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Journal Articles

Introduction to modern nodal method and discontinuity factor

Okumura, Keisuke

Nihon Genshiryoku Gakkai Dai-36-Kai Robutsuri Kaki Semina Tekisuto, p.81 - 102, 2004/08

The modern node method which uses a discontinuous factor has come to be widely used recently in the reactor core analyses of commercial light water reactors. The basic theory, numerical computation technique and examples of calculation results are explained for biginners of the modern nodal method.

JAEA Reports

Evaluation for the models of neutron diffusion theory in terms of power density distributions of the HTTR

Takamatsu, Kuniyoshi; Shimakawa, Satoshi; Nojiri, Naoki; Fujimoto, Nozomu

JAERI-Tech 2003-081, 49 Pages, 2003/10

JAERI-Tech-2003-081.pdf:2.6MB

In the case of evaluations for the highest temperature of the fuels in the HTTR, it is very important to expect the power density distributions accurately; therefore, it is necessary to improve the analytical model with the neutron diffusion and the burn-up theory. The power density distributions are analyzed in terms of two models, the one mixing the fuels and the burnable poisons homogeneously and the other modeling them heterogeneously. Moreover these analytical power density distributions are compared wtih the ones derived from the gross $$gamma$$-ray measurements and the Monte Carlo calculational code with continuous energy. As a result the homogeneous mixed model isn't enough to expect the power density distributions of the core in the axial direction; on the other hand, the heterogeneous model improves the accuracy.

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

Journal Articles

Boundary element methods applied to two-dimensional neutron diffusion problems

Journal of Nuclear Science and Technology, 22(7), p.565 - 583, 1985/00

 Times Cited Count:37 Percentile:95.21(Nuclear Science & Technology)

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:0.00(Nuclear Science & Technology)

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:34.94(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:44.84(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis of dieaway experiments in a uranium-238 sphere

Journal of Nuclear Science and Technology, 10(10), p.619 - 625, 1973/10

no abstracts in English

Journal Articles

The perturbation method for the neutron diffusion approximation

Mizoo, Nobutatsu*

Journal of Nuclear Science and Technology, 5(1), p.36 - 36, 1968/00

 Times Cited Count:0

no abstracts in English

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