• Journal of Korean Academy of Nursing
• /
• v.49 no.1
• /
• pp.92-103
• /
• 2019

Purpose: This study aimed to compare the effects of simulation integrated with problem based learning (S-PBL) according to the sequences of problem-based learning (PBL) and high fidelity simulation training (HFS) on knowledge, clinical performance, clinical judgment, self-confidence, and satisfaction in fourth-grade nursing students. Methods: In this randomized crossover design study, four S-PBLs on medical-surgical nursing were applied alternatively to two randomly-assigned groups of 26 senior nursing students for 8 weeks. The collected data were analyzed using an independent t-test. Results: The method of administering PBL prior to HFS led to significantly higher scores on knowledge (t=2.28, p=.025) as compared to the method of administering HFS prior to PBL. However, the latter method led to significantly higher scores on clinical performance (t=-6.49, p<.001) and clinical judgment (t=-4.71, p<.001) as compared to the method of administering PBL prior to HFS. There were no differences in the effect of the two methods on self-confidence (t=1.53, p=.128) and satisfaction (t=1.28, p=.202). Conclusion: The integration sequences of S-PBL was associated with different learning outcomes. Therefore, when implementing S-PBL, it is necessary to consider the educational goal to executes an appropriate sequence of integration.

• Nuclear Engineering and Technology
• /
• v.55 no.9
• /
• pp.3301-3312
• /
• 2023

This study incorporates a high-fidelity transient analysis solver based on multigroup CMFD in the MOC code STREAM. Transport modeling with heterogeneous geometries of the reactor core increases computational cost in terms of memory and time, whereas the multigroup CMFD reduces the computational cost. The reactor condition does not change at every time step, which is a vital point for the utilization of CMFD. CMFD correction factors are updated from the transport solution whenever the reactor core condition changes, and the simulation continues until the end. The transport solution is adjusted once CMFD achieves the solution. The flux-weighted method is used for rod decusping to update the partially inserted control rod cell material, which maintains the solution's stability. A smaller time-step size is needed to obtain an accurate solution, which increases the computational cost. The adaptive step-size control algorithm is robust for controlling the time step size. This algorithm is based on local errors and has the potential capability to accept or reject the solution. Several numerical problems are selected to analyze the performance and numerical accuracy of parallel computing, rod decusping, and adaptive time step control. Lastly, a typical pressurized LWR was chosen to study the rod-ejection accident.

• Nuclear Engineering and Technology
• /
• v.55 no.9
• /
• pp.3493-3505
• /
• 2023

Reactor containment buildings serve as the last barrier to prevent radioactive leakage due to accidents and their safety is crucial in overpressurization conditions. Thus, the Regulatory Guide (RG) 1.216 has mentioned the global strain as one of failure criteria in the free-field for cylindrical prestressed concrete containment vessels (PCCV) subject to internal pressure. However, there is a limit that RG 1.216 shows the free-field without the specific locations of failure criteria and also the global strain corresponding to only azimuth 135° has been mentioned in NUREG/CR-6685, regardless of the elevations of the structure. Therefore, in order to reevaluate the failure criteria of the 1:4 scaled PCCV, the high fidelity simulation model based on the experimental test was significantly validated in this study, and it was interesting to find that the experimental and numerical result was very close to each other. In addition, for the consideration of the material uncertainties, the Latin hypercube method was used as a statistical approach. Consequently, it was revealed that the radial displacements of various azimuth area such as 120°, 135°, 150°, 180° and 210° at elevations 4680 mm and 6,200 mm can represent as the global deformation at the free-field, obtained from the statistical approach.

• Journal of Korean Clinical Health Science
• /
• v.12 no.1
• /
• pp.1678-1688
• /
• 2024

Purpose: This study was conducted to explore the experiences of nursing students who participated in the pneumonia and pleural effusion using web-based virtual reality and high-fidelity simulation. Methods: This study is qualitative study using inductive content analysis. We developed simulation scenario regarding pneumonia and pleural effusion. Eleven nursing students who participated in simulation were interviewed between June 20 to August 25, 2022. The interviews were transcribed and analyzed according to the inductive content analysis. Results: The results were analyzed into three key categories: 'pre-learning and psychological burden before simulation','increased learning satisfaction','improved clinical performance'. Conclusions: Participants was able to integrate their previous experience, including clinical practice experiences, web-based virtual simulation, into high-fidelity simulation and effectively enhanced their learning experience. Therefore, when providing various types of simulation simultaneously, it is necessary to take into account the prior students' experiences and to organize simulation education by considering the characteristics of simulation.

• Nuclear Engineering and Technology
• /
• v.56 no.2
• /
• pp.359-374
• /
• 2024

A high-fidelity numerical analysis methodology was proposed for evaluating the fuel rod cladding integrity of a Prototype Gen IV Sodium Fast Reactor (PGSFR) during normal operation and Design basis events (DBEs). The MARS-LMR code, system transient safety analysis code, was applied to analyze the DBEs. The results of the MARS-LMR code were used as boundary condition for a 3D computational fluid dynamics (CFD) analysis. The peak temperatures considering HCFs satisfied the cladding temperature limit. The temperature and pressure distributions were calculated by ANSYS CFX code, and applied to structural analysis. Structural analysis was performed using ANSYS Mechanical code. The seismic reactivity insertion SSE accident among DBEs had the highest peak cladding temperature and the maximum stress, as the value of 87 MPa. The fuel cladding had over 40 % safety margin, and the strain was below the strain limit. Deformation behavior was elucidated for providing relative coordinate data on each active fuel rod center. Bending deformation resulted in a flower shape, and bowing bundle did not interact with the duct of fuel assemblies. Fuel rod maximum expansion was generated with highest stress. Therefore, it was concluded that the fuel rod cladding of the PGSFR has sufficient structural safety margin during DBEs.

• Proceedings of the Korea Information Processing Society Conference
• /
• 2008.11a
• /
• pp.1314-1315
• /
• 2008

Recent research work has unearthed that multi-radio multi-channel wireless mesh networks offer considerable capacity gains over single-radio wireless mesh networks. In this paper, we present a new routing metric for multi-radio multi-channel wireless mesh networks. The goal of the metric is to choose multiple link/node disjoint paths between a source and destination node that, when used concomitantly, impart high end-to-end throughput. The proposed metric selects high fidelity paths that will produce elevated throughput with maximum fault tolerance.

• Nuclear Engineering and Technology
• /
• v.56 no.4
• /
• pp.1310-1319
• /
• 2024

The reactor cavity cooling system (RCCS) is a passive reactor safety system commonly present in the designs of High-Temperature Gas-cooled Reactors (HTGR) that removes heat from the reactor pressure vessel by means of natural convection and radiation. It is one of the factors responsible for ensuring that the reactor does not melt down under any plausible accident scenario. For the simulation of accident scenarios, which are transient phenomena unfolding over a span of up to several days, intermediate fidelity methods and system codes must be employed to limit the models' execution time. These models can quantify radiation heat transfer well, but heat transfer caused by natural convection must be quantified with the use of correlations for the heat transfer coefficient. It is difficult to obtain reliable correlations for HTGR RCCS heat transfer coefficients experimentally due to such a system's size. They could, however, be obtained from high-fidelity steady-state simulations of RCCSs. The Rayleigh number in RCCSs is too high for using a Direct Numerical Simulation (DNS) technique; thus, a Reynolds-Averaged Navier-Stokes (RANS) approach must be employed. There are many RANS models, each performing best under different geometry and fluid flow conditions. To find the most suitable one for simulating an RCCS, the RANS models need to be validated. This work benchmarks various RANS models against three experiments performed on the HTTR RCCS Mockup by the Japanese Atomic Energy Agency (JAEA) in 1993. This facility is a 1/6 scale model of a vessel cooling system (VCS) for the High Temperature Engineering Test Reactor (HTTR), which is operated by JAEA. Multiple RANS models were evaluated on a simplified 2d-axisymmetric geometry. They were found to reproduce the experimental temperature profiles with errors of up to 22% for the lowest temperature benchmark and 15% for the higher temperature benchmarks. The results highlight that the pragmatic turbulence models need to be validated for high Rayleigh natural convection-driven flows and improved accordingly, more publicly available experimental data of RCCS resembling experiments is needed and indicate that a 2d-axisymmetric geometry approximation is likely insufficient to capture all the relevant phenomena in RCCS simulations.

• The Korea Journal of Herbology
• /
• v.34 no.6
• /
• pp.1-23
• /
• 2019

Objectives : The purpose of this study was to document the use of medicinal plants in traditional practices and to analyze and evaluate medicinal traditional knowledge of indigenous people in Wolchulsan National Park. Methods : Data were collected through interviews, informal meetings, open and group discussions, and observations guided by semi-structured questionnaires. Data were analyzed via quantitative analysis of use value (UV), informant consensus factor (ICF) and fidelity level (FL), and network analysis. Results : A total of 580 methods of usage recorded in this study were classified into 55 families, 95 genera, and 104 species. Plants with the highest recorded UVs were Glycine max (L.) Merr., Leonurus japonicus Houtt., and Artemisia princeps Pamp.. The informant consensus factor about using medicinal plants ranged from 0.55 to 0.92, which showed a high level of agreement among the informants on respiratory system disorders and pains. There were 22 species of plants with a fidelity level of 100 %, after eliminating the plants that were mentioned only once from the analysis. Finally, using network analysis, Glycine max (L.) Merr. and Artemisia princeps Pamp. were defined as species with meaningful medicinal use, while lumbago and leg pain were defined as significant ailments in the study area. Conclusions : This study highlights the diversity and importance of medicinal traditional knowledge for communities of Wolchulsan National Park, Korea. The results of this study will provide basic data for phytochemical and pharmaceutical studies, such as new medicines and therapies.

• Nuclear Engineering and Technology
• /
• v.55 no.9
• /
• pp.3450-3463
• /
• 2023

In the two-step analysis of Pebble-Bed type High-Temperature Gas-Cooled Reactor (PB-HTGR), the lattice physics calculation for the generation of homogenized cross-sections is based on the fuel pebble. However, the randomly-dispersed fuel particles in the fuel pebble introduce double heterogeneity and randomness. Compared to the deterministic method, the Monte Carlo method which is flexible in geometry modeling provides a high-fidelity treatment. Therefore, the Monte Carlo code NECP-MCX is extended in this study to perform the lattice physics calculation of the PB-HTGR. Firstly, the capability for the simulation of randomly-dispersed media, using the explicit modeling approach, is developed in NECP-MCX. Secondly, the capability for the generation of the homogenized cross-section is also developed in NECP-MCX. Finally, simplified PB-HTGR problems are calculated by a two-step neutronics analysis tool based on Monte Carlo homogenization. For the pebble beds mixed by fuel pebble and graphite pebble, the bias is less than 100 pcm when compared to the high-fidelity model, and the bias is increased to 269 pcm for pebble bed mixed by depleted fuel pebble. Numerical results show that the Monte Carlo lattice physics calculation for the two-step analysis of PB-HTGR is feasible.

• Proceedings of the Korean Institute of Information and Commucation Sciences Conference
• /
• 1999.05a
• /
• pp.425-431
• /
• 1999

We develope plasma monitoring system which detect plasma signals and store them for Laser welding quality evaluation and analysis using photo detector. The most fundamental and important aspects in such a system are signal restoration fidelity, noise immunity and noise cancelation capability. In this paper, we propose implementation method using distribute processing structure and hybrid digital communication for high noise cancelation capability, immunity and signal fidelity which are poorly presented in other researches. Lab experimental results and welding experimental results show a effectiveness of proposed method and plasma data is stored with 256 kbps without any communication error. we are implementing various welding defect recognition algorithm in this system.