Journal of Fusion Energy

, Volume 35, Issue 4, pp 621–625 | Cite as

Three Dimensional Simulation of ITER Machine by Using Geant4

Original Research
First Online:
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Abstract

International Thermonuclear Experimental Reactor (ITER) is used as a model in this examination. By using dimensional characteristics and materials used in this Tokomak and in order to study some of its parameters, simulation is done by the use of Geant4 code. In order that the results are closer to reality, all the volumes (cylinders, torus and spheres) are defined three-dimensional for the code. With respect to neutrons produced in the plasma because the fusion reaction (D, T), for the neutrons with 14.1 MeV energy that emit isotropically, a torus shaped volume source also is defined for the code. The number of neutrons was obtained at any moment of the time in different parts of the machine. For some important parts, neutron energy spectrum in that part also was obtained. X-rays energy spectrum and prompt gamma inside and outside of the machine are also obtained. The results correspond well with published reports of this field. This paper also tries to show the ability and capability of the Geant4 code to simulate nuclear reactors like ITER.

Keywords

GEANT4 Monte Carlo simulation Tokamak Neutron and gamma spectra 
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References

  1. 1.
    ITER Physics Basis Editor, et al., ITER Final Design Report, Nuclear Fusion 39 (1999)Google Scholar
  2. 2.
    T. Kammash, Fusion Reactor Physics, Principles and Technology (Ann Arbor Science, Ann Arbor, 1975)Google Scholar
  3. 3.
    C.E. Velasquez et al., Axial neutron flux evaluation in a Tokamak system: a possible transmutation blanket position for a fusion–fission transmutation system. Braz. J. Phys. 42, 237–247 (2012). doi: 10.1007/s13538-012-0081-2 ADSCrossRefGoogle Scholar
  4. 4.
    R. Neu et al., Operational conditions in a W-clad tokamak. J. Nucl. Mater. 367, 1497–1502 (2007). doi: 10.1016/j.jnucmat.2007.04.018 ADSCrossRefGoogle Scholar
  5. 5.
    X.-F. Jiang, J. Cao, C.-Y. Jiang, H.-R. Cao, X.-Y. Song, Z.-J. Yin, Tokamak fusion neutron spectrometer based on PXI bus. Nucl. Sci. Tech. (2014). doi: 10.13538/j.1001-8042/nst.25.040401 Google Scholar
  6. 6.
    S. Li, X. Xu, H. Cao, Q. Yang, Z. Yin, Dynamic linear calibration method for a wide range neutron flux monitor system in ITER. Nucl. Sci. Tech. 24(4), 40401 (2013)Google Scholar
  7. 7.
    H. Cao, S. Li, X. Xu, S. Tang, J. Yang, Q. Yang, Z. Yin, An automatic gain adjustment Campbell integrator for neutron flux detection in ITER. Nucl. Sci. Tech. 23(2), 114–117 (2012)Google Scholar
  8. 8.
    L.I.U. Rong et al., Reaction rates in blanket assemblies of a fusion–fission hybrid reactor. Nucl. Sci. Tech. 23(4), 242–246 (2012). doi: 10.13538/j.1001-8042/nst.23.242-246 Google Scholar
  9. 9.
    A. Araujo, C. Pereira, M.A.F. Veloso, A.L. Costa, Flux and dose rate evaluation of iter system using MCNP5. Braz. J. Phys. 40, 58–62 (2009). doi: 10.1590/S0103-97332010000100010 ADSCrossRefGoogle Scholar
  10. 10.
  11. 11.
  12. 12.

Copyright information

© Springer Science+Business Media New York 2016

Authors and Affiliations

  1. 1.School of Plasma Physics and Nuclear FusionInstitute of Nuclear Science and Technology (AEOI)TehranIran

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