Application of Quick Subchannel Analysis Method for Three-Dimensional Pin-by-Pin BWR Core Calculations
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概要
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Three-dimensional pin-by-pin core analysis is considered to be a candidate for the next-generation BWR core calculation method. In our previous study, the applicability of the transport and burnup calculations for a three-dimensional pin-by-pin BWR core analysis was investigated. However, the thermal-hydraulics calculation has not yet been studied in this framework. In the conventional core analysis code, the bundlewise thermal-hydraulics calculation is adopted. In the actual core analysis, the power distribution inside a fuel assembly is tilted at the region adjacent to a control blade or the core peripheral region. In these regions, the consideration of the subchannel-wise void distribution has an impact on the fission rate distribution. Therefore, an evaluation of the detailed void distribution inside an assembly, i.e., the incorporation of the subchannel wise void distribution, is desirable for the pin-by-pin BWR core analysis. Although several subchannel analysis codes have been developed, these subchannel analysis codes generally require a large computational effort to estimate the subchannel-wise void distribution in a whole BWR core. Therefore, to analyze a whole BWR core within a reasonable computation time, it was necessary to apply a fast subchannel analysis code. In this paper, a quick subchannel analysis code dedicated to pin-by-pin BWR core analysis is newly developed, and the void distribution of the present subchannel analysis code is compared with the prevailing subchannel analysis code NASCA using three-dimensional single-assembly geometries. Since the present subchannel analysis code is used for a coupled neutronics/thermal-hydraulics analysis, the results of the coupling calculation are also compared with those of NASCA. The calculation result indicates that the void distribution difference between NASCA and the present subchannel analysis code is slightly less than 10%. This result indicates that the prediction accuracy of the present subchannel analysis code will be reasonably appropriate for a pin-by-pin BWR core analysis. Furthermore, the results show that the calculation time of the present subchannel analysis code is only 10 min for a hypothetical three-dimensional ABWR quarter-core geometry using a single CPU. This calculation time is sufficient for a pin-by-pin BWR core analysis.
- 一般社団法人 日本原子力学会の論文
- 2011-12-01
著者
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Tada Kenichi
Physics And Energy Engineering Department Of Materials Graduate School Of Engineering Nagoya Univers
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KOSAKA Shinya
TEPCO Systems Corporation
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Endo Tomohiro
Dep. Of Material Physics And Energy Engineering Graduate School Of Engineering Nagoya Univ.
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Endo Tomohiro
Department Of Material Physics And Energy Engineering Graduate School Of Engineering Nagoya Universi
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Yamamoto Akio
Dep. Of Material Physics And Energy Engineering Graduate School Of Engineering Nagoya Univ.
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Yamamoto Akio
Department Of Material Physics And Energy Engineering Graduate School Of Engineering Nagoya Universi
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Endo Tomohiro
Department Of Functional Radiation Sciences Hoshi University
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TADA Kenichi
Department of Materials, Physics and Energy Engineering, Graduate School of Engineering, Nagoya Univ
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FUJITA Tatsuya
Department of Materials, Physics and Energy Engineering, Graduate School of Engineering, Nagoya Univ
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HIRANO Go
TEPCO Systems Corporation, Shibusawa City Place Eitai
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NOZAKI Kenichiro
TEPCO Systems Corporation, Shibusawa City Place Eitai
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Yamamoto Akio
Department Of Applied Chemistry Graduate School Of Science And Engineering And Advanced Research Cen
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Hirano Go
Tepco Systems Corporation
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Nozaki Kenichiro
Tepco Systems Corporation
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Fujita Tatsuya
Department Of Materials Physics And Energy Engineering Graduate School Of Engineering Nagoya University
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