Skip to main content

The Importance of Anisotropic Scattering in High Energy Neutron Transport Problems

  • Conference paper
Reactor Dosimetry
  • 108 Accesses

Abstract

Neutronic calcuations for high-energy fusion and spallation neutron sources are of increasing interest. The neutron distributions in reactor blankets or deep within shields is influenced by the elastic scattering which becomes highly anisotropic above 10 MeV expecially for heavy elements. Since cannon cross-section libraries are limited by Legendre expansion, or by their upper energy boundary, or exclude elastic scattering above 20 MeV a special library has been created.

To describe the highly anisotropic scattering of very fast neutrons adequately the transport code ANISN has been improved. Fokker-Planck terms have been introduced into the transport equation which accurately describe the small changes in energy and angle. The new code has been tesyed for a d(50)-Be neutron source in a deep penetration iron problem. The influence of the forward peaked elastic scattering on the fast neutron spectrum is shown to be significant and be handled efficiently in the new ANISN version.

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

Access this chapter

Chapter
USD 29.95
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
eBook
USD 39.99
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
Softcover Book
USD 54.99
Price excludes VAT (USA)
  • Compact, lightweight edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info
Hardcover Book
USD 54.99
Price excludes VAT (USA)
  • Durable hardcover edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info

Tax calculation will be finalised at checkout

Purchases are for personal use only

Institutional subscriptions

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

Literature

  1. M. Caro, J. Ligou, Treatment of Scattering Anisotropy of Neutrons through the Boltzmann-Fokker-Planck Equation, Nucl. Sc. Eng. 83, p. 242 (1983).

    Google Scholar 

  2. W.W. Engle, A User’s Manual for ANISN, USAEC Report K-1693 (1967).

    Google Scholar 

  3. G. Prillinger, ANISN-FP, a ANISN Version for High Energy Neutron Transport, to be published.

    Google Scholar 

  4. R.G. Alsmiller, Jr., J. Barish, Neutron Photon Multigroup Cross Sections for Neutron Energies < 400 MeV, ORNL/TM–7818 (1981), RSIC, DLC-87.

    Google Scholar 

  5. W.B. Wilson, Nuclear Data Development and Shield Design for Neutrons Below 60 MeV, LA-7159-T (1978), RSIC, DLC-84.

    Google Scholar 

  6. E.D. Arthur, P.G. Young, Evaluated Neutron-Induced Cross Sections for 54,56Fe to 40 MeV, LA-8626-MS (ENDF-304) (1980).

    Google Scholar 

  7. R.E. McFarlane, D.W. Muir, R.M. Boicourt, The NJOY Nuclear Processing System, Vol. 1, LA-9303-M (ENDF-324) (1982).

    Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Editor information

Editors and Affiliations

Rights and permissions

Reprints and permissions

Copyright information

© 1985 ECSC, EEC, EAEC, Brussels and Luxembourg

About this paper

Cite this paper

Prillinger, G., Mattes, M. (1985). The Importance of Anisotropic Scattering in High Energy Neutron Transport Problems. In: Genthon, J.P., Röttger, H. (eds) Reactor Dosimetry. Springer, Dordrecht. https://doi.org/10.1007/978-94-009-5378-9_28

Download citation

  • DOI: https://doi.org/10.1007/978-94-009-5378-9_28

  • Publisher Name: Springer, Dordrecht

  • Print ISBN: 978-94-010-8873-2

  • Online ISBN: 978-94-009-5378-9

  • eBook Packages: Springer Book Archive

Publish with us

Policies and ethics