Nonlinear Iterative Nodal Method Applied to Neutron Flux Modal Analysis
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概要
- 論文の詳細を見る
The CCCMA (Correction Coupling Coefficient Modal Analysis) method has been proposed to improve the spatial resolution of the neutron flux modal analysis. The improvement has been achieved by including the higher order intra-nodal information through the NLM (Nonlinear Iterative Method)-correction coupling coefficient. The new code system, ENTREE/ACCORD-N, has been developed in which both the polynomial and semi-analytical Legendre flux expansion functions have been implemented. The application to the two-dimensional homogeneous and heterogeneous cores that were created from the stability test point in Ringhals Unit 1 was demonstrated. The neutral line angle, eigenvalue and power shape obtained by the CCCMA were compared with those by the FDMA (Finite Difference Modal Analysis) of various mesh sizes. The CCCMA was shown to improve the solution accuracy significantly in the heterogeneous core. The ratios of the NLM-correction to FDM (Finite Difference Method) coupling coefficients in the fuel region gave a quantitative explanation of these trends. For the 1st azimuthal mode which is important in the regional instability analysis, the CCCMA produced almost the same level of accuracy as that of the (4×4) FDMA solution without any additional computational cost. The methodology has been also extended to include the discontinuity factor.
- 一般社団法人 日本原子力学会の論文
- 1999-11-25
著者
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Ninokata Hisashi
Research Lab. For Nuclear Reactors Tokyo Institute Of Technology
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Hotta Akitoshi
In-core Fuel Management Department Tepco Systems Corporation
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Hotta Akitoshi
In-core Fuel Management Department Toden Software Inc.
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TATE Katsumi
In-Core Fuel Management Department, Toden Software, Inc.
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Tate Katsumi
In-core Fuel Management Department Toden Software Inc.
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