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JAEA Reports

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.

JAEA Reports

MOSRA-Light; High speed three-dimensional nodal diffusion code for vector computers

Okumura, Keisuke

JAERI-Data/Code 98-025, 243 Pages, 1998/10

JAERI-Data-Code-98-025.pdf:10.15MB

no abstracts in English

JAEA Reports

SRAC95; General purpose neutronics code system

Okumura, Keisuke; *;

JAERI-Data/Code 96-015, 445 Pages, 1996/03

JAERI-Data-Code-96-015.pdf:12.94MB

no abstracts in English

Journal Articles

Vectorization of the three-dimensional neutron diffusion code CITATION

Harada, Hiro;

Nihon Genshiryoku Gakkai-Shi, 27(11), p.1047 - 1055, 1985/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Vectorization of Nuclear Codes on FACOM230-75APU Computer

Harada, Hiro; ; ; ;

JAERI-M 83-024, 61 Pages, 1983/02

JAERI-M-83-024.pdf:1.47MB

no abstracts in English

Journal Articles

Application of a hexagonal element scheme in the finite element method to three-dimensional diffusion problem of fast reactors

;

Journal of Nuclear Science and Technology, 20(11), p.951 - 960, 1983/00

 Times Cited Count:2 Percentile:35.16(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Effectiveness of an adaptive acceleration method for inner iterations in some neutron diffusion codes

; *

Nuclear Science and Engineering, 77, p.360 - 367, 1981/00

 Times Cited Count:2 Percentile:45.38(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

10 (Records 1-10 displayed on this page)
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