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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

Journal Articles

A double finite element method with accurate reflective boundary condition treatment for three-dimensional transport

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

JAEA Reports

Manual for JSSL(JAERI Scientific Subroutine Library); 4th edition

Fujimura, Toichiro;

JAERI-M 92-121, 218 Pages, 1992/09

JAERI-M-92-121.pdf:4.39MB

no abstracts in English

Journal Articles

Solution of three-dimensional neutron transport equation by double finite element method

; ; *

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

JAEA Reports

Manual for JSSL(JAERI Scientific Subroutine Library)

; ; ;

JAERI-M 82-095, 238 Pages, 1982/09

JAERI-M-82-095.pdf:4.77MB

no abstracts in English

JAEA Reports

Parallel Computation for Solving the Tridiagonal Linear System of Equations

; Harada, Hiro; *; ; ;

JAERI-M 9703, 39 Pages, 1981/09

JAERI-M-9703.pdf:0.89MB

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

A Program Package for Soluing Nonlinear Optimization Problems : User's Manual

; ; ;

JAERI-M 9154, 79 Pages, 1980/11

JAERI-M-9154.pdf:2.81MB

no abstracts in English

JAEA Reports

A Program Package for Salving Linear Optimization Problems; User's Manual

; ;

JAERI-M 9048, 38 Pages, 1980/09

JAERI-M-9048.pdf:1.45MB

no abstracts in English

JAEA Reports

Manual on JSSL (JAERI Scientific Subroutine Library) (2nd Edition)

; ;

JAERI-M 8479, 266 Pages, 1979/11

JAERI-M-8479.pdf:5.44MB

no abstracts in English

Journal Articles

Benchmark tests of radiation transport computer codes for reactor core and shield calculations

; *; *; *; *; *; ; *; ; ; et al.

Journal of Nuclear Science and Technology, 15(1), p.56 - 71, 1978/01

 Times Cited Count:7

no abstracts in English

Journal Articles

Application of finite element method to two-dimensional multi-group neutron transport equation in cylindrical geometry

; ; ; ; *

Journal of Nuclear Science and Technology, 14(8), p.541 - 550, 1977/08

 Times Cited Count:3

no abstracts in English

JAEA Reports

A User's Manual for JSSL(JAERI Scientific Subroutine Library)

; ;

JAERI-M 7102, 138 Pages, 1977/05

JAERI-M-7102.pdf:2.87MB

no abstracts in English

JAEA Reports

26 (Records 1-20 displayed on this page)