Skip to main content
Log in

High-accuracy neutron diffusion calculations based on integral transport theory

  • Regular Article
  • Published:
The European Physical Journal Plus Aims and scope Submit manuscript

Abstract

In this paper, the Ronen method is developed, implemented, and applied to resolve the neutron flux and the criticality eigenvalue in simple one-dimensional homogeneous and heterogeneous problems. The Ronen method is based on iterative calculations of correction factors to use in a multigroup diffusion model, where the factors are actually given by the integral transport equation. In particular, spatially dependent diffusion constants are modified locally in order to reproduce new estimates of the surface currents obtained by the integral transport operator. The diffusion solver employed in this study uses finite differences, and the transport-corrected currents are introduced into the numerical scheme as drift terms. The corrected solutions are compared against reference results from a discrete ordinate code. The results match well with the reference solutions, especially in the limit of fine meshes, but slow convergence of the scalar flux is reported.

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

Access this article

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

Instant access to the full article PDF.

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

Similar content being viewed by others

References

  1. J. Kim, Y. Kim, Development of 3-D HCMFD algorithm for efficient pin-by-pin reactor analysis. Ann. Nuclear Energy 127, 87–98 (2019)

    Google Scholar 

  2. W.R. Martin, Challenges and prospects for whole-core Monte Carlo analysis. Nuclear Eng. Technol. 44(2), 151–160 (2012)

    Google Scholar 

  3. K. Smith, Monte Carlo for practical LWR analysis: what’s needed to get to the goal? in American Nuclear Society Summer Meeting, M&C Division, Computational Roundtable, Hollywood, FL, June 27, 2011 (2011)

  4. R.D. Lawrence, Progress in nodal methods for the solution of the neutron diffusion and transport equations. Prog. Nuclear Energy 17(3), 271–301 (1986)

    Google Scholar 

  5. K.S. Smith, Assembly homogenization techniques for light water reactor analysis. Prog. Nuclear Energy 17(3), 303–335 (1986)

    Google Scholar 

  6. F. Bertrand, N. Marie, G. Prulhière, J. Lecerf, J.M. Seiler, Comparison of the behaviour of two core designs for ASTRID in case of severe accidents. Nuclear Eng. Des. 297, 327–342 (2016)

    Google Scholar 

  7. IAEA, Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation. Number 52 in Safety Reports Series (International Atomic Energy Agency, Vienna, 2008)

    Google Scholar 

  8. G.I. Bell, S. Glasstone, Nuclear Reactor Theory (Van Nostrand Reinhold, New York, 1970)

    Google Scholar 

  9. J.M. Pounders, F. Rahnema, On the diffusion coefficients for reactor physics applications. Nuclear Sci. Eng. 163, 243–262 (2009)

    Google Scholar 

  10. P.S. Brantley, E.W. Larsen, The simplified \(P_3\) approximation. Nuclear Sci. Eng. 134, 1–21 (2000)

    Google Scholar 

  11. D. Tomatis, A. Dall’Osso, Application of a numerical transport correction in diffusion calculations, in International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011), Rio de Janeiro, RJ, Brazil, May 8–12, 2011, 05 (2011)

  12. Y. Ronen, Accurate relations between the neutron current densities and the neutron fluxes. Nuclear Sci. Eng. 146(2), 245–247 (2004)

    Google Scholar 

  13. K.S. Smith, Nodal method storage reduction by nonlinear iteration. Trans. Am. Nuclear Soc. 44, 265–266 (1983)

    Google Scholar 

  14. B. Davison, J.B. Sykes, Neutron Transport Theory (Oxford University Press, Oxford, 1957)

    Google Scholar 

  15. K.M. Case, P.F. Zweifel, Linear Transport Theory (Addison-Wesley, Reading, 1967)

    Google Scholar 

  16. G.C. Pomraning, The Equations of Radiation Hydrodynamics (Pergamon Press, Oxford, 1973)

    Google Scholar 

  17. J.J. Duderstadt, W.R. Martin, Transport Theory (Wiley, New York, 1979)

    Google Scholar 

  18. E.E. Lewis, W.F. Miller, Computational Methods of Neutron Transport (Wiley, New York, 1984)

    Google Scholar 

  19. M. Abramowitz, I.A. Stegun, Handbook of Mathematical Functions with Formulas, Graphs, and Mathematical Tables (Dover, New York, 1964)

    Google Scholar 

  20. Y.A. Cengel, M.N. Özişik, Integrals involving Legendre polynomials that arise in the solution of radiation transfer. J. Quant. Spectrosc. Radiat. Transf. 31(3), 215–219 (1984)

    Google Scholar 

  21. J.J. Settle, Some properties of an integral that occurs in problems of radiative transfer. J. Quant. Spectrosc. Radiat. Transf. 52(2), 195–206 (1994)

    Google Scholar 

  22. I.S. Gradshteyn, I.M. Ryzhik, Table of Integrals, Series, and Products, 7th edn. (Academic Press, London, 2007)

    Google Scholar 

  23. J.R. Lamarsh, Introduction to Nuclear Reactor Theory (Addison-Wesley, Reading, 1966)

    Google Scholar 

  24. F. Rahnema, E.M. Nichita, Leakage corrected spatial (assembly) homogenization technique. Ann. Nuclear Energy 24(6), 477–488 (1997)

    Google Scholar 

Download references

Acknowledgements

The authors express their gratitude to Prof. Yigal Ronen who initiated the idea for this study. R.G. is partially supported by the Israel Ministry of Energy, Contract No. 216-11-008.

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to Erez Gilad.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Gross, R., Tomatis, D. & Gilad, E. High-accuracy neutron diffusion calculations based on integral transport theory. Eur. Phys. J. Plus 135, 235 (2020). https://doi.org/10.1140/epjp/s13360-020-00216-y

Download citation

  • Received:

  • Accepted:

  • Published:

  • DOI: https://doi.org/10.1140/epjp/s13360-020-00216-y

Navigation