27 February 1997 Development of nodal Sn transport method in 3D hexagonal geometry
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Proceedings Volume 2867, International Conference Neutrons in Research and Industry; (1997) https://doi.org/10.1117/12.267959
Event: Fifth International Conference on Applications of Nuclear Techniques: Neutrons in Research and Industry, 1996, Crete, Greece
Abstract
A new nodal Sn transport calculation code NSHEX has been developed to accurately estimate the 3D transport effect of fast reactors in hexagonal-z geometry. The intra-node distribution of source is expanded into quadratic polynomials, and the neutron angular distribution of node surface fluxes and intra-node fluxes is considered by Sn quadrature. In addition, some improvements have been made on the code in order to enhance the accuracy. The accuracy of the present method was validated through numerical analyses for a commercial scale fast reactor with the comparison of Monte Carlo method.
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Toshikazu Takeda, Toshikazu Takeda, Toshihisa Yamamoto, Toshihisa Yamamoto, Yousuke Katagi, Yousuke Katagi, Kei Ohya, Kei Ohya, } "Development of nodal Sn transport method in 3D hexagonal geometry", Proc. SPIE 2867, International Conference Neutrons in Research and Industry, (27 February 1997); doi: 10.1117/12.267959; https://doi.org/10.1117/12.267959
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