ANISN-DORT-ROZ-MCNP-TRAMO Neutron-Gamma Flux Intercomparison Exercise for a Simple Testing Model


ANISN-DORT-ROZ-MCNP-TRAMO Neutron-Gamma Flux Intercomparison Exercise for a Simple Testing Model

Böhmer, B.; Borodkin, G.; Brodkin, E.; Egorov, A.; Konheiser, J.; Kozhevnikov, S.; Manturov, G.; Voloschenko, A.; Zaritsky, S.

The ability of transport codes ANISN, DORT, ROZ-6, MCNP and TRAMO, as well as nuclear data libraries BUGLE-96, ABBN-93, VITAMIN-B6 and ENDF/B-6 to deliver consistent gamma and neutron flux results was tested in calculation of an one-dimensional cylindrical model consisting of a homogeneous core and an outer zone with a single material. Model variants with H2O, Fe, Cr and Ni in the outer zones were investigated. The results are compared with MCNP-ENDF/B-6 results. Discrepancies are discussed. The specified test model is proposed as a computational benchmark for testing calculation codes and data libraries.

Keywords: Coupled neutron-gamma transport calculations; neutron data libraries; Monte Carlo Codes; discrete ordinate codes; calculational benchmark

  • Poster
    11th International Symposium on Reactor Dosimetry, 18 -23 August 2002 in Brussels, Belgium, Proceedings by World Scientific Publ., ISBN 981-238-448-0, p. 572-579
  • Lecture (Conference)
    13th Seminar on Algorithms and Codes for Neutronics Calculations of Nuclear Reactors, 26-29 October 2002, Obninsk, Rußland
  • Contribution to proceedings
    11th International Symposium on Reactor Dosimetry, 18 -23 August 2002 in Brussels, Belgium, Proceedings by World Scientific Publ., ISBN 981-238-448-0, p. 572-579

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Publ.-Id: 4273