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Maruyama, Shuhei
Proceedings of International Conference on Physics of Reactors 2022 (PHYSOR 2022) (Internet), 10 Pages, 2022/05
This paper proposes a new homogenization method, "Boundary Condition Free Homogenization (BCFH)". The traditional homogenization method separates the core calculation and the cell (assembly) calculation by assuming a specific boundary condition or a peripheral region in the cell calculation. Nevertheless, there are ambiguities and approximation in these assumptions, and they can also cause a decline in accuracy. BCFH aims to avoid these problems and improve the accuracy in the cell calculation such as homogenization. We imposed the conditions that the physical quantities in the cell related to the reaction rate preservation is preserved for any incoming partial current, during the homogenization. That is, the response matrices of cell average (or total) flux and outgoing partial current, to be the same form between heterogeneous and homogeneous system. As a result, homogenized parameters, such as cross-sections, superhomgenization factors, and discontinuity factors, are no longer dependent on a specific boundary condition. The new homogenized parameters obtained in this way are extended from the conventional vector form to the matrix form in BCFH. To investigate the performance of BCFH, numerical tests are done for the simplified models which originates in 750MW-class sodium-cooled fast reactor with MOX fuel core in Japan. It is found that BCFH is particularly effective in evaluating control rod reactivity worth and reaction rate distribution, compared to the traditional method. We conclude that the BCFH can be a promising homogenization concept for core neutronic analysis.
Wang, Z.; Duan, G.*; Matsunaga, Takuya*; Sugiyama, Tomoyuki
International Journal of Heat and Mass Transfer, 157, p.119919_1 - 119919_20, 2020/08
Times Cited Count：17 Percentile：76.17(Thermodynamics)
dinger equationUtsumi, Takayuki*; Yabe, Takashi*; Koga, J. K.; Aoki, Takayuki*; Sekine, Masatoshi*
Computer Physics Communications, 157(2), p.121 - 138, 2004/02
Times Cited Count：13 Percentile：51.45(Computer Science, Interdisciplinary Applications)no abstracts in English
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.
Tokuda, Shinji; *
Tokei Suri Kenkyujo Kyodo Kenkyu Ripoto, 110, p.70 - 77, 1998/03
no abstracts in English
Kunugi, Tomoaki; *; *
Proc. of 2nd Japan-Central Europe Joint Workshop on Modelling of Materials and Combustion, 0, p.205 - 208, 1996/00
no abstracts in English
Fujimura, Toichiro
Computer Physics Communications, 82, p.111 - 119, 1994/00
Times Cited Count：1 Percentile：21.58(Computer Science, Interdisciplinary Applications)no abstracts in English
JAERI-M 91-108, 25 Pages, 1991/07
no abstracts in English
C-J.Jeong*; Okumura, Keisuke; ; Tanaka, Kenichi*
Journal of Nuclear Science and Technology, 27(6), p.515 - 523, 1990/06
no abstracts in English
; ;
JAERI-M 84-159, 147 Pages, 1984/09
no abstracts in English
; *;
JAERI-M 83-144, 40 Pages, 1983/09
no abstracts in English
; ; *
Journal of Nuclear Science and Technology, 20(7), p.620 - 623, 1983/00
Times Cited Count：3 Percentile：54.47(Nuclear Science & Technology)no abstracts in English
