DESIGN OF THE LOCAL GAMMA COUNTER SHIELD FOR THE INSTALLATION - - PowerPoint PPT Presentation

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DESIGN OF THE LOCAL GAMMA COUNTER SHIELD FOR THE INSTALLATION - - PowerPoint PPT Presentation

DESIGN OF THE LOCAL GAMMA COUNTER SHIELD FOR THE INSTALLATION INTENDED FOR THE IDENTIFICATION OF HIDDEN EXPLOSIVES AND DRUGS Participants: Supervisor: Michal Kesina , Ekaterina Lesovaya, University of West Bohemia in Pilsen Joint Institute


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SLIDE 1

DESIGN OF THE LOCAL GAMMA COUNTER SHIELD FOR THE INSTALLATION INTENDED FOR THE IDENTIFICATION OF HIDDEN EXPLOSIVES AND DRUGS

Supervisor: Ekaterina Lesovaya, Joint Institute for Nuclear Research in Dubna Participants: Michal Křesina, University of West Bohemia in Pilsen Anna Borkowska Michał Nowakowski Jagiellonian University in Cracow

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SLIDE 2

Plan of presentation

2

Design of the local gamma counter shield...

  • M. Kresina , A. Borkowska, M. Nowakowski

1.Introduction 2.The aim and task 3.An equipment description 4.Results 5.Conclusions 6.Bibliography

en.wikipedia.org siliconangle.com www.pittsburghcoalitionforsecurity.org

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SLIDE 3
  • 1. Introduction

3

Design of the local gamma counter shield...

  • M. Kresina , A. Borkowska, M. Nowakowski

Airport scanners Complex for monitoring vehicles Mobile complex

Variants for detecting hidden drugs and explosives “Rapiscan Systems” (USA)

1 2 3 4 5 6 7 8 9 50 100 150 200

4.44 MeV cross section, mbarn Е, MeV

12C 1 2 3 4 5 6 7 8 9 20 40 60 80 100 120 140 160 180

7.12 6.92 6.13 4.44 3.86 3.69 3.09 2.75 1.76 cross section, mbarn Е, MeV

16O

1 2 3 4 5 6 7 8 9 10 20 30 40 50 60

2.13 3.09 6.1 6.45 6.73 7.03 5.11 4.44 3.86 3.69 2.32 1.64 cross section, mbarn Е, MeV

14N

Gamma ray lines produced by 14.1 MeV neutron irradiation of carbon, nitrogen and oxygen

  • E. Lesovaya
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SLIDE 4
  • 2. The aim and tasks

4

Design of the local gamma counter shield...

  • M. Kresina , A. Borkowska, M. Nowakowski

Computational modeling

  • f the local shield of a gamma

spectrometer against 14.1 MeV neutrons for choosing the optimal shielding material and design.

www.wisegeek.com

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SLIDE 5
  • 3. An equipment description

5

Design of the local gamma counter shield...

The calculations have been carried

  • ut using the Monte Carlo

(MC)-based MCNP4C code. The MCNP code, developed and maintained by Los Alamos National Laboratory, is the internationally recognized code for the MC analysis of neutron and gamma ray transport (hence NP for neutral particles).

  • M. Kresina , A. Borkowska, M. Nowakowski

greatlakesgeomatics.com

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SLIDE 6
  • 3. An input file

6

Design of the local gamma counter shield...

Mode n p IMP:n,p 1 1 0 1 0 1 1 SDEF cel=4 pos=0.01 0 0 vec=1 0 0 dir=d1 par=1 erg=14 wgt=5e+6 SI1 0 1 SP1 0 1 M1 6000.60c 0.3333 1001.60c 0.6667 $ Polyethylene M3 82000.60c 1 $ Pb-nat M2 26000.50c 1 $ Fe-nat F1:n (7 8 9) 7 fq1 e f F11:p (7 8 9) 7 fq11 e f E1 1e-9 1.585e-9 2.512e-9 3.981e-9 6.31e-9 1e-8 1.585e-8 2.512e-8 3.981e-8 6.31e-8 1e-7 1.585e-7 2.512e-7 3.981e-7 6.31e-7 1e-6 1.585e-6 2.512e-6 3.981e-6 6.31e-6 1e-5 1.585e-5 2.512e-5 3.981e-5 6.31e-5 1e-4 1.585e-4 2.512e-4 3.981e-4 6.31e-4 1e-3 1.585e-3 2.512e-3 3.981e-3 6.31e-3 1e-2 1.585e-2 2.512e-2 3.981e-2 6.31e-2 1e-1 1.585e-1 2.512e-1 3.981e-1 6.31e-1 1e-0 1.585e-0 2.512e-0 3.981e-0 6.31e-0 1e+1 11 12 13 13.9 14 E11 0.5 474i 10 4i 20 NPS 2000000000 CTME 60 c ===cells=== 1 2 -7.8 1 -12 -5 6 2 -4 $ Fe 2 2 -7.8 11 -13 -5 6 2 -4 3 0 -7 9 -8 $ BGO 4 0 -10 (-1:3:5:-6:-2:4) (7:8:-9) 5 0 10 6 2 -7.8 12 -11 -5 6 2 -4 7 2 -7.8 13 -3 -5 6 2 -4 c ===== SURFACES ==== 1 px 5 2 p 0.15 1 0 0 3 px 30 4 p -0.15 1 0 0 5 p -0.15 0 1 0 6 p 0.15 0 1 0 7 c/z 33.82 0 3.81 8 pz 3.81 9 pz -3.81 10 so 100 11 px 17.5 12 px 11.25 13 px 23.75

Monte Carlo simulations for the

  • ptimization of shielding materials

for gamma-detector cell card- used to specify volume surface card- used to specify surfaces geometry data card- contains any data that is needed for the problem

  • M. Kresina , A. Borkowska, M. Nowakowski
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SLIDE 7
  • 3. An input file: geometry and material

7

Design of the local gamma counter shield...

  • M. Kresina , A. Borkowska, M. Nowakowski

L/2 2 4,5,6 x y z 5 cm L/4 L=25 cm, 35 cm, 45 cm 7.62 cm 3.81 cm 12 1 11 13 3 9 7 8 BGO S 1 6 2 7 Homogenous shield Polyethylene (CH2, ρ=0.94 g/cm3) Iron (Fe, ρ=7.8 g/cm3) Lead (Pb, ρ=11.4 g/cm3) Heterogeneous shield CH2- Fe and Fe- CH2 CH2- Pb and Pb- CH2

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SLIDE 8

1E-9 1E-6 1E-3 1 0.01 0.1 1 10 100 1000

Polyethylene Number of neutrons in the bin E[MeV] 25 cm 35 cm 45 cm

1E-3 0.1 10 0.1 1 10 100 1000

25 cm 35 cm 45 cm Iron Number of neutrons in the bin E[MeV]

0.01 0.1 1 10 0.1 1 10 100 1000

Lead Number of neutrons in the bin E[MeV] 25 cm 35 cm 45 cm

8

Design of the local gamma counter shield...

  • M. Kresina , A. Borkowska, M. Nowakowski

Fe Pb Pol

  • 4. Results for neutrons: homogeneous shields
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SLIDE 9

9

Design of the local gamma counter shield...

  • M. Kresina , A. Borkowska, M. Nowakowski

Fe Pb

  • 4. Results for neutrons: heterogeneous shields

1E-9 1E-6 1E-3 1 0.01 0.1 1 10 100 1000

Lead-Polyethylene

Number of neutrons in the bin E[MeV] 25 cm 35 cm 45 cm

1E-3 1 1E-3 0.01 0.1 1 10 100 1000

Polyethylene-Lead

Number of neutrons in the bin E[MeV] 25 cm 35 cm 45 cm

1E-9 1E-6 1E-3 1 0.01 0.1 1 10 100 1000

Iron-Polyethylene

Number of neutrons in the bin E[MeV] 25 cm 35 cm 45 cm

1E-6 1E-4 0.01 1 1E-3 0.01 0.1 1 10 100 1000

Polyethylene-Iron

Number of neutrons in the bin E[MeV] 25 cm 35 cm 45 cm

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SLIDE 10

Results for neutrons: sum up

10

Design of the local gamma counter shield...

  • M. Kresina , A. Borkowska, M. Nowakowski

neutrons [%] shield / depth [cm] 25 35 45 Polyethylene 0.5726 0.1178 0.0267 Fe 0.0990 0.0084 0.0007 Pb 0.2740 0.0355 0.0047 PbPol 0.3469 0.0522 0.0082 PolPb 0.4446 0.0776 0.0147 FePol 0.1973 0.0234 0.0030 PolFe 0.2758 0.0393 0.0060

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SLIDE 11

Results for γ rays: homogeneous shields

11

Design of the local gamma counter shield...

  • M. Kresina , A. Borkowska, M. Nowakowski

1 2 3 4 5 6 7 4 8 12 16 18

Iron Number of gamma rays in the bin E [MeV] 25cm 35cm 45cm

1 2 3 4 5 6 2 4 10.0 10.2 10.4 10.6 10.8 11.0

Lead Number of gamma rays in the bin E [MeV] 25cm 35cm 45cm

1 2 3 4 5 6 0.00 0.05 0.10 0.15 0.20 0.25 120 130

Polyethylen Number of gamma rays in the bin E [MeV] 25cm 35cm 45cm

Fe Pb Pol

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SLIDE 12

Results for γ rays : heterogeneous shields

12

Design of the local gamma counter shield...

  • M. Kresina , A. Borkowska, M. Nowakowski

Pb Fe

1 2 3 4 5 6 7 8 9 10 3 6 34

Iron - Polyethylen Number of gamma rays in the bin E [MeV] 25cm 35cm 45cm

1 2 3 4 5 6 2 45 54

Lead - Polyethylen Number of gamma rays in the bin E [MeV] 25cm 35cm 45cm

1 2 3 4 5 6 7 8 9 10 20 45.0 45.5 46.0 46.5 47.0 47.5 48.0

Polyethylen - Iron Number of gamma rays in the bin E [MeV] 25cm 35cm 45cm

1 2 3 4 5 6 2 4 6 16 18

Polyethylen - Lead Number of gamma rays in the bin E [MeV] 25cm 35cm 45cm

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SLIDE 13

Results for γ rays: sum up

13

Design of the local gamma counter shield...

  • M. Kresina , A. Borkowska, M. Nowakowski

gamma rays [%] shield / depth [cm] 25 35 45 Polyethylene 0.0171 0.0041 0.0011 Fe 0.0624 0.0053 0.0007 Pb 0.0281 0.0037 0.0004 PbPol 0.0188 0.0029 0.0005 PolPb 0.0469 0.0078 0.0015 FePol 0.0386 0.0046 0.0006 PolFe 0.1702 0.0245 0.0038

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SLIDE 14
  • 5. Conclusions

14

Design of the local gamma counter shield...

  • M. Kresina , A. Borkowska, M. Nowakowski
  • 1. We have mastered MCNP – a universal program for neutron and gamma ray transport in matter.
  • 2. Using the MCNP4C program, we calculated the spectra of neutrons and γ rays emitted from homogeneous

and heterogeneous shields made of CH2, Fe, Pb, and their combinations with a thickness of 25, 35, and 45 cm towards the gamma-spectrometer. The neutrons hitting the shielding had an energy

  • f 14.1 MeV.
  • 3. We have proposed a criteria of evaluating of the effectiveness of shields as regards minimizing the

number of background counts.

  • Total number of secondary neutrons is minimalized.
  • The most dangerous thermal and epithermal neutrons are abscent in flux.
  • Yield from secondary γ rays in energies above 4 MeV is the lowest (4.44 MeV 12C,

5.11 MeV 14N,6.13 16O).

  • 5. It is shown that a homogeneous 45 cm iron shield is the most efficient against secondary neutrons

and γ rays because:

  • 4. It is shown that the shape of the neutron spectra for a heterogeneous shields is mainly determined

by the last layer of the shield matter.

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SLIDE 15
  • 6. Bibliography

15

Design of the local gamma counter shield...

  • M. Kresina , A. Borkowska, M. Nowakowski
  • 1. G. Lucas, MCNP Tutorial, Spring 2010,

http://homepages.cae.wisc.edu/~bohm/neep412/lucasMCNPTutorialspring2010.pdf

  • 2. X-5 Monte Carlo Team, MCNP — A General Monte Carlo N-Particle Transport Code,

Version 5, 24 April 2013, http://www.nucleonica.net/wiki/images/8/89/MCNPvolI.pdf

www.creativindie.com

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SLIDE 16
  • 7. The end

16

Design of the local gamma counter shield...

  • M. Kresina , A. Borkowska, M. Nowakowski

Thank you for your attention!