CN116718626B - Data acquisition and analysis system based on neutron multiple measurement - Google Patents
Data acquisition and analysis system based on neutron multiple measurement Download PDFInfo
- Publication number
- CN116718626B CN116718626B CN202310577336.3A CN202310577336A CN116718626B CN 116718626 B CN116718626 B CN 116718626B CN 202310577336 A CN202310577336 A CN 202310577336A CN 116718626 B CN116718626 B CN 116718626B
- Authority
- CN
- China
- Prior art keywords
- neutron
- count
- measurement
- personal computer
- detection limit
- 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.)
- Active
Links
- 238000005259 measurement Methods 0.000 title claims abstract description 60
- 238000004458 analytical method Methods 0.000 title claims abstract description 34
- 238000009826 distribution Methods 0.000 claims abstract description 28
- 238000007405 data analysis Methods 0.000 claims abstract description 13
- 238000001514 detection method Methods 0.000 claims description 37
- 239000000463 material Substances 0.000 claims description 27
- 238000000605 extraction Methods 0.000 claims description 18
- 238000000034 method Methods 0.000 claims description 16
- 238000004364 calculation method Methods 0.000 claims description 11
- 239000000941 radioactive substance Substances 0.000 claims description 3
- 238000005516 engineering process Methods 0.000 abstract description 10
- 238000005457 optimization Methods 0.000 abstract description 4
- 230000000694 effects Effects 0.000 description 6
- 230000004992 fission Effects 0.000 description 5
- 238000006243 chemical reaction Methods 0.000 description 4
- 238000000691 measurement method Methods 0.000 description 3
- 230000009286 beneficial effect Effects 0.000 description 2
- JJWKPURADFRFRB-UHFFFAOYSA-N carbonyl sulfide Chemical compound O=C=S JJWKPURADFRFRB-UHFFFAOYSA-N 0.000 description 2
- 238000003745 diagnosis Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000012857 radioactive material Substances 0.000 description 2
- 230000008859 change Effects 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 230000000155 isotopic effect Effects 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000002269 spontaneous effect Effects 0.000 description 1
- 238000003860 storage Methods 0.000 description 1
Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N23/00—Investigating 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
- G01N23/22—Investigating 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
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T3/00—Measuring neutron radiation
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Physics & Mathematics (AREA)
- General Health & Medical Sciences (AREA)
- Biochemistry (AREA)
- Analytical Chemistry (AREA)
- Chemical & Material Sciences (AREA)
- Immunology (AREA)
- Pathology (AREA)
- High Energy & Nuclear Physics (AREA)
- Molecular Biology (AREA)
- Spectroscopy & Molecular Physics (AREA)
- Measurement Of Radiation (AREA)
Abstract
The invention discloses a data acquisition and analysis system based on neutron multiple measurement, which comprises a detector, a digitizer and an industrial personal computer, wherein the detector is used for detecting the neutron multiple measurement; the detector is used for detecting neutrons emitted by the sample, and outputs a pulse signal every time a neutron event is detected; the digitizer is used for acquiring the arrival time of each pulse signal and transmitting the arrival time to the industrial personal computer; the industrial personal computer is used for storing neutron event time stamps transmitted by the digitizer, carrying out online time correlation coincidence analysis on the measured pulse signals to obtain neutron multiple distribution of the pulse signals, and judging, analyzing and storing the obtained neutron multiple distribution data. The invention has the advantages of both a shift register-based data acquisition technology and a digital acquisition-based offline analysis technology, thereby facilitating the calibration of system working parameters and the optimization of data analysis parameters and facilitating the measurement of normal operation of the system.
Description
Technical Field
The invention relates to the technical field of neutron multiple measurement, in particular to a data acquisition and analysis system based on neutron multiple measurement.
Background
The fissile material can possibly generate neutrons due to spontaneous or induced fission, and the neutron penetrating capability is high, so that nondestructive diagnosis of the fissile material cracking rate, quality or sample alpha activity in the sample is realized by utilizing the sample emergent neutrons, and the nondestructive diagnosis is widely applied to measurement technology. Non-destructive neutron-based measurement techniques are particularly advantageous when the sample density is high. However, because radionuclides including fissile material in the sample may emit alpha, these alpha's may emit neutrons as a result of the (alpha, n) reaction upon striking the light material. Thus, obtaining information about fissile material within a sample based on the total neutron emissivity of the sample may introduce large deviations. Because a single fission reaction may emit multiple neutrons, while a single (α, n) reaction may generate only one neutron, neutron multiplexing measurement techniques may utilize this difference to directly correlate the measurement results to the rate of fission reactions within the sample, thereby accurately extracting information about fissile material within the sample. Thus, neutron multiplex measurement techniques are widely used for the measurement of radioactive materials, including but not limited to the rate of fission, the mass of fissile material, and the alpha activity of the sample.
The key to measuring neutron multiplexing information of a sample is to acquire neutron multiplexing distribution. Currently, there are two main methods for implementing neutron multiplex distribution: the first method utilizes a coincidence analyzer based on a shift register to acquire and analyze neutron signals of a detector, and can directly give out multiple distributions of neutrons; the second method utilizes a digital acquisition technology to acquire the arrival time of each neutron signal of the detector, and then utilizes an off-line time analysis method to reconstruct multiple distributions of neutrons. The two methods have the advantages that the measurement result can be given immediately after the measurement is finished, but parameters including, but not limited to, pre-delay, long delay, coincidence door width and the like related to reconstruction of neutron multiple distribution must be given in advance and cannot be changed; the second method has the advantages that the method can change and optimize data analysis parameters including but not limited to pre-delay, long delay, coincidence door width and the like, so that more reliable results can be obtained, meanwhile, the method can also analyze dead time, coincidence door efficiency and the like, which is very beneficial to the scale and state adjustment of working parameters of a measurement system, but the method cannot obtain measurement results in time, and measurement data generated by the method occupy a large storage space, so that the use of a related measurement system is inconvenient.
The existing data acquisition and analysis technology is inconvenient for system working parameter calibration and data analysis parameter optimization or is inconvenient for normal system working measurement.
Disclosure of Invention
Aiming at the defects in the prior art, the data acquisition and analysis system based on neutron multiple measurement solves the problems that the traditional data acquisition and analysis technology is not convenient for system working parameter scale and data analysis parameter optimization or normal working measurement of the system.
In order to achieve the aim of the invention, the invention adopts the following technical scheme: a data acquisition and analysis system based on neutron multiple measurement comprises a detector, a digitizer and an industrial personal computer;
the detector is used for detecting neutrons emitted by the sample, and outputs a pulse signal every time a neutron event is detected;
the digitizer is used for acquiring the arrival time of each pulse signal and transmitting the arrival time to the industrial personal computer;
the industrial personal computer is used for storing neutron event time stamps transmitted by the digitizer, carrying out online time correlation coincidence analysis on the measured pulse signals to obtain neutron multiple distribution of the pulse signals, and judging, analyzing and storing the obtained neutron multiple distribution data.
Further: the industrial personal computer is provided with control software, and the working modes of the industrial personal computer comprise a debugging mode and a measuring mode.
Further: when the industrial personal computer works in a debugging mode, the industrial personal computer stores the time stamp of the neutron event transmitted by the digitizer in a hard disk so as to facilitate offline analysis.
Further: when the industrial personal computer works in a measurement mode, the industrial personal computer performs online time association coincidence analysis on the measured pulse signals to obtain neutron multiple distribution of the pulse signals, and judges, analyzes and stores the obtained neutron multiple distribution data.
Further: the neutron multiple distribution can extract total count S, double coincidence count D and triple coincidence count T, and the specific extraction method comprises the following steps:
D＝S(f 1 -b 1 )
T＝S[f 2 -b 2 -2b 1 (f 1 -b 1 )]/2
wherein f 1 、f 2 、b 1 And b 2 All are intermediate parameters, and the calculation formula is as follows:
in the above, P R+A And P A For said neutron multiplex distribution, P R+A (v) represents the count of v events in the R+A window, P A (v) represents the count of v events in the A window, and Max represents the counted P R+A (v) and P A A maximum value of v of (v).
Further: the method for judging the neutron multiple distribution data specifically comprises the following steps:
setting a cutoff parameter Ks according to neutron multiple distribution of the radioactive substance which is measured, and calculating v>At Ks, P measured under normal conditions R+A (v) and P A (v) are all 0;
calculating an updated double coincidence count D 'and a triple coincidence count T' through the truncated parameters Ks;
if the relative deviation between D 'and D, T' and T exceeds a set threshold, judging that the measurement data fail, otherwise, judging that the measurement data are valid;
and when the measured data are valid, judging whether the measured data are larger than a system detection limit, and obtaining the count rate related to fissile material target information extraction.
Further: the calculation formulas of the D 'and the T' are as follows:
D′＝S′(f 1 -b 1 )
T′＝S′[f 2 -b 2 -2b 1 (f 1 -b 1 )]/2
in the above formula, S ' is the updated total count, D ' is the updated double coincidence count, and T ' is the updated triple coincidence count;
wherein f 1 、f 2 、b 1 And b 2 All are intermediate parameters, and the calculation formula is as follows:
in the above formula, ks is a set truncation parameter.
Further: the method for judging whether the measured data is larger than the system detection limit comprises the following steps:
the corresponding count rates RS, RD and RT are obtained by removing the measurement time by S, D, T, the count rate parameters related to the extraction of the target information of the fissile material are defined as RS, RD or RT, the detection limit of the parameters related to the extraction of the target information of the fissile material is calculated, and the count rate parameters related to the extraction of the target information of the fissile material and the detection limit corresponding to the count rate parameters are compared: if the count rate parameter is greater than the corresponding detection limit, carrying out data analysis by using the count rate; if the count rate parameter is smaller than the corresponding detection limit, the detection limit is used for replacing the count rate parameter for data analysis.
Further: the specific calculation formula of the detection limit of the parameters involved in fissile material target information extraction is as follows:
in the above formula, t is the measurement time, C b For background count rate corresponding to count parameter, i.e. count rate when no sample is measured, if C b Representing RS, L is the detection limit of RS, if C b Represents RD, L is the limit of detection of RD, if C b And if the signal represents RT, L is the detection limit of RT.
The beneficial effects of the invention are as follows: the data acquisition and analysis system based on digital acquisition provided by the invention has two working modes for selection: when the working parameter scale of the measuring system and the data analysis parameters are optimized, the time stamp of the neutron event measured is saved so as to perform offline analysis; when the measurement system executes a normal measurement task, the on-line time correlation coincidence analysis technology is adopted to realize the instant acquisition of neutron multiple distribution, so as to realize the rapid extraction of fissile material target information. The system has the advantages of a shift register-based data acquisition technology and a digital acquisition-based offline analysis technology, is convenient for system working parameter scale and data analysis parameter optimization, and is also convenient for normal working measurement of the system.
Drawings
FIG. 1 is a block diagram of a system architecture of the present invention;
FIG. 2 is a schematic diagram of the workflow of the data acquisition and analysis system of the present invention.
Detailed Description
The following description of the embodiments of the present invention is provided to facilitate understanding of the present invention by those skilled in the art, but it should be understood that the present invention is not limited to the scope of the embodiments, and all the inventions which make use of the inventive concept are protected by the spirit and scope of the present invention as defined and defined in the appended claims to those skilled in the art.
As shown in fig. 1, a neutron multiple measurement-based data acquisition and analysis system comprises a detector, a digitizer and an industrial personal computer;
the detector is used for detecting neutrons emitted by the sample, and outputs a pulse signal every time a neutron event is detected;
the digitizer is used for acquiring the arrival time of each pulse signal and transmitting the arrival time to the industrial personal computer;
the control software on the industrial personal computer is designed into two working modes: the "debug" mode and "measurement" mode, the specific modes of operation are set by the operator, the main workflow of which is described in fig. 2. When the system works in a debugging mode, the industrial personal computer stores the neutron event time stamp transmitted by the digitizer in the hard disk so as to facilitate detailed offline analysis; when the system works in a measurement mode, the industrial personal computer performs online time correlation coincidence analysis on the measured signals to obtain neutron multiple distribution of the measurement, and judges, analyzes and stores the obtained data. The "debug" and "measure" modes are just names, but other names may be substituted.
If the data acquisition and analysis system performs a measurement mode, the neutron multiple distribution of the measurement, namely P, can be directly acquired due to the adoption of an online time-correlated coincidence analysis technology R+A And P A . By P R+A And P A The total count (S), the double coincidence count (D) and the triple coincidence count (T) can be obtained, and the specific extraction method is as follows:
D＝S(f 1 -b 1 ) (2)
T＝S[f 2 -b 2 -2b 1 (f 1 -b 1 )]/2 (3)
wherein:
wherein P is R+A (v) represents the count of v events in the R+A window, P A (v) represents the count of v events in the A window, and Max represents the counted P R+A And P A Is a maximum value of v.
Because the interaction of cosmic rays with heavy elements near the measurement system can lead to the rupture of the nuclei of the heavy elements to emit a large number of neutrons at one time, these neutrons not only being at P R+A And P A Where v is small, a count is caused at P R+A And P A The larger position of the center v can cause a large amount of counting, and once the position of the center v is counted, the effect on D, T is very strong, so that a large deviation of a measurement result is caused; at the same time, if the measuring system vibrates due to external force, the measured P can be caused R+A And P A Where v is larger, this causes counting. The neutron multiplex distribution due to the measured radioactive material is mainly concentrated where v is small, although P is directly discarded R+A And P A A larger count of the medium v can reduce the universeThe effect of rays and vibrations on the measurement results, but it cannot eliminate cosmic rays and vibrations induced P R+A And P A The smaller of the counts of v has an effect on the measurement. Therefore, the present invention proposes a method for determining whether the measured data is valid by setting a cutoff parameter Ks, and the program performs the result analysis only when the data is valid. If the measured data is judged to be invalid, the measuring system carries out data measurement again. The specific method for judging whether the measured data is valid is as follows:
(1) setting a cutoff parameter Ks according to neutron multiplex distribution of the radioactive substance which is measured, wherein Ks is a value, and v is as>At Ks, P measured under normal conditions R+A (v) and P A (v) are all 0;
(2) s, D and T are calculated according to the calculation methods given by the formulas (1) - (7), max in the formulas (1) - (7) is replaced by Ks, and D 'and T' are calculated again;
(3) if the relative deviation between D 'and D, T' and T exceeds a set threshold (e.g., 5% or 10%), then the current measurement data is determined to be invalid, otherwise the data is valid.
If the measurement data is valid, a determination is then made as to whether the measurement is greater than a system detection limit. First, the measurement time is divided by S, D and T to obtain the corresponding count rates RS, RD and RT. Then, it is clear whether the count rate parameter involved in the extraction of fissile material target information is RS, RD or RT, or two or all of them. Then, calculating the detection limit of parameters related to fissile material target information extraction, wherein the specific calculation method comprises the following steps:
wherein t is the measurement time, C b For background count rate corresponding to count parameter, i.e. count rate when no sample is measured, if C b Representing RS, L is the detection limit of RS, if C b Represents RD, L is the limit of detection of RD, if C b And if the signal represents RT, L is the detection limit of RT. Finally, the extraction of target information of the contrast fissile material involvesAnd the count rate parameter and the corresponding detection limit thereof: if the count rate parameter is greater than the corresponding detection limit, performing subsequent data analysis by using the count rate parameter; if the count rate parameter is less than its corresponding detection limit, the detection limit is used to replace the count rate parameter for subsequent data analysis. The detection limit judgment is carried out in consideration of the fact that when the measurement count parameter is smaller than the detection limit, the confidence of the measurement result is low, the relative deviation between repeated measurement results is large, and unstable misunderstanding of a measurement system is easily caused to people.
After the detection limit is judged, the counting rate parameter related to fissile material target information extraction is obtained, and the fissile material target information can be directly given out by directly combining the working parameters of the system and a set calculation formula during data analysis. The system operating parameters include, but are not limited to, scale parameters, detection efficiency, coincidence gate efficiency, sample mass, and isotopic abundance information of fissile elements, and the fissile material target information includes, but is not limited to, fission rate, mass of fissile material, radioactivity, and radioactivity specific activity. If the detection limit of the related counting rate parameter is used in the process of extracting the fissile material target information, a similar reminding character such as that the measurement result is lower than the system detection limit XX is marked in the result, wherein XX is the extracted fissile material target information.
Claims (6)
1. The data acquisition and analysis system based on neutron multiple measurement is characterized by comprising a detector, a digitizer and an industrial personal computer;
the detector is used for detecting neutrons emitted by the sample, and outputs a pulse signal every time a neutron event is detected;
the digitizer is used for acquiring the arrival time of each pulse signal and transmitting the arrival time to the industrial personal computer;
the industrial personal computer is used for storing neutron event time stamps transmitted by the digitizer, carrying out online time correlation coincidence analysis on the measured pulse signals to obtain neutron multiple distribution of the pulse signals, and judging, analyzing and storing the obtained neutron multiple distribution data;
the neutron multiple distribution can extract total count S, double coincidence count D and triple coincidence count T, and the specific extraction method comprises the following steps:
wherein, f1, f2, b1 and b2 are all intermediate parameters, and the calculation formula is:
in the formula, PR+A and PA are neutron multiple distribution, PR+A (v) represents the count of v events in the range of an R+A window, PA (v) represents the count of v events in the range of an A window, and Max represents the maximum value of v of PR+A (v) and PA (v) which are counted;
the method for judging the neutron multiple distribution data specifically comprises the following steps:
setting a cutoff parameter Ks according to neutron multiplex distribution of the measured radioactive substances, wherein when v > Ks, PR+A (v) and PA (v) which are measured under normal conditions are 0;
calculating an updated double coincidence count D 'and a triple coincidence count T' through the truncated parameters Ks;
if the relative deviation between D 'and D, T' and T exceeds a set threshold, judging that the measurement data fail, otherwise, judging that the measurement data are valid;
when the measured data is effective, judging whether the measured data is larger than a system detection limit, and obtaining the counting rate related to fissile material target information extraction;
the calculation formulas of the D 'and the T' are as follows:
in the above formula, S ' is the updated total count, D ' is the updated double coincidence count, and T ' is the updated triple coincidence count;
wherein, f1, f2, b1 and b2 are all intermediate parameters, and the calculation formula is:
in the above formula, ks is a set truncation parameter.
2. The neutron multiple measurement-based data acquisition and analysis system according to claim 1, wherein the industrial personal computer is provided with control software, and the working modes of the industrial personal computer comprise a debugging mode and a measuring mode.
3. The neutron multiplicity measurement-based data acquisition and analysis system of claim 1, wherein when the industrial personal computer is operating in "debug" mode, the industrial personal computer stores the time stamp of the neutron event transmitted from the digitizer in a hard disk for offline analysis.
4. The neutron multiple measurement-based data acquisition and analysis system according to claim 1, wherein when the industrial personal computer works in a measurement mode, the industrial personal computer performs online time-correlated coincidence analysis on the measured pulse signals to acquire neutron multiple distribution of the pulse signals, and judges, analyzes and stores the acquired neutron multiple distribution data.
5. The neutron multiplexing measurement-based data acquisition and analysis system according to claim 1, wherein the method for judging whether the measured data is greater than the system detection limit is specifically as follows:
the corresponding count rates RS, RD and RT are obtained by removing the measurement time by S, D, T, the count rate parameters related to the extraction of the target information of the fissile material are defined as RS, RD or RT, the detection limit of the parameters related to the extraction of the target information of the fissile material is calculated, and the count rate parameters related to the extraction of the target information of the fissile material and the detection limit corresponding to the count rate parameters are compared: if the count rate parameter is greater than the corresponding detection limit, carrying out data analysis by using the count rate; if the count rate parameter is smaller than the corresponding detection limit, the detection limit is used for replacing the count rate parameter for data analysis.
6. The neutron multiplex measurement-based data acquisition and analysis system of claim 5, wherein the specific calculation formula of the detection limit of the parameter involved in the fissile material target information extraction is:
in the above formula, t is the measurement time, cb is the background count rate of the corresponding count parameter, i.e. the count rate when no sample is measured, L is the detection limit of RS if Cb represents RS, L is the detection limit of RD if Cb represents RD, and L is the detection limit of RT if Cb represents RT.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310577336.3A CN116718626B (en) | 2023-05-22 | 2023-05-22 | Data acquisition and analysis system based on neutron multiple measurement |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310577336.3A CN116718626B (en) | 2023-05-22 | 2023-05-22 | Data acquisition and analysis system based on neutron multiple measurement |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN116718626A CN116718626A (en) | 2023-09-08 |
| CN116718626B true CN116718626B (en) | 2023-12-29 |
Family
ID=87868860
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202310577336.3A Active CN116718626B (en) | 2023-05-22 | 2023-05-22 | Data acquisition and analysis system based on neutron multiple measurement |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN116718626B (en) |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104678425A (en) * | 2015-02-02 | 2015-06-03 | 中国原子能科学研究院 | Fast-neutron multiple measuring-analyzing method based on liquid scintillation detector |
| CN109324542A (en) * | 2018-09-12 | 2019-02-12 | 中国原子能科学研究院 | A kind of neutron multiplicity measurement Special pulse signal processor |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8194813B2 (en) * | 2004-10-19 | 2012-06-05 | Lawrence Livermore National Security, Llc | Absolute nuclear material assay using count distribution (LAMBDA) space |
-
2023
- 2023-05-22 CN CN202310577336.3A patent/CN116718626B/en active Active
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104678425A (en) * | 2015-02-02 | 2015-06-03 | 中国原子能科学研究院 | Fast-neutron multiple measuring-analyzing method based on liquid scintillation detector |
| CN109324542A (en) * | 2018-09-12 | 2019-02-12 | 中国原子能科学研究院 | A kind of neutron multiplicity measurement Special pulse signal processor |
Also Published As
| Publication number | Publication date |
|---|---|
| CN116718626A (en) | 2023-09-08 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Luescher et al. | Search for ββ decay in 136Xe: new results from the Gotthard experiment | |
| Tovesson et al. | Cross Sections for 239Pu (n, f) and 241Pu (n, f) in the Range En= 0.01 eV to 200 MeV | |
| CN111221030A (en) | Neutron-gamma detector based on physical integration and neutron-gamma online screening method | |
| EP3662307B1 (en) | Method and system for pulse multiplicity counting with dead time correction | |
| Jaffke et al. | Determining reactor fuel type from continuous antineutrino monitoring | |
| GB2600505A (en) | Estimation method and monitoring system for plutonium concentration in uranium plutonium solution system based on neutron coincidence counting | |
| CN116718626B (en) | Data acquisition and analysis system based on neutron multiple measurement | |
| EP1707992B1 (en) | Improvements in and relating to monitoring of radioactive emissions | |
| Bruggeman et al. | Neutron coincidence counting based on time interval analysis with one-and two-dimensional Rossi-alpha distributions: an application for passive neutron waste assay | |
| CN102621170B (en) | Method for automatically determining measurement time in detection of energy spectrometer | |
| Nakao et al. | Developments of a new data acquisition system at ANNRI | |
| KR101197002B1 (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 | |
| CN110764157B (en) | Suspicious object detection method | |
| US5550382A (en) | Process and apparatus for compacting informations to be stored and processing said compacted informations | |
| Koskelo et al. | Sustainability of gamma-ray isotopic evaluation codes | |
| Butcher et al. | Digital coincidence counting–initial results | |
| RU2548132C1 (en) | Detection and identification of radioactive abnormalities in natural media and flows | |
| Sellinschegg | A statistic sensitive to deviations from the zero-loss condition in a sequence of material balances | |
| Nagy | Neutron Multiplicity Counting with the Analysis of Continuous Detector Signals | |
| Jingwen et al. | Absolute measurements of 235 U and 239 Pu fission cross section induced by 14.7 MeV neutrons | |
| Manzanillas | Performance of the SoLid Reactor Neutrino Detector | |
| JP2002148383A (en) | Diagnosis apparatus and system for deterioration by irradiation | |
| Zucker | Neutron correlation counting for the nondestructive analysis of nuclear materials | |
| Geist | Multiplicity counting | |
| Tovesson et al. | Fission cross-section measurement programme at Lansce |
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 | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |