CN100570401C - A kind of method of eliminating neutron dose equivalent meter counting loss on every side - Google Patents
A kind of method of eliminating neutron dose equivalent meter counting loss on every side Download PDFInfo
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- CN100570401C CN100570401C CNB2007101192649A CN200710119264A CN100570401C CN 100570401 C CN100570401 C CN 100570401C CN B2007101192649 A CNB2007101192649 A CN B2007101192649A CN 200710119264 A CN200710119264 A CN 200710119264A CN 100570401 C CN100570401 C CN 100570401C
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Abstract
A kind of method of eliminating neutron dose equivalent meter counting loss on every side, exist serious counting loss when in pulsed neutron field or strong neutron field, measuring at this instrument, a kind of effective solution that proposes belongs to the sub-radiation field applied technical field of pulsed neutron radiation field or persistent erection.The present invention utilizes BF
3The quantity of electric charge of proportional counter output loses the characteristic that is directly proportional with charged particle in the pipe self-energy, the period of the day from 11 p.m. to 1 a.m in measuring more than two simultaneously, output pulse amplitude strengthens, after putting, the equivalent instrument master connects a plurality of discriminators, correspond respectively to 1, the threshold value of 2 and 3 neutron stacks, microprocessor is sent in the output pulse of different discriminators respectively, probability calculation according to the stack power spectrum goes out real dose equivalent, makes counting loss obtain revising.The present invention is simple in structure, and deal with data is easy, can make counting loss can effectively obtain revising.
Description
Technical field
The present invention is directed to when the instrument neutron dose equivalent instrument of measuring the neutron irradiation extent of injury is measured in pulsed neutron field or strong neutron field and exist a kind of effective solution that can eliminate the counting loss of measurement that serious counting loss proposes, belong to the sub-radiation field applied technical field of pulsed neutron radiation field or persistent erection.
Background technology
Since the sixties in last century, scientist's neutron dose equivalent instrument that begins one's study, to the eighties be mature technology, many companies of many countries all have ripe product to sell.The Neutron Monitor NM2B type produced of the NUCLEAR ENTERPRISES LTD. of Britain for example.ANM type zone neutron detector, the wide moderate energy neutron monitor of WENM that Beijing high-energy radiation guard technology Ltd produces.They all are a kind of rem instrument of the Andersson-Brauns of being called type.Its sonde configuration such as Fig. 1, Fig. 1 is the sonde configuration figure of the neutron dose equivalent instrument of Andersson-Brauns type, wherein 1 is the slowing down layer of being done by polythene material, be used for slowing down fast neutron and intermediate neutron, the 2nd, absorption layer, be to be used for absorbing unnecessary thermal neutron, the 3rd, internal layer slowing down layer is used for slowing down to pass the fast neutron of absorption layer and slow neutron.Make neutron become thermal neutron.(detector of back is only to the thermal neutron sensitivity) the 4th, BF
3The neutron proportional counter tube is used for writing down (thermal neutron and boron 10 generation nuclear reactions through the thermal neutron of slowing down
10B+n →
4α+
7Li+2.31MeV).This structure can make the neutron dose equivalent instrument satisfy the neutron energy response of International Commission on Radiological Protection (ICRP) regulation, and Fig. 2 is the single neutron fluence of monoenergetic announced of ICRU57 (1998) to the conversion coefficient of dose equivalent on every side.The block scheme of its instrument is seen Fig. 3.Fig. 3 is the instrument block scheme of the neutron dose equivalent instrument of Andersson-Brauns type.By slowing down layer (1), boron absorption layer (2), internal layer slowing down layer (3), and BF
3The neutron dose equivalent instrument probe that direct ratio neutron counter tube (4) is formed, the neutron that satisfies the ICRP of International Commission on Radiological Protection regulation can ring characteristic.BF
3The charge number that the neutron proportional counter tube produces is proportional to the energy loss of charged particle in counter tube, be transformed into voltage signal by preposition electric charge (voltage) sense amplifier, amplify by main amplifier again and the adjustment time constant, remove noise and gamma-rays background by discriminator.Discriminator output pulse is sent into rolling counters forward through being shaped.So various technical indicators of neutron dose equivalent instrument have satisfied the energy response requirement of International Commission on Radiological Protection basically.
But because BF
3Neutron proportional counter tube and electronics circuit subsequently all have certain dead time.The dead time of for example above-mentioned Neutron Monitor NM2B is 4.5 μ s, just have simultaneously within the 4.5 μ s 2 above neutrons and
10B has carried out nuclear reaction, also can only be as a pulse recording.Have article report this neutron dosimeter in burst pulse neutron irradiation field, leak the meter seriously reach 30%, sometimes more up to 75%.In order to solve the problem of counting loss, people have thought many improving one's methods:
Method 1: in the slow body that satisfies the rem characteristic, place the GM counter tube of contracted payment, in slow body, place the quencher time pipe of contracted payment and be called the Ag-SQS Neutron Detector in order to improve counting rate.Perhaps place indium in slow body, the β ray of activation products is measured in the activation back.Above way is called activation method.The advantage of this way is can not cause counting loss or seldom cause counting loss.But the radioactivity of activation products has the half life period of oneself, for example
Emit the β ray, the half life period is 24.4sec, and
Half life period is 2.42min.Very detector still has counting after the burst pulse neutron.Because residual activity is arranged, when being repeatedly used, dose value is not easy to calculate, and reaction neutron dose equivalent is not directly perceived, yet bad correction.
Method 2: use the LiF thermoluminescent detector (TLD), this way can not on-line measurement.
Summary of the invention
Goal of the invention: the counting loss problem when improving that dose equivalent meter uses around the neutron in pulsed neutron radiation field and the sub-radiation field of persistent erection, we have proposed a method, and this method is to have utilized BF
3The direct ratio performance of neutron proportional counter tube, when two neutrons simultaneously at BF
3When in the counter tube nuclear reaction taking place, the output of the proportional counter tube significantly probability of pulse can strengthen, and measuring 3 middle period of the day from 11 p.m. to 1 a.m output pulse amplitudes simultaneously can be bigger.Fig. 4 is the circuit block diagram of follow-on neutron dose equivalent instrument.Here select for use a plurality of discriminators to correspond respectively to the amplitude of single neutron, two neutrons and three neutron superimposed pulse, make the discriminator (wide window single channel pulse height analyzer) of pulse by different threshold values of different amplitudes, different single track output, the input single-chip microcomputer, note down different neutron pulse numbers, be converted at last neutron dose equivalents (Sv/h) sievert (Sv) or sievert (Sv)/hour.As long as 2 or several discrimination threshold or wide window single-channel analyzer (several single-channel analyzer) are set,, just can analytical calculation there be several neutrons that nuclear reaction takes place simultaneously by following method deal with data.
A kind of method of eliminating neutron dose equivalent meter counting loss on every side, this method may further comprise the steps:
(1) with light exposure detector (can not produce the fluence of neutron pulse stack), measures BF with multichannel pulse scope-analyzer
3The power spectrum of proportional counter tube.As Fig. 5 is a typical B F
3The power spectrum of counter tube.Because most of nuclear reaction takes place, and has same energy loss to produce ionization in counter tube, form peak value in the middle of counter tube.Part nuclear reaction occurs near the tube wall, and portion of energy is lost in tube wall, forms the hangover of low energy limit.
(2) two power spectrums that the neutron stack does not take place are added up synthetic, synthesize two pure BF that the nuclear reaction incident takes place simultaneously
3The stack power spectrum of counter tube, as Fig. 6, Fig. 6 is the power spectrum of two superimposed pulses calculating of statistical stacking.This is not contain the not power spectrum of superimposed pulse because can not obtain having only stack with the method for experiment.
(3) carrying out same syntheticly with the power spectrum of 2 superimposed pulses again with single pulse power spectrum, produce 3 power spectrums that neutron is recorded simultaneously in counter tube, is the power spectrum of three superimposed pulses calculating of statistical stacking as Fig. 7.
Carry out the power spectrum that spectrum stripping also can obtain pure superimposed pulses with power spectrum that contains superimposed pulse and individual pulse power spectrum, but accurate inadequately, should not adopt.
The concrete steps of synthetic two the superimposed pulses power spectrums of statistics are as follows:
With transverse axis five equilibrium (pressing energy MeV or pulse height V), we press the energy five equilibrium, the 0.1MeV portion earlier
Because 2 tested neutrons are uncorrelated, each neutron all may produce the pulse of any amplitude (energy), the probability of each amplitude such as Fig. 5, the superimposed pulses of any amplitude that any amplitude pulses that neutron 2 produces all may produce with neutron 1.
We suppose that threshold value is selected in 1.0MeV, and the pulse below the 1.0MeV is disregarded, and does not also consider during calculating.
1.0MeV～1.1MeV is the 1st road
1.1MeV～1.2MeV is the 2nd road
……
2.9MeV～3.0MeV is the 20th road
Synthetic back 2.0MeV～2.1MeV is first road, and 2.1MeV～2.2MeV is second road ..., 5.9MeV～6.0MeV is the 40th road.
Each road probability of neutron 1
1P
1,
1P
2,
1P
3...
1P
20
Each road probability of neutron 2
2P
1,
2P
2,
2P
3...
2P
20
Each road probability P after synthetic
1, P
2, P
3... P
40
2.0P
1＝
1P
1·
2P
1
2.1P
2＝
1P
1·
2P
2+
2P
1·
1P
2
2.2P
3＝
1P
1·
2P
3+
1P
2·
2P
2+
1P
3·
2P
1
2.3P
4＝
1P
1·
2P
4+
1P
2·
2P
3+
1P
3·
2P
2+
1P
4·
2P
1
……
The j road is
To two typical single pulse energy spectrograms 5, synthesize the BF that obtains two superimposed pulses of Fig. 6 with this way
3The output pulse power spectrum of neutron proportional counter tube.
The counting that each wide window single track output pulse should be noted down is definite according to the scale-up factor C of power spectrum area statistics.Scale-up factor C is the small-pulse effect by superimposed pulse, the probability (III district, I district area SI or SIII in the power spectrum) of the part that the single track of low one or 2 threshold value of quilt has been counted is tried to achieve with the ratio of this single-channel count probability (IV district, II district area SII or SIV in the power spectrum) partly.In power spectrum shown in Figure 6, the I district is the zone of energy below 3.0MeV, and the II district is the zone of energy between 3.0MeV～5.3MeV; In power spectrum shown in Figure 7, the III district is the zone of energy between 3.0MeV～5.3MeV, and the IV district is the zone of energy more than 5.3MeV.Each output pulsimeter (C of each output pulsimeter 1, the second single track of first single track
2=2+f
2=2+S
I/ S
II), each output pulsimeter (C of the 3rd single track
3=3+f
3=3+S
III/ S
IV).
Threshold value setting of the present invention is to be determined by the pulse power spectrum of detector output and peak value thereof, be characterized in by the power spectrum of two single neutron pulses carry out probability statistics obtain two neutron pulses stacks power spectrum, carry out probability statistics by the power spectrum of two neutron pulses stack De Neng Spectrum and single neutron pulse and obtain the power spectrum of three neutron pulses stacks and obtain the more power spectrum of multiphonon superimposed pulses with this probabilistic statistical method.
Fig. 6 is the power spectrum of two superimposed pulses calculating of statistical stacking.The corresponding 1.0MeV energy of threshold under first single track, the corresponding 3.0MeV energy of upper-level threshold, first one-channel record mainly is the neutron pulse of not having stack so, wherein also comprised the neutron pulse of two superimposed pulses below some 3.0MeV, also be used as a middle subrecord, in fact the pulse in I district is that two neutrons nuclear reaction takes place simultaneously are formed by stacking, and the pulse in Fig. 6 I district has been missed like this.Threshold is located at 3MeV under second single track, upper-level threshold 5.3MeV, and what this single track was measured is the pulse of the stack in II district, two pulses of each output pulse recording.The superimposed pulse ratio in the I district of error of omission can be come out f
2=S
1/ S
IISo the output pulse to each the 2nd single track should be remembered C
2=2+f
2=2+S
I/ S
II, rather than 2.
Same 3 superimposed pulses (see figure 7)s except the output pulse of the 3rd single track of record 5.3Mev～8.0Mev energy, will consider that also 3 following superimposed pulses of 5.3Mev form pulse.3.0Mev the probability of 3 following superimposed pulses very I to ignore.Like this, should remember C to the output pulse of each the 3rd single track
3=3+f
3=3+S
III/ S
IVRather than 3.
The present invention utilizes BF
3The quantity of electric charge of proportional counter output loses the characteristic that is directly proportional with charged particle in the pipe self-energy, the period of the day from 11 p.m. to 1 a.m in measuring more than two simultaneously, output pulse amplitude strengthens, and connects a plurality of discriminators after main putting, and corresponds respectively to 1, the threshold value of 2 and 3 neutron stacks, microprocessor is sent in the output pulse of different discriminators respectively, goes out real dose equivalent according to the probability calculation of stack power spectrum, and the present invention is simple in structure, deal with data is easy, can make counting loss can effectively obtain revising.
Description of drawings
Fig. 1 is the sonde configuration figure of the neutron dose equivalent instrument of Andersson-Brauns type.
Fig. 2 is the single neutron fluence of monoenergetic announced of ICRU57 (1998) to the conversion coefficient of dose equivalent on every side.
Fig. 3 is the instrument block scheme of the neutron dose equivalent instrument of Andersson-Brauns type.
Fig. 4 is the circuit block diagram of follow-on neutron dose equivalent instrument.
Fig. 5 is a typical B F
3The energy spectrogram of counter tube.
Fig. 6 is the power spectrum of two superimposed pulses calculating of statistical stacking.
Fig. 7 is the power spectrum of three superimposed pulses calculating of statistical stacking.
Embodiment
With 1 Curie's americium-beryllium neutron source neutron irradiation dose equivalent instrument probe, behind preposition charge amplifier, connect main amplifier, potential pulse input multichannel analyzer after the amplification is adjusted enlargement factor and infinitesimal analysis time constant, and the peak that makes the 2.31Mev energy is approximately to strain 2.3V.Record BF
3The power spectrum of neutron counter tube such as Fig. 5.Because counting rate is lower, this power spectrum does not have superimposed pulse.According to formula
Calculate the power spectrum of two superimposed pulses of Fig. 6 and the power spectrum of three superimposed pulses of Fig. 7.
Integration is obtained S
I=0.0222
S
II＝0.9773
S
III＝0.0968
S
IV＝0.9045
Calculate f
2=S
I/ S
II=0.0227
f
3＝S
III/S
IV＝0.1070
C
2＝2+f
2＝2+S
I/S
II＝2.0227
C
3＝3+f
3＝3+S
III/S
IV＝3.1070
Threshold 1V under the 1st single track, upper-level threshold 3V.Threshold 3V upper-level threshold 5.3V under the 2nd single track.Threshold 5.3V upper-level threshold 8V under the 3rd single track.
To the output pulsimeter 1 of each the 1st single track, to the output pulsimeter 2.0227 of each the 2nd single track, to the output pulsimeter 3.1070 of each the 3rd single track
So just the superimposed pulse below 3 is not all write down or not can be leaked meter.
Claims (2)
1, a kind of method of eliminating neutron dose equivalent meter counting loss on every side is provided with a plurality of discriminators behind the main amplifier of described equivalent instrument, it is characterized in that this method may further comprise the steps:
1), measures the BF of described equivalent instrument by discriminator with the probe of the described equivalent instrument of light exposure
3The power spectrum of output pulse when the neutron proportional counter tube writes down single neutron is hereinafter to be referred as single neutron spectrum;
2) two single neutron spectrums are added up synthetic, synthesize when two neutrons are write down by described counter tube simultaneously and export the stack power spectrum of pulse, hereinafter to be referred as dineutron stack power spectrum;
Described statistics is synthetic to be may further comprise the steps:
(1) presses energy MeV with the transverse axis five equilibrium, the 0.1MeV portion earlier;
(2) we suppose, threshold value is selected in 1.0MeV, and the pulse below the 1.0MeV is disregarded, and does not also consider during calculating; For single neutron spectrum,
1.0MeV～1.1MeV is the 1st road,
1.1MeV～1.2MeV is the 2nd road,
……，
2.9MeV～3.0MeV is the 20th road;
Dineutron stack power spectrum after synthetic,
2.0MeV～2.1MeV is first road,
2.1MeV～2.2MeV is second road,
……，
5.9MeV～6.0MeV is the 40 road;
(3) establishing the probability that neutron 1 is recorded in each road is
1P
1,
1P
2,
1P
3...
1P
20,
The probability that neutron 2 is recorded in each road is
2P
1,
2P
2,
2P
3...
2P
20,
The probability that synthetic back is recorded in each road is P
1, P
2, P
3... P
40
Because 2 tested neutrons are uncorrelated, each neutron all may produce any energy pulses, so the probability that synthetic back is recorded in each road is
The first road P
1=
1P
1 2P
1,
The second road P
2=
1P
1 2P
2+
2P
1 1P
2,
The 3rd road P
3=
1P
1 2P
3+
1P
2 2P
2+
1P
3 2P
1,
The 4th road P
4=
1P
1 2P
4+
1P
2 2P
3+
1P
3 2P
2+
1P
4 2P
1,
……
The j road
Like this, two just synthetic dineutron stack power spectrums that obtain of single neutron spectrum;
3) carry out same statistics with dineutron stack power spectrum again with single neutron spectrum and synthesize, produce when 3 neutrons are write down by described counter tube simultaneously and export the stack power spectrum of pulse, hereinafter to be referred as three neutrons stack power spectrum;
4) can obtain each regional area S by spectral integral to dineutron stack power spectrum and the stack of three neutrons respectively
I, S
II, S
III, S
IV, S wherein
IBe the region area of energy below 3.0MeV in the dineutron stack power spectrum, S
IIBe the region area of energy between 3.0MeV～5.3MeV in the dineutron stack power spectrum; S
IIIBe the zone of energy between 3.0MeV～5.3MeV in the three neutrons stack power spectrum, S
IVBe the zone of energy more than 5.3MeV in the three neutrons stack power spectrum;
5) following single track is set and carries out following counting to avoid the counting loss of 3 superimposed pulses below the neutron:
Threshold 1.0MeV, upper-level threshold 3.0MeV under the 1st single track, the neutron number of each output pulse representative of record is 1;
Threshold 3.0MeV, upper-level threshold 5.3MeV under the 2nd single track, the pulse of record is the pulse that the stack of 2 neutrons forms, the counting loss of generation is f
2=S
I/ S
II, promptly the neutron number of each output pulse representative of the 2nd single track is C
2=2+f
2=2+S
I/ S
II
Threshold 5.3MeV, upper-level threshold 8.0MeV under the 3rd single track, the pulse of record is the pulse that the stack of 3 neutrons forms, the counting loss of generation is f
3=S
III/ S
IV, promptly the neutron number of each output pulse representative of the 3rd single track is C
3=3+f
3=3+S
III/ S
IV
2, a kind of method of eliminating neutron dose equivalent meter counting loss on every side according to claim 1 is characterized in that described discriminator is a multichannel pulse scope-analyzer.
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| CN101666227B (en) * | 2008-09-03 | 2013-02-20 | 中国石油天然气集团公司 | Method for acquiring natural gamma spectra |
| CN102928866B (en) * | 2011-08-09 | 2015-05-20 | 中国辐射防护研究院 | Method for measuring spectrum and accumulated dose of neutrons by utilizing passive detector |
| CN102799792B (en) * | 2012-08-17 | 2015-06-17 | 中国原子能科学研究院 | Dead time correction method of reactor reactivity measured value |
| CN104678423B (en) * | 2015-03-10 | 2017-05-31 | 四川中测辐射科技有限公司 | The measuring method of dose equivalent under the conditions of binary channels number system and high dose |
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| CN106990428B (en) * | 2017-05-03 | 2019-05-03 | 中国核动力研究设计院 | The method and its realization device of uranium content in a kind of neutron measurement uranium-bearing liquid |
| CN107340533B (en) * | 2017-07-07 | 2019-05-07 | 西北核技术研究所 | The proportional detector output amplitude compensation method of 3He Central spectrometer and device |
| CN113359178B (en) * | 2021-03-29 | 2023-05-16 | 山西中辐核仪器有限责任公司 | Radiometer based on self-adaptive dead time compensation |
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