Three-Dimensional Direct Response Matrix Method Using a Monte Carlo Calculation

Ishii, Kazuya; Hino, T.; Mitsuyasu, Takeshi; Aoyama, Motoo

doi:10.3327/jnst.46.259

Cited by 6 publications

(7 citation statements)

References 2 publications

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“…(1) includes a summation that continues fo number of generation grow in number. 2 Thus, the summa tions can be limited to a practical number of gene…”

Section: Formalization Of 3d-drmmentioning

confidence: 99%

Computing Acceleration for a Pin-by-Pin Core Analysis Method Using a Three-Dimensional Direct Response Matrix Method

Mitsuyasu

Ishii

Hino

2011

Progress in Nuclear Science and Technology

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“…(1) includes a summation that continues fo number of generation grow in number. 2 Thus, the summa tions can be limited to a practical number of gene…”

Section: Formalization Of 3d-drmmentioning

confidence: 99%

Computing Acceleration for a Pin-by-Pin Core Analysis Method Using a Three-Dimensional Direct Response Matrix Method

Mitsuyasu

Ishii

Hino

2011

Progress in Nuclear Science and Technology

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“…5) (1) Transmission probability (T ii,gi!io,go ): the probability that a neutron entering from the ii'th face at the gi'th group will eventually exit from the io'th face at the go'th group. (2) Neighbor-induced production probability (S ii,gi!je,m ): the expected number of neutrons born in the axial zone, m, of the fuel rod, je, by the fission reaction of a neutron entering from the ii'th face at the gi'th group.…”

Section: Evaluation Of Three-dimensional Direct Response Matrixmentioning

confidence: 99%

“…[4][5][6][7][8] The basic idea underlying the 3D-DRM is to classify neutron behaviors in a fuel assembly into four fundamental reaction processes: (1) transmission across the fuel assembly; (2) neutron production by neighbor-induced, or (3) self-induced neutrons; and (4) neutrons escaping from the fuel assembly. These four reaction processes are represented by and correspond to four types of subresponse matrices.…”

Section: Introductionmentioning

confidence: 99%

BWR Core Simulator Using Three-Dimensional Direct Response Matrix and Analysis of Cold Critical Experiments

Hino¹,

Ishii²,

Mitsuyasu³

et al. 2010

J. Nucl. Sci. Technol.

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A new core analysis method has been developed in which neutronic calculations using a three-dimensional direct response matrix (3D-DRM) method are coupled with thermal-hydraulic calculations. As it requires neither a diffusion approximation nor a homogenization process of lattice constants, a precise representation of the neutronic heterogeneity effect in an advanced core design is possible. Moreover, the pin-by-pin power distribution can be directly evaluated, which enables precise evaluations of core thermal margins. Verification of the neutronic calculation using the 3D-DRM method was examined by analyses of cold criticality experiments of commercial power plants. The standard deviations and maximum differences in predicted neutron multiplication factors were 0.07%Ák and 0.19%Ák for a BWR5 plant, and 0.11%Ák and 0.25%Ák for an ABWR plant, respectively. A coupled analysis of the 3D-DRM method and thermal-hydraulic calculations for a quarter ABWR core was done, and it was found that the thermal power and coolant-flow distributions were smoothly converged.

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“…These subresponse matrices are illustrated in Fig. 1 and defined 4) as follows. (1) Transmission probability (T ii;gi!io;go ): the probability that a neutron entering from the ii-th face at the gi-th group eventually exits to the io-th face at the go-th group.…”

Section: D-drm Methodsmentioning

confidence: 99%

Development of Spectral History and Pin Power Correction Methods for Pin-by-Pin Core Analysis Method Using Three-Dimensional Direct Response Matrix

Mitsuyasu

Ishii

Hino

et al. 2010

J. Nucl. Sci. Technol.

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Spectral history and pin power correction methods have been developed for the pin-by-pin core analysis method using the three-dimensional direct response matrix (3D-DRM). The direct response matrix is formalized using four subresponse matrices in order to respond to a core eigenvalue k and thus it can be recomposed at each outer iteration in the core analysis. For core analysis, it is necessary to take into account the historical effect, which is related to spectral heterogeneity. The spectral history method is used to evaluate the nodal burn-up spectrum obtained by using the outgoing neutron current instead of the nodal flux because the 3D-DRM method does not use the nodal flux. The pin power correction method corrects the fuel rod neutron production rates obtained in the pin-by-pin calculation. These two methods were tested in a heterogeneous system. The test results show that the neutron multiplication factor error and nodal neutron production rate errors can be reduced by half during burn-up. The root-mean-square differences between the relative fuel rod neutron production rate distributions and the maximum error of relative fuel rod production rate can also be reduced by half. This means that the developed methods can reflect the effects of intra-and interassembly heterogeneities during burn-up and can be used for core analysis.

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Three-Dimensional Direct Response Matrix Method Using a Monte Carlo Calculation

Cited by 6 publications

References 2 publications

Computing Acceleration for a Pin-by-Pin Core Analysis Method Using a Three-Dimensional Direct Response Matrix Method

Computing Acceleration for a Pin-by-Pin Core Analysis Method Using a Three-Dimensional Direct Response Matrix Method

BWR Core Simulator Using Three-Dimensional Direct Response Matrix and Analysis of Cold Critical Experiments

Development of Spectral History and Pin Power Correction Methods for Pin-by-Pin Core Analysis Method Using Three-Dimensional Direct Response Matrix

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