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Prompt gamma-ray methods for industrial process evaluation: A simulation study

Mohammed Siddig H. Mohammed

Mohammed Siddig H. Mohammed

King Abdulaziz University, Department of Nuclear EngineeringJeddah, Saudi Arabia
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Mohammed, Mohammed Siddig H.
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Abdulsalam Alhawsawi

Abdulsalam Alhawsawi

King Abdulaziz University, Department of Nuclear EngineeringJeddah, Saudi Arabia
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Alhawsawi, Abdulsalam
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M. S. Aljohani

M. S. Aljohani

King Abdulaziz University, Department of Nuclear EngineeringJeddah, Saudi Arabia
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Aljohani, M. S.
, 
Mohammed M. Damoom

Mohammed M. Damoom

King Abdulaziz University, Department of Nuclear EngineeringJeddah, Saudi Arabia
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Damoom, Mohammed M.
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Essam M. Banoqitah

Essam M. Banoqitah

King Abdulaziz University, Department of Nuclear EngineeringJeddah, Saudi Arabia
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Banoqitah, Essam M.
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Ezzat Elmoujarkach

Ezzat Elmoujarkach

King Abdulaziz University, Department of Nuclear EngineeringJeddah, Saudi Arabia
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Elmoujarkach, Ezzat
  
Feb 17, 2022
Prompt gamma-ray methods for industrial process evaluation: A simulation study's Cover Image
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Article Category: Original Paper
Published Online: Feb 17, 2022
Page range: 11 - 18
Received: Feb 01, 2021
Accepted: Nov 09, 2021
DOI: https://doi.org/10.2478/nuka-2022-0001
Keywords
© 2022 Mohammed Siddig H. Mohammed et al., published by Sciendo
This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International License.

Fig. 1

Prompt gamma-ray spectrum of the reaction 157Gd (n, γ).
Prompt gamma-ray spectrum of the reaction 157Gd (n, γ).

Fig. 2

Neutron spectrum of 252Cf.
Neutron spectrum of 252Cf.

Fig. 3

Simulation setup.
Simulation setup.

Fig. 4

The gamma-ray spectrum obtained in the simulation: the pipe with a diameter of 10 cm (a), 20 cm (b), and 30 cm (c).
The gamma-ray spectrum obtained in the simulation: the pipe with a diameter of 10 cm (a), 20 cm (b), and 30 cm (c).

Fig. 5

Neutron dose rates from the neutron source with the minimum activity at different radii.
Neutron dose rates from the neutron source with the minimum activity at different radii.

Fig. 6

Neutron dose rates from the neutron source with the maximum activity at different radii.
Neutron dose rates from the neutron source with the maximum activity at different radii.

Fig. 7

The pipe with a diameter 10 cm without 57Gd (a) and with 57Gd (b). The pipe with a diameter 20 cm without 57Gd (c) and with 57Gd (d). The pipe with a diameter 30 cm without 57Gd (e) and with 57Gd.
The pipe with a diameter 10 cm without 57Gd (a) and with 57Gd (b). The pipe with a diameter 20 cm without 57Gd (c) and with 57Gd (d). The pipe with a diameter 30 cm without 57Gd (e) and with 57Gd.

Fig. 8

Imaging of the pipe with diameter 30 cm using 60Co (a) and prompt gamma-ray (b). (Fig. 8b is reproduced from Fig. 7e).
Imaging of the pipe with diameter 30 cm using 60Co (a) and prompt gamma-ray (b). (Fig. 8b is reproduced from Fig. 7e).

Fig. 9

Reconstructed prompt gamma CT images: (a) X plane, (b) Y plane, (c) Z plane.
Reconstructed prompt gamma CT images: (a) X plane, (b) Y plane, (c) Z plane.

Neutrons interactions with air, water, gadolinium, steel, and the detector

Material Nuclides Atom fraction Total collisions Collisions weight Weight lost to capture Photons produced Photon weight produced%
Air C 1.50E–04 4 1.68E–08 0.00E+00 0 0.00
N 7.84E–01 49 813 2.09E–04 1.06E–05 515 2.16E–04
O 2.11E–01 15 614 6.55E–05 2.77E–07 42 1.76E–05
Ar 4.67E–03 309 1.30E–06 0.00E+00 66 2.77E–05
Water + 5% Gd H 6.65E–01 193 776 900 8.13E–01 2.67E–04 35 038 1.47E–02
O 3.33E–01 37 866 142 1.59E–01 4.52E–04 91 459 3.84E–02
157Gd 2.01E–03 6 394 471 2.68E–02 2.37E–02 19 207 904 8.25E–02
Steel C 2.28E–02 484 984 2.03E–03 1.46E–06 2 726 1.14E–03
Fe 9.77E–01 29 489 449 1.24E–01 5.04E–04 7 955 587 3.34E–02
NaI Na 5.00E–01 8 353 033 3.50E–02 4.11E–05 1 276 750 5.36E–03
I 5.00E–01 14 164 504 5.94E–02 1.88E–03 8 494 594 3.56E–02
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