Multigroup neutral particle transport theory revisited: The development of an analytical Benchmark

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

The multigroup equation of neutron transport theory is solved in an infinite medium setting to obtain the partial Green's function. The solution is found via a Fourier transform approach from which the singular eigenfunction expansion emerges. The solution features full anistropic scattering and a full group-to-group scattering matrix. As a demonstration, the scalar flux for several scenarios is obtained both in plane and spherical geometries. The application of the Wynn-epsilon acceleration algorithm is shown to provide remarkable improvement for highly forward-peaked scattering.

Original languageEnglish (US)
Title of host publicationProceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology
Subtitle of host publicationReactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting
PublisherAmerican Nuclear Society
ISBN (Electronic)0894486721, 9780894486722
StatePublished - 2002
Event2002 International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing, PHYSOR 2002 - Seoul, Korea, Republic of
Duration: Oct 7 2002Oct 10 2002

Publication series

NameProceedings of the PHYSOR 2002 - International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing - The ANS 2002 RPD Topical Meeting

Conference

Conference2002 International Conference on the New Frontiers of Nuclear Technology : Reactor Physics, Safety and High-Performance Computing, PHYSOR 2002
Country/TerritoryKorea, Republic of
CitySeoul
Period10/7/0210/10/02

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Nuclear and High Energy Physics
  • Radiation
  • Safety, Risk, Reliability and Quality

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