Skip to main content
SpringerLink
Log in

Analysis for Radiation and Shielding Dose in Plasma Focus Neutron Source Using FLUKA

  • Original Research
  • Published:
Journal of Fusion Energy Aims and scope Submit manuscript

Abstract

Monte Carlo simulations have been performed for the attenuation of neutron radiation produced at Plasma focus (PF) devices through various shielding design. At the test site it will be fired with deuterium and tritium (D-T) fusion resulting in a yield of about 1013 fusion neutrons of 14 MeV. This poses a radiological hazard to scientists and personnel operating the device. The goal of this paper was to evaluate various shielding options under consideration for the PF operating with D-T fusion. Shields of varying neutrons-shielding effectiveness were investigated using concrete, polyethylene, paraffin and borated materials. The most effective shield, a labyrinth structure, allowed almost 1,176 shots per year while keeping personnel under 20 mSV of dose. The most expensive shield that used, square shield with 100 cm concrete thickness on the walls and Borated paraffin along with borated polyethylene added outside the concrete allowed almost 15,000 shot per year.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Log in via an institution

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Institutional subscriptions

Fig. 1
Fig. 2
Fig. 3
Fig. 4
Fig. 5
Fig. 6
Fig. 7
Fig. 8
Fig. 9
Fig. 10
Fig. 11
Fig. 12
Fig. 13
Fig. 14
Fig. 15
Fig. 16
Fig. 17
Fig. 18
Fig. 19
Fig. 20
Fig. 21
Fig. 22
Fig. 23
Fig. 24
Fig. 25
Fig. 26
Fig. 27
Fig. 28
Fig. 29
Fig. 30
Fig. 31
Fig. 32
Fig. 33
Fig. 34
Fig. 35
Fig. 36
Fig. 37
Fig. 38
Fig. 39
Fig. 40
Fig. 41
Fig. 42
Fig. 43
Fig. 44
Fig. 45

Similar content being viewed by others

References

  1. H.R. Yousefi, F.M. Aghamir, K. Masugata, Effect of the insulator length on Mather-type plasma focus devices. Phys. Lett. A 361, 360–363 (2007)

    Google Scholar 

  2. C. Moreno, H. Bruzzone, J. Martínez, A. Clausse, Conceptual engineering of plasma-focus thermonuclear pulsors, IEEE Trans. Plasma Sci. 28(5), (2000)

  3. R.J. O’Brien, Shielding and Radiation Dose Analysis for A Dense-Plasma Focus Neutron Source, (Mechanical Engineering University of Nevada, Las Vegas, 2005)

  4. V. Andersen, F. Ballarini, G. Battistoni, M. Campanella, M. Carboni, F. Cerutti, A. Empl, A. Fasso, A. Ferrari, E. Gadioli, M.V. Garzelli, K. Lee, A. Ottolenghi, M. Pelliccioni, L.S. Pinsky, J. Ranft, S. Roesler, P.R. Sala, T.L. Wilson, Fluka toward a FLUKA based simulation tool aimed at the evaluation of space radiation environments (2004)

  5. A. Ferrari, P. R. Sala, A. Fass`o, J. Ranft, Fluka: a Multi-Particle Transport Code (Program version 2008)

  6. L. Soto, New Trends and Future Perspectives on Plasma Focus Research, (Institute of Physics Publishing, 2005)

  7. S. Lee, Scaling of the Plasma Focus. Viewpoint from Dynamics, Nanyang Technology University, National Institute of Education 469, Bukit Timah Road, Singapore 259756 (1998)

Download references

Author information

Authors and Affiliations

  1. Nuclear Engineering and Physics Faculty, Amirkabir University of Technology, Tehran, Iran

    M. J. Nemati, R. Amrollahi & M. Habibi

Authors
  1. M. J. Nemati
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. R. Amrollahi
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. M. Habibi
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding author

Correspondence to M. J. Nemati.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Nemati, M.J., Amrollahi, R. & Habibi, M. Analysis for Radiation and Shielding Dose in Plasma Focus Neutron Source Using FLUKA. J Fusion Energ 31, 284–297 (2012). https://doi.org/10.1007/s10894-011-9454-8

Download citation

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10894-011-9454-8

Keywords

Search

Navigation