Analysis of the applicability of acceleration methods for a triangular prism geometry nodal diffusion code

Fujimura, Toichiro*; Okumura, Keisuke

JAERI-Research 2002-024, 27 Pages, 2002/11

JAERI-Research-2002-024.pdf:1.04MB

A prototype version of a diffusion code has been developed to analyze the hexagonal core as reduced moderation reactor and the applicability of some acceleration methods have been investigated to accelerate the convergence of the iterative solution method. The hexagonal core is divided into regular triangular prisms in the three-dimensional code MOSRA-Prism and a polynomial expansion nodal method is applied to approximate the neutron flux distribution by a cubic polynomial. The multi-group diffusion equation is solved iteratively with ordinal inner and outer iterations and the effectiveness of acceleration methods is ascertained by applying an adaptive acceleration method and a neutron source extrapolation method, respectively. The formulation of the polynomial expansion nodal method is outlined in the report and the local and global effectiveness of the acceleration methods is discussed with various sample calculations. A new general expression of vacuum boundary condition, derived in the formulation is also described.

A New mixed method with finite difference and finite element method for neutron diffusion calculation

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Journal of Nuclear Science and Technology, 18(8), p.571 - 580, 1981/00

https://doi.org/10.3327/jnst.18.571

no abstracts in English

EISPACK-J: Subprogram Package for Solving Eigenvalue Problems; Development and Benchmark Test of SSL, No.8

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JAERI-M 8253, 133 Pages, 1979/05

JAERI-M-8253.pdf:4.0MB

no abstracts in English