An optimization approach to establish an appropriate energy group structure for BWR pin-by-pin core analysis

Fujita, Takayoshi; Tada, Kenichi; Endo, Takao; Yamamoto, Akio; Kosaka, Satoru; Hirano, Go; Nozaki, Kenichiro

doi:10.1080/00223131.2012.693890

Cited by 7 publications

(3 citation statements)

References 13 publications

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“…With the success of the approach for pressurized water reactors (PWRs) [14], applications to boiling water reactor (BWR) problems have also been studied; modeling of the pin-cell homogenized cross section [15] and its energy structure [16] are examined since there is strong intra-/inter-assembly heterogeneity in BWR configurations. Another approach is to enhance calculation methods for pin power distribution C 2014 Atomic Energy Society of Japan.…”

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confidence: 99%

Recent activities in the field of reactor physics

Tatsumi¹,

Chiba

2014

Journal of Nuclear Science and Technology

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confidence: 99%

Recent activities in the field of reactor physics

Tatsumi¹,

Chiba

2014

Journal of Nuclear Science and Technology

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“…Ref. [16]. The pin-cell averaged cross sections used in the present study are calculated by the HELIOS code in eight energy groups, which are collapsed from 47 energy groups [17].…”

Section: Calculation Conditions and Verification Approachesmentioning

confidence: 99%

A macroscopic cross-section model for BWR pin-by-pin core analysis

Fujita

Endo

Yamamoto

2013

Journal of Nuclear Science and Technology

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A macroscopic cross-section model used in boiling water reactor (BWR) pin-by-pin core analysis is studied. In the pin-by-pin core calculation method, pin-cell averaged cross sections are calculated for many combinations of core state and depletion history variables and are tabulated prior to core calculations. Variations of cross sections in a core simulator are caused by two different phenomena (i.e. instantaneous and history effects). We treat them through the core state variables and the exposure-averaged core state variables, respectively. Furthermore, the cross-term effect among the core state and the depletion history variables is considered. In order to confirm the calculation accuracy and discuss the treatment of the cross-term effect, the k-infinity and the pin-by-pin fission rate distributions in a single fuel assembly geometry are compared. Some cross-term effects could be negligible since the impacts of them are sufficiently small. However, the cross-term effects among the control rod history (or the void history) and other variables have large impacts; thus, the consideration of them is crucial. The present macroscopic cross-section model, which considers such dominant cross-term effects, well reproduces the reference results and can be a candidate in practical applications for BWR pin-by-pin core analysis on the normal operations.

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“…2) Furthermore, a theoretical approach to establishing the energy group structure has been studied. 9) As described above, the pin-by-pin BWR core analysis has been investigated from the viewpoint of performing transport and burnup calculations. However, the thermalhydraulics calculation had not been incorporated into the framework of our previous studies.…”

Section: Introductionmentioning

confidence: 99%

Application of Quick Subchannel Analysis Method for Three-Dimensional Pin-by-Pin BWR Core Calculations

Tada

Fujita

Endo

et al. 2011

Journal of Nuclear Science and Technology

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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.

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An optimization approach to establish an appropriate energy group structure for BWR pin-by-pin core analysis

Cited by 7 publications

References 13 publications

Recent activities in the field of reactor physics

Recent activities in the field of reactor physics

A macroscopic cross-section model for BWR pin-by-pin core analysis

Application of Quick Subchannel Analysis Method for Three-Dimensional Pin-by-Pin BWR Core Calculations

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