CN108445529A - Active neutron personnel dosimeter and its measurement method based on three layers of silicon detector - Google Patents
Active neutron personnel dosimeter and its measurement method based on three layers of silicon detector Download PDFInfo
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Abstract
The present invention relates to a kind of active neutron personnel dosimeters and its measurement method based on three layers of silicon detector, the personnel dosimeter includes main detector and its outer layer transformant component, nuclear electronics system, main detector and its outer layer transformant component include three passivation injection plane silicon detectors, be followed successively by Open detectors, Fast detectors, Albedo detectors from top to bottom, be equipped in front of the Open detectors polyethylene layer and6LiF coating is equipped with polyethylene layer in front of Fast detectors, be equipped in front of Albedo detectors Boron-containing-PE layer, polyethylene layer and6LiF coating；Nuclear electronics system provides high pressure for each detector, and obtains detectable signal and carry out multi-channel analysis.The present invention provides two kinds of measurement patterns, neutron fluence and personal dose equivalent information can be provided in direct-reading pattern in real time, neutron field power spectrum can more accurately be provided by solving in spectral model.Energy measurement range of the present invention is wide, and has energy resolution, can be used in n γ mixing fields.
Description
Technical field
The present invention relates to neutron personnel dosimeter technologies, and in particular to a kind of active neutron based on three layers of silicon detector
Personnel dosimeter and its measurement method.
Background technology
Current more common neutron personal dose is calculated as CR-39 solid plastic track detectors.This plastic track is visited
Device is surveyed after neutron exposure, the atoms such as C, H and O therein and neutron collide and generate recoil nucleus, when recoil nucleus energy is enough
Damage latent mark can be generated when big in the material.The methods of chemical etching or chemical etching then are reused, in detection equipment
The track for being easy to observation is etched in material, and is observed under the microscope through row.This solid trace type personal dose is in respect of volume
Small, the advantages that not needing electronics equipment when measuring.But it is insufficient also fairly obvious：1. measurement lower limit is higher, about 100keV,
This is because determined by this this basic principle of detector measurement recoil nucleus and the property of material itself, so if
When measuring wide range or the softer neutron field of power spectrum using this personnel dosimeter, the dosage of the neutron field can be underestimated；2. this individual
Dosimeter can only measure the number of neutron, and can not learn the energy of neutron, if its field of employment and calibration neutron source used
Power spectrum differ greatly, then its reading is also inevitable higher or relatively low；3. this personal dose is calculated as passive type neutron personal dose
Meter then is read after needing staff to wear a period of time, can not real-time display dosage, so if being limited more than dosage
Value can not also alarm, and be only used for the routine monitoring under non-accident condition and dose evaluation；4. pair plastic track detector carries out
When reading, need, using instruments such as microscopes, to count the track number in detector, take time and effort.
Bibliographic reference about CR-39 neutron personnel dosimeters is as follows：
Cao Lei, Deng Jun, Zhang Guiying, wait .CR39 neutron personnel dosimeter performance tests study radiation protection [J], 2012,
32(3):103-107.
Feng Yushui, Li Junwen, Lin Zhikai wait .CR-39 plastics recoil track Personal Neutron Dosimeter nuclear technology [J],
1988,11(9):44-46.
Since the 1960s, semiconductor detector starts to be used for neutron detection relatively broadly.Utilize semiconductor
Detector makes seed personal dose's timing, additional layer neutron conversion body thin film or coating usually outside detector, in
The sub nuclear reaction with certain specific species generates secondary charged particle, and then learns the relevant information of neutron.These nuclear reactions master
Have6Li (n, α) T,10B(n,α)7Li, He (n, p) T,155,157Gd(n,γ)156,158Gd etc..In more typical semi-conductor type
Sub- personal dose is calculated as the DOS-2002 of German PTB productions.This personnel dosimeter is based primarily upon single layer silicon detector, and is visiting
Survey device outer layer equipped with polyethylene and6LiF deduces personal agent as fast neutron and thermal neutron transformant by recording neutron number
Measure equivalent.DOS-2002 has certain neutron and gamma-rays resolution capability.The shortcoming of DOS-2002 essentially consists in：It can not
Differentiate neutron energy.The essence of this personnel dosimeter is record thermal neutron and fast neutron number, and its personal dose equivalent
Response is larger with energy variation, and minimum value may differ by several orders of magnitude with maximum value.Therefore, record count obviously can not be compared with
Accurately provide personal dose equivalent.
Bibliographic reference about semiconductor neutron personnel dosimeter is as follows：
Luszik-Bhadra.Electronic personal doesmeters:The solution to problems
of individual monitoring in mixed neutron fields.Radiation Protection
Dosimetry[J],2004,110(1-4):747-752.
M.Luszuk-Bhadra,W.Wendt and M.Weierganz.The Electronic Neutron/Photon
Doesmeter PTB DOC-2002.Radiation Protection Dosimetry[J],2004,110(1-4):291-
295.
Invention content
It is wide it is an object of the invention in view of the drawbacks of the prior art, provide a kind of energy measurement range, and there is energy
The active neutron personnel dosimeter of resolution capability can use in n- γ mixing fields, and provide neutron individual's agent simultaneously
Two kinds of measurement methods of gauge.
Technical scheme is as follows：A kind of active neutron personnel dosimeter based on three layers of silicon detector, including
Main detector and its outer layer transformant component, nuclear electronics system, the main detector and its outer layer transformant component include
Three passivation injection plane silicon detectors, are followed successively by Open detectors, Fast detectors, Albedo detectors, institute from top to bottom
Be equipped in front of the Open detectors stated polyethylene layer and6LiF coating, Fast detectors front are equipped with polyethylene layer, and Albedo is visited
Survey device in front of be equipped with Boron-containing-PE layer, polyethylene layer and6LiF coating；Nuclear electronics system provides high pressure for each detector,
And it obtains detectable signal and carries out multi-channel analysis.
Further, the active neutron personnel dosimeter as described above based on three layers of silicon detector, wherein the core
Electronic system includes preamplifier, main amplifier, low-tension supply, high voltage power supply and multichannel analyzer, three passivation injections
The detectable signal of plane silicon detector is sent into multichannel analyzer through preamplifier, main amplifier.
Further, the active neutron personnel dosimeter as described above based on three layers of silicon detector, wherein described three
A passivation injection plane silicon detector is encapsulated in aluminum shell.
A kind of measurement method of above-mentioned active neutron personnel dosimeter, using direct-reading pattern, this method is first by neutron
Three parts can be divided into：20meV~1keV slow neutron energy area, 1keV~1MeV intermediate neutron energy area, 1MeV~20MeV fast neutrons
Energy area passes through the fluence response that monoenergetic neutrons fluence Calibration Experiment obtains each detector of personnel dosimeter under different-energy, meter
The mean fluence response for calculating different energy areas, then utilizes fluence-personal dose equivalent conversion coefficient to obtain personal dose equivalent
Response；The counting of Fast detectors divided by its response are the personal dose equivalent of fast neutron contribution, Open detectors and Fast
The personal dose equivalent that the difference divided by Open detectors of the counting of detector contribute the response of low energy neutron for low energy neutron,
Difference divided by the intermediate neutron response of the counting of Albedo detectors and Open detectors are the personal dose of intermediate neutron contribution
Equivalent, the sum of three are total neutron personal dose equivalent.
The measurement method of another above-mentioned active neutron personnel dosimeter, using solution spectral model, this method utilizes recoil
There are following relationships with neutron energy with angle for the energy of proton：
Ep=Encos2φ
Wherein, EpFor recoil proton energy, EnFor incident neutron energy, φ is recoil angle,
The pulse amplitude spectrum deconvolution that Fast detectors are measured is neutron energy spectrum.
Beneficial effects of the present invention are as follows：1) the neutron energy measurement range covering radiation of personnel dosimeter of the invention is anti-
Protect common neutron field energy range, thermal energy~20MeV；2) present invention has certain energy resolution, can provide respectively low
The personal dose equivalent of moderate energy neutron, intermediate neutron and fast neutron；3) detection limit of the invention is relatively low, is 9.86 × 10-1μSv；
4) present invention has gamma-rays discrimination capabilities, can be used in n- γ mixing fields；5) the present invention provides two kinds of measurement patterns,
Neutron fluence and personal dose equivalent information can be provided in direct-reading pattern in real time, is solved in capable of more accurately being provided in spectral model
Subfield power spectrum.
Description of the drawings
Fig. 1 is the structural schematic diagram of main detector of the present invention and its outer layer transformant component；
Fig. 2 is the structural schematic diagram of personnel dosimeter nuclear electronics system；
Fig. 3 is personal dose equivalent response results schematic diagram；
Fig. 4 is personnel dosimeter 7MeV photo response schematic diagram of calculation result；
Fig. 5 is solution spectral model neutron energy spectrum result schematic diagram.
Specific implementation mode
The present invention is described in detail below with reference to the accompanying drawings and embodiments.
The present invention provides a kind of neutron personnel dosimeters based on three layers of silicon detector, include mainly with lower part：It is main
Detector and its outer layer transformant component, nuclear electronics system.Invention also provides two kinds of the neutron personnel dosimeter
Measurement pattern, including direct-read method and Analysis software.
Neutron personnel dosimeter detector body diameter 20mm, high 20mm are encapsulated in the aluminum of 20mm × 40mm × 60mm
In shell.Include mainly three passivation injection plane silicon detectors in component, polyethylene, the poly- second of boracic are housed around silicon detector
Alkene,6The materials such as LiF form interlayer structure as slow body, absorber and transformant.Silicon detector is entitled successively from top to bottom
Open detectors, Fast detectors and Albedo detectors.
As shown in Figure 1,2 front of Fast detectors is only equipped with polyethylene layer 4, which can only record fast neutron and proton
The recoil proton that elastic scattering generates occurs.Only the neutron to energy more than 1MeV generates response to Fast detectors 2.
Open detectors 1 and 3 front of Albedo detectors are not only equipped with polyethylene layer 4, also6LiF coating 5, therefore it
Be able to record low energy neutron with6The α particles and tritium that Li reactions generate；The recoil proton of fast neutron generation can be also recorded simultaneously.
In addition to above-mentioned peripheral components, apart from human body or body when being also equipped with Boron-containing-PE layer 6 in front of Albedo detectors 3, and working
Film closer to, therefore its low energy neutron response be slightly below Open detectors, and intermediate neutron response be slightly above Open detectors.
As specific embodiment, detector is the MSD011 type PIPS detectors of MICRON companies of Britain production, spirit
The quick a diameter of 10mm in area, is maximally depleted 300 μm of layer thickness.In actual use, detector high pressure is set to 3.5V, it is sensitive at this time
Area's thickness is about 100 μm.Under this sensitive thickness, silicon detector can deposit completely neutron with6The α particles that Li reactions generate
With tritium particle, for both particles, this detector is full appositional pattern detector.But range of the recoil proton in silicon
It is longer, thus can only completely sedimentary energy be 3.2MeV recoil proton.When recoil proton energy is higher, this detector is
Penetrating type detector can only judge particle energy by the energy deposition spectra shape difference that different-energy recoil proton generates.
Open detectors respond highest to thermal neutron, and Albedo detectors respond highest to intermediate neutron, and Fast detectors are only to fast
Neutron has response.
In External reforming body component, polyethylene and Boron-containing-PE are thickness 2mm, the disk of diameter 20mm.Boron-containing-PE
For B4C。6LiF plated films use ion sputtering film coating technology, and the cation which is generated using gas discharge is under electric field action
High-speed motion bombards target material, so that the atom in target material is escaped and is deposited on polyethylene surface, is formed6LiF plated films.6LiF
4 μm of coating film thickness, mass thickness 1mg/cm2.Since aluminium is very small to the scattering section of neutron, and consider intensity and cost,
Therefore shell uses aluminum alloy material, thickness 1mm.
As shown in Fig. 2, nuclear electronics system includes preamplifier, main amplifier, low-tension supply, high voltage power supply and multiple tracks
Analyzer and its software.The system is mainly that detector provides high pressure, and high voltage power supply output voltage is 3.5V, keeps system normal
Work.Pulse signal can be amplified, signal-to-noise ratio is improved, and carry out analog-to-digital conversion and multi-channel analysis etc..
The personnel dosimeter of the present invention shares both of which：Direct-reading pattern and solution spectral model.Direct-reading pattern can give in real time
The neutron fluence in the areas Chu Sangeneng or personal dose equivalent are a kind of rather roughs but quick method；Spectral model is solved to utilize
Analysis software, the pulse amplitude spectrum deconvolution that Fast detectors are measured are neutron energy spectrum, and the model results are more accurate, but nothing
Method calculates in real time.
1) direct-reading pattern
The basis of direct-reading pattern is response difference of three detectors to different-energy neutron.
Above-mentioned neutron energy range is divided into three parts by the neutron personnel dosimeter：20meV~1keV slow neutron energy area
(thermal)；1keV~1MeV intermediate neutron energy area (interval)；1MeV~20MeV fast-neutron ranges (fast).Therefore,
Neutron fluence φ that all can be in area is the sum of three's fluence：
φ=φthermal+φinterval+φfast (1)
For each detector, tale M is the sum of three areas Ge Neng neutron countings：
M=Mthermal+Minterval+Mfast (2)
In addition, according to the definition that fluence responds, explorer count is equal to unit-energy interval neutron fluence φ againE(E) with
Integral of corresponding energy bite fluence response R (E) products in all-round area：
M=∫ φE(E)R(E)dE (3)
Discretization is carried out to formula (3), counting and corresponding mean fluence that explorer count is three areas Ge Neng can be approximately considered
Respond the sum of products：
M=φthermalRthermal+φintervalRinterval+φfastRfast (4)
Since the transformant in front of three detectors is different, for the neutron of different-energy, their response
Slightly difference.Each detector application equation (4) can be obtained：
MO=φthermalRO,thermal+φintervalRO,interval+φfastRO,fast
MF=φfastRF,fast
MA=φthermalRA,thermal+φintervalRA,interval+φfastRA,fast (5)
In formula, Rthermal、RintervalAnd RfastIndicate that detector puts down low energy neutron, intermediate neutron and fast neutron respectively
Equal fluence response can respond Calibration Experiment by Monte Carlo calculations or single energy fluence and obtain.In view of active individual
Dosimeter needs this feature of the parameters such as instant playback personal dose equivalent, and the calculating of equation (5) is excessively complicated, it is difficult to small-sized
Change, is not suitable for personnel dosimeter.Therefore, equation (5) can be reduced in conjunction with the features of response of three detectors：
MO=RO,thermal×φthermal×C1
MF=RF,fast×φfast×C2
MA=RA,interval×φinterval×C3 (6)
In equation (6), C indicates the calibration factor of each detector.Utilize the neutron fluence-provided in No. ICRP74 report
Fluence can be responded and be converted to personal dose equivalent response by personal dose equivalent conversion coefficient.
According to design and experimental result, calculates each detector and the average personal dose equivalent of different energy areas neutron is rung
It answers.When measurement, the neutron counting of three detectors divided by corresponding personal dose equivalent response and its calibration factor, you can substantially
Obtain neutron fluence or the personal dose equivalent in three areas Ge Neng.
As specific embodiment, personnel dosimeter under different-energy is obtained by monoenergetic neutrons fluence Calibration Experiment first
The fluence of each detector responds.Experiment energy point include 144keV, 250keV, 565keV, 1.2MeV, 2.5MeV, 5MeV with
And 14.8MeV.According to Monte Carlo calculations as a result, selecting 1MeV for gamma-rays threshold value.After deducting corresponding counts, shadow cone method is used
Or extrapolation deducts the background contributions of room scattering.Thus the mean fluence response that different energy areas can be calculated, then utilizes note
Amount-personal dose equivalent conversion coefficient obtains personal dose equivalent response.According to experimental result, it is believed that Fast detectors
It counts divided by it responds personal dose equivalent of as fast neutron contribution；The difference of the counting of Open detectors and Fast detectors is removed
The personal dose equivalent that the response of low energy neutron is contributed as low energy neutron using Open detectors；And Albedo detectors and Open
Difference divided by the intermediate neutron response of the counting of detector are the personal dose equivalent of intermediate neutron contribution.The sum of three is total
Neutron personal dose equivalent.Utilize the counting of formula (7) and three detectors, you can acquire neutron personal dose equivalent.Wherein
Hp(10) each energy region neutron personal dose equivalent is indicated；MFIndicate Fast explorer counts；MAIndicate Albedo explorer counts；
MOIndicate Open explorer counts；Indicate fast-neutron range be averaged personal dose equivalent respond；In expression in energy
Subzone be averaged personal dose equivalent response；Indicate low energy neutron be averaged personal dose equivalent respond.
2) spectral model is solved
Due to before detector Fast be equipped with layer of polyethylene thin slice, when neutron energy be higher than 1MeV when, can with it is therein
Elastic scattering occurs for proton, gets recoil proton.There are following relationships with neutron energy with angle for the energy of recoil proton：
Ep=Encos2φ (8)
Wherein, EpFor recoil proton energy, EnFor incident neutron energy, φ is recoil angle.According to this relationship, it will be able to
Using the method for returning convolution, pass through the anti-energy information for releasing incident neutron of Analysis software.
As specific embodiment, first by testing the method measured compared with theoretical calculation, determine that three silicon are visited
Survey the receptance function of device.Using the Monte Carlos GEANT4 program, calculating detector Open and detector Albedo is in 20meV for simulation
The receptance function of totally 39 energy points, calculating detector Fast are total in 1MeV~15MeV energy ranges in~15MeV energy ranges
30 receptance functions.The response results that the result of theoretical calculation is responded to Calibration Experiment with monoenergetic neutrons are compared, to theory
Result of calculation is modified.Using genetic algorithm carry out multiple tracks spectrum unscrambling calculating, through determination solution space, determine fitness function,
Determine the processes such as genetic operator, it is neutron energy spectrum that the pulse amplitude spectrum measured, which is returned convolution,.
It is as shown in table 1 that spectrum unscrambling calculates design relevant parameter.
1 spectrum unscrambling of table calculates the relevant parameter being related to
Neutron personnel dosimeter provided by the invention using passivation injection plane silicon detector, silicon detector have it is small,
The features such as light weight, high sensitivity.The volume of one detector and its External reforming body is only φ 20mm × 5mm.Personal dose
Meter overall outer dimensions are 20mm × 40mm × 60mm, and quality is only 55g, are suitable for personal daily and wear.
Utilize the quasi monoenergetic neutrons established on China Atomic Energy Science Research Institute's metrology and measurement portion 5SDH-2 tandem accelerators
Reference radiation field has carried out monoenergetic neutrons fluence Calibration Experiment.Experiment energy point include 144keV, 250keV, 565keV,
1.2MeV, 2.5MeV, 5MeV and 14.8MeV, each energy point are tested under two different distances respectively, to deduct room
Scattering background.It is as shown in Figure 3 that personal dose equivalent responds experimental result.Different detector neutron personal dose equivalents are rung in Fig. 3
Thermal energy should be covered with energy variation, energy range to 20MeV, the radiation protection for being suitable for most of places works.
Calibration Experiment and Monte Carlo simulation are responded by monoenergetic neutrons, the personnel dosimeter can also be obtained to different energy
The average personal dose equivalent response of neutron is measured, as shown in table 2.
2. personnel dosimeter difference energy area of table be averaged personal dose equivalent response (s/ μ Sv)
According to the principle formula in table 2 and technical solution, the detection limit of this personnel dosimeter is 9.86 × 10-1μ Sv, far
Less than existing passive type personnel dosimeter detection limit.
This personnel dosimeter influences caused by deducting gamma-rays by way of card domain, can more accurately measure neutron
Caused by personal dose equivalent.
Fig. 4 is to deposit spectrum using the 7MeV photon energies that the Monte Carlos GEANT4 program calculates.It can be seen from the figure that energy
The photon that amount is 7MeV at most deposits the energy of 1MeV in the silicon detector that sensitive volume thickness is 100 μm.Therefore, as long as by light
Sub- threshold value is set as 1MeV, this neutron personnel dosimeter is at best able to deduct the photon of 7MeV.
This personnel dosimeter is positioned over241Test experiments are carried out under Am-Be neutron sources.The result of direct-reading pattern such as 3 institute of table
Show, solving spectral model, the results are shown in Figure 5.
Table 3.241Am-Be neutron source personal dose equivalents experimental result (μ Sv/h)
241Personal dose equivalent conventional true value at Am-Be neutron sources 101cm is (3.24E+02) μ Sv/h, and experiment is opposite
Error is that the conventional true value at 52.6%, 67cm is (3.53E+02) μ Sv/h, and experiment relative error is 52.1%.
In Fig. 5, two kinds of lines are respectively what ISO8529 was provided241Am-Be neutron sources standard spectrum and resolving spectra.From
It can be seen from the figure that, resolving spectra coincide preferable with standard spectrum.The personal dose equivalent that spectrum unscrambling obtains at 101cm is (1.90E+
02) μ Sv/h, conventional true value are (3.53E+02) μ Sv/h, and experiment relative error is 41.5%；The individual that spectrum unscrambling obtains at 67cm
Dose equivalent is (5.51E+02) μ Sv/h, and conventional true value is (7.36E+02) μ Sv/h, and experiment relative error is 25.1%.
Obviously, various changes and modifications can be made to the invention without departing from essence of the invention by those skilled in the art
God and range.If in this way, belonging to the model of the claims in the present invention and its equivalent technology to these modifications and changes of the present invention
Within enclosing, then the present invention is also intended to include these modifications and variations.
Claims (5)
1. a kind of active neutron personnel dosimeter based on three layers of silicon detector, it is characterised in that：Including main detector and its
Outer layer transformant component, nuclear electronics system, the main detector and its outer layer transformant component include that three passivation are injected
Plane silicon detector is followed successively by Open detectors, Fast detectors, Albedo detectors, Open detections from top to bottom
Be equipped in front of device polyethylene layer and6LiF coating, Fast detectors front are equipped with polyethylene layer, are equipped in front of Albedo detectors
Boron-containing-PE layer, polyethylene layer and6LiF coating；Nuclear electronics system provides high pressure for each detector, and obtains detection letter
Number carry out multi-channel analysis.
2. the active neutron personnel dosimeter as described in claim 1 based on three layers of silicon detector, it is characterised in that：It is described
Nuclear electronics system include preamplifier, main amplifier, low-tension supply, high voltage power supply and multichannel analyzer, three passivation
The detectable signal of injection plane silicon detector is sent into multichannel analyzer through preamplifier, main amplifier.
3. the active neutron personnel dosimeter as described in claim 1 based on three layers of silicon detector, it is characterised in that：It is described
Three passivation injection plane silicon detectors be encapsulated in aluminum shell.
4. the active neutron personnel dosimeter based on three layers of silicon detector described in a kind of any one of claim 1-3
Measurement method, it is characterised in that：Using direct-reading pattern, neutron energy range is divided into three parts by this method first：20meV~1keV is slow
Neutron energy range, 1keV~1MeV intermediate neutron energy area, 1MeV~20MeV fast-neutron ranges are real by monoenergetic neutrons fluence scale
The fluence response for obtaining each detector of personnel dosimeter under different-energy is tested, the mean fluence response in different energy areas is calculated,
Then it utilizes fluence-personal dose equivalent conversion coefficient to obtain personal dose equivalent to respond；The counting of Fast detectors divided by its
Response is the personal dose equivalent of fast neutron contribution, difference divided by the Open detection of the counting of Open detectors and Fast detectors
Device is to the personal dose equivalent that the response of low energy neutron is low energy neutron contribution, the counting of Albedo detectors and Open detectors
Difference divided by intermediate neutron response be intermediate neutron contribution personal dose equivalent, the sum of three be total neutron personal dose
Equivalent.
5. the active neutron personnel dosimeter based on three layers of silicon detector described in a kind of any one of claim 1-3
Measurement method, it is characterised in that：Using solution spectral model, this method exists using the energy of recoil proton with angle and neutron energy
Following relationship：
Ep=Encos2φ
Wherein, EpFor recoil proton energy, EnFor incident neutron energy, φ is recoil angle,
The pulse amplitude spectrum deconvolution that Fast detectors are measured is neutron energy spectrum.
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| CN111257922A (en) * | 2020-02-17 | 2020-06-09 | 兰州大学 | BF with wide energy spectrum3Long neutron counter measuring system |
| CN111257922B (en) * | 2020-02-17 | 2023-03-10 | 兰州大学 | BF with wide energy spectrum 3 Long neutron counter measuring system |
| CN112904403A (en) * | 2021-01-22 | 2021-06-04 | 中国科学院合肥物质科学研究院 | Wide-energy-spectrum neutron fluence on-line monitoring system |
| CN113805217A (en) * | 2021-08-05 | 2021-12-17 | 中国原子能科学研究院 | Method and system for determining number of Li-6 atomic nuclei |
| CN115267879A (en) * | 2022-08-01 | 2022-11-01 | 西北核技术研究所 | Measuring device and measuring method for high-resolution pulse fast neutron flux and energy spectrum |
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