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

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

doi:10.1080/18811248.2010.9711639

Cited by 7 publications

(4 citation statements)

References 5 publications

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“…In the first case, there were four angular segments and three energy groups. These numbers were equal to those in the analysis of cold critical experiments of commercial plants [6]. In the second case, there were 16 angular segments and three energy groups, and in the third case, there were 16 and nine, respectively.…”

Section: Analysis Processmentioning

confidence: 99%

“…Each fuel rod had four axial zones in a node the height of which was 100 mm. These numbers of sub-surfaces and fuel rod axial zones were equal to those in the analysis of cold critical experiments of commercial power plants [6]. Three cases were calculated about the numbers of angular segments for each sub-surface and energy groups in consideration that the size of the BASALA experimental cores were much smaller than that of commercial power plants.…”

Section: Analysis Processmentioning

confidence: 99%

“…To verify the pin-by-pin core analysis method using the three-dimensional direct response matrix, Hino et al [6] carried out an analysis of cold critical experiments for commercial power plants. They obtained standard deviations and maximum differences in the evaluated critical k-effective values of 0.07% Dk and 0.19% Dk for a BWR5 plant, and 0.11% Dk and 0.25% Dk for an ABWR plant, respectively.…”

Section: Introductionmentioning

confidence: 99%

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Analysis of the MOX critical experiments BASALA by pin-by-pin core analysis method using three-dimensional direct response matrix

Ishii

Mitsuyasu

Hino

et al. 2012

Journal of Nuclear Science and Technology

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An analysis of the MOX critical experiments BASALA was performed to verify the pin-by-pin core analysis method using a three-dimensional direct response matrix. The BASALA experiments simulate full MOX BWR cores, and they were carried out in the EOLE critical facility of the French Atomic Energy Commission (CEA) by the Nuclear Power Engineering Corporation (NUPEC) in collaboration with CEA. The BASALA experimental cores are very heterogeneous because their size is much smaller than that of commercial power plants. The main features of the pin-by-pin core analysis method using the three-dimensional direct response matrix are that the response matrix can reflect the intra-assembly heterogeneous effect, the diffusion approximation is not involved, and the fuel rod fission rate can be directly evaluated. The maximum difference of the critical k-effective values among all nine cores analyzed was about 0.4% Dk. The root mean square differences between the calculated and measured radial fuel rod fission rate distributions in the test assembly of all cores were within 1.8% and nearly comparable to measurement error. The calculated results of the reactivity worth agreed with the measured results within 9%. These good agreements mean that the pin-by-pin core analysis method using the three-dimensional direct response matrix accurately reflects the effects of the intra-and inter-assembly heterogeneities in heterogeneous systems like the BASALA experimental cores.

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Section: Analysis Processmentioning

confidence: 99%

Section: Analysis Processmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Analysis of the MOX critical experiments BASALA by pin-by-pin core analysis method using three-dimensional direct response matrix

Ishii

Mitsuyasu

Hino

et al. 2012

Journal of Nuclear Science and Technology

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“…Parameterization becomes even more difficult if burnup is included for cycle analyses. Recent work has attempted to parameterize the responses for steady-state analysis of cold critical experiments [19]. While the results are promising (sub-percent errors on pin fission rates), the problem assessed is not entirely representative of the current problems of interest.…”

Section: Major Challengementioning

confidence: 99%

Solving eigenvalue response matrix equations with nonlinear techniques

Roberts

Forget

2014

Annals of Nuclear Energy

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This paper presents new algorithms for use in the eigenvalue response matrix method (ERMM) for reactor eigenvalue problems. ERMM spatially decomposes a domain into independent nodes linked via boundary conditions approximated as truncated orthogonal expansions, the coefficients of which are response functions. In its simplest form, ERMM consists of a two-level eigenproblem: an outer Picard iteration updates the k-eigenvalue via balance, while the inner λ-eigenproblem imposes neutron balance between nodes. Efficient methods are developed for solving the inner λ-eigenvalue problem within the outer Picard iteration. Based on results from several diffusion and transport benchmark models, it was found that the Krylov-Schur method applied to the λ-eigenvalue problem reduces Picard solver times (excluding response generation) by a factor of 2-5. Furthermore, alternative methods, including Picard acceleration schemes, Steffensen's method, and Newton's method, are developed in this paper. These approaches often yield faster k-convergence and a need for fewer k-dependent response function evaluations, which is important because response generation is often the primary cost for problems using responses computed online (i.e., not from a precomputed database). Accelerated Picard iteration was found to reduce total computational times by 2-3 compared to the unaccelerated case for problems dominated by response generation. In addition, Newton's method was found to provide nearly the same performance with improved robustness.

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A coupling model for the two-stage core calculation method with subchannel analysis for boiling water reactors

Mitsuyasu

Aoyama

Yamamoto

2017

Annals of Nuclear Energy

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

Cited by 7 publications

References 5 publications

Analysis of the MOX critical experiments BASALA by pin-by-pin core analysis method using three-dimensional direct response matrix

Analysis of the MOX critical experiments BASALA by pin-by-pin core analysis method using three-dimensional direct response matrix

Solving eigenvalue response matrix equations with nonlinear techniques

A coupling model for the two-stage core calculation method with subchannel analysis for boiling water reactors

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