Inclusion of a general volumetric source option in the ANISN code

E. S. Chalhoub; Roberto D. M. Garcia

doi:10.1117/12.267949

27 February 1997 Inclusion of a general volumetric source option in the ANISN code

E. S. Chalhoub, Roberto D. M. Garcia

Proceedings Volume 2867, International Conference Neutrons in Research and Industry; (1997) https://doi.org/10.1117/12.267949
Event: Fifth International Conference on Applications of Nuclear Techniques: Neutrons in Research and Industry, 1996, Crete, Greece

Abstract

Changes introduced into the ANISN code in order to make available an option for solving neutron-transport problems with volumetric sources that may depend on space and angle are described. The usefulness of this new capability is illustrated for the case of a slab subject to a monodirectional external flux.

Citation Download Citation

E. S. Chalhoub and Roberto D. M. Garcia "Inclusion of a general volumetric source option in the ANISN code", Proc. SPIE 2867, International Conference Neutrons in Research and Industry, (27 February 1997); https://doi.org/10.1117/12.267949

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