Simulations of Si-PIN photodiode based detectors for underground explosives enhanced by ammonium nitrate

Simulations of Si-PIN photodiode based detectors for underground explosives enhanced by ammonium nitrate

Accepted Manuscript Simulations of Si-PIN photodiode based detectors for underground explosives enhanced by ammonium nitrate Mete Yücel, Ahmet Bayrak,...

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Accepted Manuscript Simulations of Si-PIN photodiode based detectors for underground explosives enhanced by ammonium nitrate Mete Yücel, Ahmet Bayrak, Esra Barlas Yücel, Cenap S. Ozben

PII: DOI: Reference:

S0168-9002(17)31180-4 https://doi.org/10.1016/j.nima.2017.10.091 NIMA 60237

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Nuclear Inst. and Methods in Physics Research, A

Received date : 12 July 2017 Revised date : 24 October 2017 Accepted date : 29 October 2017 Please cite this article as: M. Yücel, A. Bayrak, E.B. Yücel, C.S. Ozben, Simulations of Si-PIN photodiode based detectors for underground explosives enhanced by ammonium nitrate, Nuclear Inst. and Methods in Physics Research, A (2017), https://doi.org/10.1016/j.nima.2017.10.091 This is a PDF file of an unedited manuscript that has been accepted for publication. As a service to our customers we are providing this early version of the manuscript. The manuscript will undergo copyediting, typesetting, and review of the resulting proof before it is published in its final form. Please note that during the production process errors may be discovered which could affect the content, and all legal disclaimers that apply to the journal pertain.

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Simulations of Si-PIN Photodiode Based Detectors for Underground Explosives Enhanced by Ammonium Nitrate

4

Mete Y¨ ucel, Ahmet Bayrak, Esra Barlas Y¨ ucel, Cenap S. Ozben∗

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5 6

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˙ Istanbul Technical University, Faculty of Science and Letters, Department of Physics ˙ Engineering, 34469 Maslak Sarıyer, Istanbul Turkey.

Abstract Massive Ammonium Nitrate (NH4 -NO3 ) based explosives buried underground are commonly used in terror attacks. These explosives can be detected using neutron scattering method with some limitations. Simulations are very useful tools for designing a possible detection system for these kind of explosives. Geant4 simulations were used for generating neutrons at 14 MeV energy and tracking them through the scattering off the explosive embedded in soil. Si-PIN photodiodes were used as detector elements in the design for their low costs and simplicity for signal readout electronics. Various neutron-charge particle converters were applied on to the surface of the photodiodes to increase the detection efficiency. Si-PIN photodiodes coated with 6 LiF provided the best result for a certain energy interval. Energy depositions in silicon detector from all secondary particles generated including photons were taken into account to generate a realistic background. Humidity of soil, one of the most important parameter for limiting the detection, was also studied.

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Keywords: Geant4, Explosives, Si-PIN Photodiodes, Neutron Detection,

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Monte Carlo Simulations, Ammonium Nitrate



Email address: [email protected] (Cenap S. Ozben)

Preprint submitted to Elsevier

October 24, 2017

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1. Introduction

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Explosives enhanced by large amount of ammonium nitrate (AN) are com-

12

monly used in terror attacks costing many lives around the globe. This situation

13

creates a demand for an efficient way to detect this kind of explosives. Various

14

groups have been working on methods to develop systems for the detection of

15

explosives [1–3]. However, each method brings its own problems, may require

16

sophisticated equipment and is technically complicated. Further investigations

17

and work are necessary to produce commercially viable explosive detectors [4, 5].

18

Among various methods, neutron based explosive detection benefits from

19

high penetrability of neutrons and their unique interactions with the target

20

nuclei. There are several works focused on the detection of underground explo-

21

sives [6, 7] or explosive hidden in vehicles and compartments [8, 9] based on the

22

methods of neutron scattering. Fast neutron analysis, thermal neutron analysis

23

and prompt gamma analysis are other methods used in this field. However,

24

explosives with small masses in short detection distances are targeted in most

25

of these studies. In contrast, large scale terror attacks have utilized ammonium

26

nitrate enhanced explosives with hundreds of kilograms of weight. Considering

27

this massive ammonium nitrate content, it is worthwhile to re-investigate the

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detection limits of ammonium nitrate enhanced explosives, especially buried

29

underground. A technique based on the analysis of scattered neutrons from

30

ammonium nitrate explosive embedded in soil was used in this study. Neutrons

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from a D-T source and the secondary particles from neutron interactions were

32

tracked till they reach Si-PIN photodiode detectors. Various converter materials

33

applied to the surface of Si-PIN photodiodes to increase the detection efficiency.

34

An energy cut was applied to the detected neutron spectra to obtain the best

35

possible discrimination between soil and the explosive embedded in soil.

36

Neutron detectors used in most of the studies are usually 3 He based detec-

37

tors [10]. However, the limited availability and high cost of 3 He have encouraged

38

researchers to find alternatives. One of the new candidates under consideration

39

are detectors based on silicon PIN photodiodes. Their capability for neutron de-

2

40

tection has been investigated in recent years [11]. Since they have low efficiency

41

for the direct neutron detection, Si-PIN photodiodes are usually used with a

42

converter [12, 13] to generate charged particles which can produce signal in sil-

43

icon substructure. Advantages of Si-PIN photodiodes as detectors are their low

44

cost and expandability to large area to increase detection solid angle. Choice

45

of converter material depends on the neutron energy. Generally, low Z mate-

46

rials like polyethylene, polystyrene are used for fast neutrons [14]. As known,

47

fast neutrons make inelastic collisions and produce protons in polyethylene.

48

For thermal and epithermal neutrons, a wide range of nuclear interactions are

49

available. Studies show that 6 LiF and 10 B are used as convenient converter ma-

50

terials [15]. Neutron capture by

51

produces an alpha particle with 1.44 MeV kinetic energy. Similarly, neutrons

52

are captured based on 6 Li(n,α)3 H primary reaction and an alpha particle with

53

2.05 MeV and a triton with 2.73 MeV kinetic energies are generated. If

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6

10

B according to

10

B(n,α)7 Li nuclear reaction

10

B or

LiF layers are applied on the photodiode surface, secondary particles generated

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based on these reactions lose all their energies due to the ionization in silicon,

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resulting in larger detection efficiency. Since 6 Li produces energetically favored

57

back to back particles and thermal neutron cross section of 6 Li(n,α)3 H reaction

58

is much larger compared to the one of

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to be used. Multiple 6 LiF coated silicon photodiodes can be used for extending

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the surface of the detection and this segmented structure can detect neutrons

61

with higher spatial resolution. The signal process and readout electronics are

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relatively simple for photodiodes.

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2. Monte Carlo Simulations

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B(n,α)7 Li, 6 LiF coating was decided

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Geant4 (Geometry and Tracking) is a toolkit of simulations for interactions

65

of particles with matter [16]. Geant4 describes the behavior of low energy neu-

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trons with four physics processes; elastic scattering, inelastic scattering, neutron

67

capture and neutron induced fission. G4NeutronHP is the model used and this

68

model is based on the ENDF/B VI, ENDF/B VII and JENDL evaluated neutron

3

69

libraries provided by the Cross Section Evaluation Working Group (CSEWG)

70

and the Nuclear Data Evaluation Centre of Japan Atomic Energy Agency. In-

71

teractions of low energy (<20 MeV) alpha particles and TENDL cross section

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library have been added to Geant4 recently [17].

73

We used Geant4 version 10.1 simulation package in this work. In simulations,

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14 MeV neutrons (based on D-T interaction) were generated isotropically (4π

75

geometry). Neutrons traveled directly or through a polyethylene moderator to

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the explosive embedded soil. 500 kg ammonium nitrate was used in a geometry

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of a cube with 67 cm side length. Scattered neutrons from ammonium nitrate

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buried in various depths in soil were tracked. The simulations were performed

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for 6 LiF and polyethylene applied to the surface of a relatively large (50 cm X

80

50 cm) Si-PIN photodiode. Si-PIN detector was positioned 10 cm above the

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soil and a 10 cm thick lead shielding takes place between the source and the

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detector. Energy depositions of scattered neutrons, produced gamma rays and

83

particles generated in the converter material were recorded in each simulation.

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Soil composition used in the simulations was taken from the Table 1 of [18].

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The simulation geometry is given in Figure 1. Pb Shield D-T Neutron Source Si-PIN Detector

Explosive enhanced by NH4NO3

Soil

10 cm

y

10 cm x

Figure 1: X-Y profile of the simulation geometry consist of the D-T neutron source, lead shielding, Si-PIN detector, soil and the explosive.

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Detector position relative to the neutron source and target position is impor-

87

tant for the detection efficiency. In order to maximize the detection of scattered

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neutrons, the area of a triangle connecting the centers of the source, the tar4

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get and the detector should be minimized briefly. Since there is no control on

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the depth of the buried explosive, the practical way to maximize the detected

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events is to position the detector as close as possible to the neutron source. The

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drawback is the background due to the source itself. Determining spatial distribution of scattered neutrons is important for de-

94

signing the detector. For this reason, the spatial distributions of scattered neu-

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trons from the explosive buried in soil (10 cm depth) were determined for various

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energy intervals. In this study, Geant4 simulations were run and the number of

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neutrons reaching the silicon detector were recorded for various energy regions.

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This study is shown in Figure 2. position(mm) z zposition(mm)

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80

80

200

70

200

70

100

40

0

40

100 10

200

100

0

100

200

10

200

0

70

200

100

0

100

200

0

70

100

40

20 10

−200 −200

−100

0

100

200

0

100

0

100

200

70 60

100

0

40

50

0

40

30

−100

20 10

−200 −200

−100

0

100

200

0

30

−100

20 10

−200 −200

−100

0

100 200 x position (mm)

Figure 2: Neutrons reaching the detector surface with energies below 100 keV (left), between 100 keV and 1 MeV (center) and above 1 MeV (right). Distributions in the top row were obtained from pure soil and the ones in bottom row were obtained from the explosive buried in soil at 10 cm depth. Red color represents higher neutron intensity on the surface of the detector.

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0

80

200

50

30

−100

10

200

60

50

0

20

200

80

200

60

100

30

100

80

200

40

20

20

200

50

0

30

30

100

60

100 50

50

0

70

60

60

100

80

200

Neutron energy spectra at the entrance of the Si-PIN photodiode detector

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0

100

depending on the buried depth of ammonium nitrate were determined in another

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simulation study. There were visible differences between the energy spectra for

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less than 1 MeV. Reduction in the number of slow-intermediate neutrons is due

103

to thermalization and absorption of neutrons inside ammonium nitrate. Merged

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graph in Figure 3.a shows neutron energies down to the thermal energy bin.

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There are more neutron events originated from the soil with explosive compared

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to the one with pure soil in the thermal energy bin. There is a considerable

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difference between the pure soil and the soil with explosive in terms of number

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of scattered neutrons as seen from the Figure 3.a. However, neutrons are not the

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only particles reaching the detector, there are highly intense gamma background

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due to the inelastic scattering of neutrons both from soil and explosive. Figure

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3.b shows the gamma and neutron events reaching the detector surface. Table

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1 is provided for quantifying this study. In this work, 50 million neutrons from

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the D-T gun were generated and distributed isotropically.

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Counts

Counts

104

103

102

104

10

1

0.01

0.1

1

Energy (keV)

pure soil AN buried in 10 cm depth 103

AN buried in 30 cm depth AN buried in 50 cm depth 0.02

0.03

0.2

0.1

0.3 0.4

1

2 3 Energy (MeV)

Counts

0.01

104

pure soil AN buried in 10 cm depth AN buried in 30 cm depth AN buried in 50 cm depth 0.01

0.02

0.03

0.2

0.1

0.3 0.4

1

2 3 Energy (MeV)

Figure 3: (a) Neutron, (b) Neutron and gamma energy spectra at the entrance of the detector.

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Table 1: Scattered neutron statistics; Nx stands for the number of neutrons reaching the detector. Ex refers to the total energy deposited by neutrons in silicon where x is the upper limit of the energy in MeV.

Case

N1.0

N0.1

E1.0

E0.1

Pure Soil

411466

123965

14870

9748

AN at 50 cm

395014

109946

14768

9581

AN at 30 cm

366415

95782

14604

9527

AN at 10 cm

315674

102658

13490

8487

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Table 1 shows that there is 4% to 23% difference between the pure soil and

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the soil with AN in it for under 1 MeV. However, due to low detection efficiency

116

of bare silicon for neutrons, the 23% scaled down to 13% for the deposited

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energy in the best case. This result already shows that detection of explosive

118

with bare Si-PIN detector is difficult. For that reason, simulations of 6 LiF coated

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or polyethylene masked (as a n-p converter) Si-PIN photodiodes were studied

120

and resulting detection efficiencies were determined. To proceed this work,

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a simulation study was necessary to determine the optimum thickness of 6 LiF

122

coating. For this study, neutrons from 1 keV to 1 MeV were directed to the 6 LiF

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coated photodiode surface and corresponding deposited energies in silicon from

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the interaction of all primary and secondary particles were determined. Figure

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4 shows the relation between the thickness of coating and number of secondary

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particles reaching the surface of Si-PIN photodiode. One can conclude from this

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study that the efficiency does not change much above 50 µm 6 LiF thickness. On

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the other hand, smaller the neutron energy is higher the production rate of alpha

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and triton particles is, as expected. Charged particles generated in the coating

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material deposit all their energies in silicon when they hit.

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Charge particle counts

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1 keV 10 keV 100 keV 1 MeV

2

10

10

20

30

40

50

60

70

80

90 100 Thickness (µm)

Figure 4: Number of charged particles generated in 6 LiF coating and reach the Si-PIN detector depending on the thickness of the coating and incoming neutron energy.

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Figure 5 shows the comparison of energy depositions in Si-PIN for 50 µm

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thick 6 LiF coated, non coated and the case where 1 mm thick polyethylene layer

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is masked in front of the photodiode. As seen from the Figure 5, due to the

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production of charged particles in coating material, energy deposition in silicon

135

increases especially between 0.5 MeV and 3 MeV. It can be also seen that there

136

is a visible difference in the spectra of detected particles above 2 MeV between

137

the polyethylene windowed silicon detector and bare silicon detector. However,

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the advantage of 6 LiF over the polyethylene window can also be seen from the

139

Table 2.

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Counts

104

bare silicon with 50 µm 6LiF coating with 1 mm polyethylene window

103

102

0.1

0.2

0.3

0.4 0.5

1

2

3

4

5

6 7 8 9 10 Energy (MeV)

Figure 5: Comparison of energy depositions in Si-PIN photodiode from scattered neutrons when 6 LiF and polyethylene converters were used.

Table 2: Number of particles that deposited their energies into the detector material above 0.5 MeV when 6 LiF and polyethylene converters were used. 50 million isotropically distributed neutrons from D-T source were used in the simulations.

6

LiF

Polyethylene

Pure Soil

3196

3880

AN at 50 cm

3284

3851

AN at 30 cm

3574

3992

AN at 10 cm

4613

3814

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Figure 6 shows the deposited energy spectrum for polyethylene windowed

141

silicon detector for various bury depths. There is no significant difference in the

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detected events to distinguish the soil and the soil with explosive buried in.

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Counts

104

pure soil AN buried in 10 cm depth AN buried in 30 cm depth AN buried in 50 cm depth

103

102

0.1

0.2

0.3

0.4 0.5

1

2

3

4

5

6 7 8 9 10 Energy (MeV)

Figure 6: Deposited energies in polyethylene windowed silicon PIN photodiode for various bury depths.

Figure 7 shows the deposited energy spectrum for 6 LiF coated silicon de-

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tector for various bury depths of explosive. As seen from the Figure 7, there

145

is a visible difference for the energy deposition between 0.5 MeV and 3 MeV

146

when the buried depth is especially less than 30 cm. This is mostly due to the

147

absorption of alpha and triton particles generated in 6 LiF and deposited their

148

energies in silicon.

Counts

143

104

pure soil AN buried in 10 cm depth AN buried in 30 cm depth AN buried in 50 cm depth

3

10

102

0.1

0.2

0.3

0.4 0.5

1

2

3

4

5

6 7 8 9 10 Energy (MeV)

Figure 7: Deposited energies in 6 LiF coated Si-PIN photodiode for various bury depths.

149

Since the work presented in Figure 5 shows 6 LiF converter to be the best

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candidate to distinguish the signal from background events, it has been decided

151

to focus on 6 LiF. Figure 8 shows a study performed with a 6 LiF converter

152

applied to the detector surface for determining an optimum energy threshold

153

to have the best separation between the soil with and without AN embedded

154

in. The optimum lower energy threshold was determined to be 0.9 MeV and

155

the events above this energy are taken into account for the comparisons in the

156

following studies.

Number of standart deviations (z )

150

30 AN buried in 10 cm depth 25

AN buried in 30 cm depth AN buried in 50 cm depth

20

15

10

5

0

0.2

0.4

0.6

0.8

1

1.2 1.4 Low energy treshold (MeV)

Figure 8: Relation between low energy threshold of detected events and separation quality in terms of number of standard deviations.

157

Number of standard deviations were determined from the following relation; E−S z=√ E+S

(1)

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Here S is the count rate with pure soil and E is the count rate with explosive in

159

soil for various bury depths.

160

Another work performed in the simulations was to investigate if thermalizing

161

the neutrons from 14 MeV D-T neutron source helps the detection or not. For

162

that reason, a 10 cm thick polyethylene block was inserted between the neutron

163

gun and the soil and the resultant deposited energies in 6 LiF coated detector 12

were registered. Figure 9 shows this work. This result can be directly compared

165

with the results presented in Figure 7. It shows that thermalizing the neutrons

166

beforehand has obvious disadvantage.

Counts

164

pure soil AN buried in 10 cm depth AN buried in 30 cm depth

103

AN buried in 50 cm depth

102

0.1

0.2

0.3

0.4 0.5

1

2

3

4

5

6 7 8 9 10 Energy(MeV)

Figure 9: Deposited energies in silicon when 14 MeV neutrons were moderated with 10 cm polyethylene block.

167

Finally, the complete detection system including the source can be mounted

168

on a vehicle. This vehicle travels on a suspicious road and watches for for

169

anomalies in count rate of the scattering neutrons. A question arises as to what

170

should be the maximum speed of the vehicle be in order to have a statisti-

171

cally significant detection of the explosive. For this reason, count rates were

172

determined at various vehicle positions with respect to the buried explosive.

173

In this work, 20 million neutron events were generated at 4π geometry for 19

174

different positions relative to the explosive and energy deposited events in 6 LiF

175

coated photodiode were counted above a certain energy threshold (Figure 10).

176

A low energy threshold of 0.9 MeV was applied for the analysis since it was

177

determined to be the most sensitive threshold for the detection. The sampling

178

intervals were chosen to be 11.6 cm. Since the simulations took considerable

179

amount of time, only 20 million initial events were generated and tracked at

180

each position. This was only 20% of the neutrons provided by D-T source in a

181

second. We have assumed that time takes for the vehicle to travel between the

13

two consecutive positions is 0.100 s (the corresponding speed of the vehicle is

183

1.16 m/s). Full neutron flux available from the D-T source provides 100 million

184

neutrons per second to all directions (4π). This means, similar statistical power

185

can be obtained from a vehicle traveling with 5.80 m/s (20.9 km/h).

Counts

182

100

A

C

B

AN buried in 10 cm soil

soil explosive shield detector source

80

60

A

AN buried in 30 cm soil

C

B

40

0

0.5

1

1.5

2 Distance(m)

Figure 10: Change in the count rate when a vehicle with an installed detector approaches to the buried explosive. The speed of vehicle is 20.9 km/h.

186

2.1. Effect of Soil Humidity

187

It has been known that humidity in soil changes the results due to hydrogen

188

content of water. Humidity content of soil was changed between 5% and 20% and

189

corresponding deposited energies of scattered neutrons including all secondary

190

particles were determined from the simulations. The explosive was buried at

191

10 cm in all cases in this work. Figure 11 shows the comparison of deposited

192

energies for different concentrations of water in soil. The water in soil enhances

193

the signal between 1.5 and 3 MeV which implies that the hydrogen in AN and

194

in H2 O moderates the neutrons down to an energy that their cross section is

195

relatively large to interact with 6 LiF coating Table 3. shows the detectability

196

in terms of number of standard deviations (z) under humid conditions.

14

Counts

104

no humidity 5% humidity 10% humidity 15% humidity

103

102

0.1

0.2

0.3

0.4 0.5

2

1

3

4

5

6 7 8 9 10 Energy (MeV)

Figure 11: Comparison of deposited energies for various cases with different concentrations of water in soil. The explosive was buried at 10 cm depth.

Table 3: Total detector counts for various water concentrations in soil. Case-1 and Case-2 represent the count rates and deviations for buried depths of 10 cm and 30 cm respectively. 0.9 MeV lower energy threshold was used for both cases. Abbreviations; S: Counts from pure soil, E: Counts from soil with explosive buried in, z: Differences in terms of number of standard deviations as described in Equation 1.

Case-1 Humidity

Case-2

S

E

z

E

z

20%

4465

3774

-7.6

4351

-1.2

15%

4152

3368

-9.0

4092

-0.66

10%

3638

2879

-9.4

3480

-1.9

5%

2644

2353

-4.1

2388

-3.6

0%

841

2014

22

1207

8.1

197

Table 3 shows scattering count rate increases almost by a factor of five for the

198

bare soil when humidity concentration changes from 0% to 15%. This is due to

199

large neutron scattering cross section of hydrogen in water. On the other hand,

200

the count rate increases only 40% within explosive positioned to 10 cm depth. 15

201

This shows some of the fraction of the humid soil is replaced by the explosive

202

material having less hydrogen in it. As seen from Table 3, z value changes its sign

203

with humidity. Negative sign of z value is the signature of count deficiency. In all

204

humidity concentration levels we studied, the explosive with 10 cm bury depth

205

is detectable. When the explosive is at 30 cm depth, the count rate increases

206

three times due to change in the humidity concentration level from 0% to 15%.

207

This is due to most neutrons penetrating into soil scatter from hydrogen before

208

reaching the explosive. We can conclude that when the explosive is buried to 30

209

cm depth, it is only detectable if the humidity concentration of soil is less than

210

5%. The results also shows the technique has a dependency on anything in the

211

soil content that have a different water absorption rate than soil. Such materials

212

can look like a buried AN signal and increase the rate of false positives.

213

3. Conclusion

214

Monte Carlo simulations showed that the explosives enhanced by massive

215

amount of AN buried underground can be detected with neutron scattering

216

method by using 6 LiF coated Si-PIN detectors. The optimum thickness of 6 LiF

217

was determined to be 50 µm. Above this thickness, production and absorption

218

rates of the secondary charged particles were observed to be the same. The

219

optimum lower energy threshold for counting the events was determined to

220

be 0.9 MeV. Humidity of the soil is one of the important limiting factor and

221

therefore has been studied in the simulations. The studies showed that it is

222

possible to detect an AN enhanced explosive buried 10 cm depth up to 20%

223

humidity concentration. When the buried explosive is closer to the surface,

224

humidity of the soil increases the detection probability. When it is deeper,

225

success rate of detection strongly depends on the humidity level of the soil. In

226

this study, it was showed that detecting the explosive from 30 cm bury depth

227

is possible if the humidity concentration is less than 5%. The humidity study

228

showed that the success of detection can be influenced by substances having

229

different water absorption rates compared to surrounding soil. These substances

16

230

can generate an AN like signal which increases the rate of false positives. Studies

231

also showed that detection probability of scattered neutrons increases when 14

232

MeV D-T neutron gun was directly used without any moderator.

17

233

4. References

234

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