• Journal of Distribution Science
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• v.20 no.1
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• pp.67-76
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• 2022

Purpose: The purpose is to verify the impact of the store environment on interpersonal service quality (ISQ), shopping value and patronage intention, as well as the moderating role of the store format: supermarkets vs hypermarkets. This is significant as previous studies on retailing neglected the effect of interpersonal service quality on the experiential shopping value. The comparison of the model between two retailing formats (hypermarkets and supermarkets) provides a significant contribution and responds to a need to provide insights regarding the moderation of the store types on the contribution of interpersonal service quality and experiential value to customer's retention. Research design, data, and methodology: The hypotheses have been tested after analyzing the data of a survey among 405 consumers exiting stores representing various retailing stores in Tunisia. A Structural model have been finally verified by a path analysis after applying a confirmatory factorial analysis. Multigroup analyses on AMOS allowed to verify the moderation of store types. Results: Results mainly show that patronage intention is affected by the experiential perceived value dimensions. The latter is a direct consequence of ISQ and an indirect outcome of perceived shopping environment. The impact of value, environment and ISQ is moderated by the store type.

• Nuclear Engineering and Technology
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• v.55 no.7
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• pp.2474-2482
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• 2023

The development of fast reactors with complex designs and operation status requires more accurate and effective simulation. The Monte-Carlo method can generate multi-group cross-sections in arbitrary geometry without approximation on resonances treatment and leads to good results in combination with diffusion codes. However, in previous studies, the coupling of Monte-Carlo generated multi-group cross-sections (MC-MGXS) and transport solvers has shown relatively large biases in fast reactor problems. In this paper, the main contribution to the biases is proved to be the neglect of the angle-dependence of the total cross-sections. The flux-moment homogenization technique (MHT) is proposed to take into account this dependence. In this method, the angular dependence is attributed to the transfer cross-sections, keeping an independent form for the total sections. For the MET-1000 benchmark, the multi-group transport simulation results with MC-MGXS generated with MHT are improved by 700 pcm and an additional 120 pcm with higher order scattering. The factors that cause the residual bias are discussed. The core power distribution bias is also significantly reduced when MHT is used. It proves that the MCMGXS with MHT can be applicable with transport solvers in fast reactor analysis.

• Science of Emotion and Sensibility
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• v.9 no.1
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• pp.19-26
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• 2006

In this research, a theoretical model indicating the influence of fragrance sensibility response on attitude toward and buying intention of scented textile products was tested. On-line survey data was collected from a total of 530 consumers who have used or purchased scented textile products. In results, gender differences were found in the multigroup analysis using Structural Equation Modeling. In the model of females, pleasantness, stimulating, familiarity and congruency of scent affected attitude toward scented textile products while pleasantness was only a factor influencing attitude toward scented textile products in the model of males. In addition, pleasantness was the most important factor for Two genders although males indicated a higher level of buying intention toward scented textile products.

• Nuclear Engineering and Technology
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• v.21 no.4
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• pp.245-258
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• 1989

A 69-group cross section library consisting of more than 130 materials was generated for thermal reactor applications using the NJOY nuclear data processing system and the recent version of evaluated nuclear data files available from IAEA Nuclear Data Section. The multigroup library was validated through the analysis of various criticality experiments and depletion results of PWR. When used with the WIMS-KAERI code, the average $K_{eff}$ obtained for 47 uranium-oxide and 41 uranium metal fueled critical configurations is 0.9997 with a standard deviation of 0.69 percent. The calculated burnup dependent isotopic inventories of uranium and plutonium generally show good agreement with measured values obtained from depleted PWR pins.s.

• Korean Journal of Child Studies
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• v.38 no.2
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• pp.191-204
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• 2017

Objective: The purpose of this study was to explore the structural relationships among duration of media use, behavior problems, and school adjustment, while accounting for gender differences. Methods: The study used 4th-wave panel data from the Korean Children and Youth Panel Study, and 2,119 first graders in elementary school were analyzed. The data were analyzed using Structural Equation Modeling. Results: The results can be summarized as follows. First, the duration of media use had a direct effect on school adjustment. Secondly, the duration of media use had an indirect effect on school adjustment through internalizing and externalizing problems. According to multigroup analysis, gender differences were found in the structural relations among variables. Conclusion: This study emphasizes the needs for media usage education to improve children's school adjustment. Furthermore, it suggests that different intervention strategies for internalizing/externalizing behavior problems are needed depending on gender.

• Nuclear Engineering and Technology
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• v.49 no.1
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• pp.43-53
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• 2017

Increasing the operation cycle length can be an important goal in the fuel reload design of a nuclear reactor core. In this research paper, a new optimization approach, electromagnetism mechanism (EM), is applied to the fuel arrangement design of the Bushehr WWER-1000 core. For this purpose, a neutronic solver has been developed for calculating the required parameters during the reload cycle of the reactor. In this package, two modules have been linked, including PARCS v2.7 and WIMS-5B codes, integrated in a solver for using in the fuel arrangement optimization operation. The first results of the prepared package, along with the cycle for the original pattern of Bushehr WWER-1000, are compared and verified according to the Final Safety Analysis Report and then the results of exploited EM linked with Purdue Advanced Reactor Core Simulator (PARCS) and Winfrith Improved Multigroup Scheme (WIMS) codes are reported for the loading pattern optimization. Totally, the numerical results of our loading pattern optimization indicate the power of the EM for this problem and also show the effective improvement of desired parameters for the gained semi-optimized core pattern in comparison to the designer scheme.

• Journal of the Korean Society of Clothing and Textiles
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• v.45 no.4
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• pp.714-726
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• 2021

The purpose of this study is to investigate the effect of retail therapy (RT) values and the role of body consciousness on therapeutic shopping motivations and outcomes. In order to accomplish our research aim, we investigated therapeutic shopping values (i.e., positive mood reinforcement and negative mood reduction) and the moderating effects of body surveillance, body shame, and weight preoccupation. A total of 247 female college students in the United States participated in an online Qualtrics survey, and structural equation modeling (SEM) and multigroup analysis were performed to analyze the data. The findings reveal that therapeutic shopping values (positive mood reinforcement and negative mood reduction) significantly influence therapeutic shopping motivation. Therapeutic shopping motivation, in turn, positively influences therapeutic shopping outcomes. Moreover, weight preoccupation moderates the relationship between negative mood reduction and therapeutic shopping motivation, suggesting that RT should especially be utilized for weight-conscious individuals. The results can be utilized for retailers to develop marketing strategies for consumers who are conscious about their appearance. Academic and managerial implications, along with future research, are suggested.

• Nuclear Engineering and Technology
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• v.54 no.12
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• pp.4731-4742
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• 2022

RBMK fuel assemblies differ from other LWR FA due to a specific arrangement of the fuel rods, the low enrichment, and the used burnable absorber - erbium. Therefore, there is a challenge to adapt modeling tools, developed for other LWR types, to solve RBMK problems. A set of 10 different depletion simulation schemes were tested to estimate the impact on reactivity and spent fuel composition of possible SCALE code options for the neutron transport modelling and the use of different nuclear data libraries. The simulations were performed using cross-section libraries based on both, VII.0 and VII.1, versions of ENDF/B nuclear data, and assuming continuous energy and multigroup simulation modes, standard and user-defined Dancoff factor values, and employing deterministic and Monte Carlo methods. The criticality analysis with burn-up credit was performed for the SFP loaded with RBMK-1500 FA. Spent fuel compositions were taken from each of 10 performed depletion simulations. The criticality of SFP is found to be overestimated by up to 0.08% in simulation cases using user-defined Dancoff factors comparing the results obtained using the continuous energy library (VII.1 version of ENDF/B nuclear data). It was shown that such discrepancy is determined by the higher U-235 and Pu-239 isotopes concentrations calculated.

• Nuclear Engineering and Technology
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• v.55 no.11
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• pp.4048-4056
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• 2023

The feasibility of using the Monte Carlo code MCS to generate multigroup cross sections for nodal diffusion simulations RAST-F of liquid metal fast reactors is investigated in this paper. The performance of the MCS/RAST-F code system is assessed using steady-state simulations of the ANTS-100e core. The results show good agreement between MCS/RAST-F and MCS reference solutions, with a keff difference of less than 77 pcm and root-mean-square differences in radial and axial power of less than 0.5% and 0.25%, respectively. Furthermore, the MCS/RAST-F reactivity feedback coefficients are within three standard deviations of the MCS coefficients. To validate the internal thermal-hydraulic (TH) feedback capability in RAST-F code, the coupled neutronic/TH1D simulation of ANTS-100e is performed using the case matrix obtained from MCS branch calculations. The results are compared to those obtained using the MARS-LBE system code and show good agreement with relative temperature differences in fuel and coolant of less than 0.8%. This study demonstrates that the MCS/RAST-F code system can produce accurate results for core steady-state neutronic calculations and for coupled neutronic/TH simulations.

• Nuclear Engineering and Technology
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• v.55 no.4
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• pp.1563-1570
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• 2023

In this study, a DeCART/MIG uncertainty quantification (UQ) analysis code system with a multicorrelated cross section stochastic sampling (S.S.) module was established and verified through the UAM (Uncertainty Analysis in Modeling) and the BEAVRS (Benchmark for Evaluation And Validation of Reactor Simulations) benchmark calculations. For the S.S. calculations, a sample of 500 DeCART multigroup cross section sets for two major actinides, i.e., ²³⁵U and ²³⁸U, were generated by the MIG code and covariance data from the ENDF/B-VII.1 evaluated nuclear data library. In the three pin problems (i.e. TMI-1, PB2, and Koz-6) from the UAM benchmark, the uncertainties in k_inf by the DeCART/MIG S.S. calculations agreed very well with the sensitivity and uncertainty (S/U) perturbation results by DeCART/MUSAD and the S/U direct subtraction (S/U-DS) results by the DeCART/MIG. From these results, it was concluded that the multi-group cross section sampling module of the MIG code works correctly and accurately. In the BEAVRS whole benchmark problems, the uncertainties in the control rod bank worth, isothermal temperature coefficient, power distribution, and critical boron concentration due to cross section uncertainties were calculated by the DeCART/MIG code system. Overall, the uncertainties in these design parameters were less than the general design review criteria of a typical pressurized water reactor start-up case. This newly-developed DeCART/MIG UQ analysis code system by the S.S. method can be widely utilized as uncertainty analysis and margin estimation tools for developing and designing new advanced nuclear reactors.