unit mass delayed neutron counting of two time periods as quantitative coefficient in mensuration U ?Pu potpourri; (4) set up system of linear equations, try to achieve content by system of linear equations.
2. one according to claim 1 measure U ?in Pu potpourri
235u and
239the method of Pu content, is characterized in that, the time period chosen in described step (3) is two time periods before and after 10s.
3. one according to claim 2 measure U ?in Pu potpourri
235u and
239the method of Pu content, is characterized in that, two described time periods are 1 ~ 10s and 11 ~ 20s.
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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 |
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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)
Title |
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