• Title/Summary/Keyword: technology level evaluation

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Factors Affecting the Usage of an ERP System in Operation : A Socio-technical View with User Orientation (운영 중인 ERP 시스템의 활용도에 영향을 미치는 요인에 관한 연구 : 사용자 중심의 통합된 사회-기술적 관점에서)

  • Cho, Eun-Kyong;Min, Dai-Hwan
    • Journal of Information Technology Services
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    • v.9 no.2
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    • pp.129-149
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    • 2010
  • Although many organizations have implemented and used ERP systems for years, industry reports point out that the usage level does not reach their expectation. As a result, they do not enjoy the benefits from the investment into ERP systems. This study attempts to develop a research model and test the model empirically for identifying factors that affect the usage of an ERP system at a public organization. This study has classified potential factors into three groups of technical system characteristics (usability, usefulness), organizational support characteristics (operational support, education and training, evaluation and measurement), and user characteristics (organizational citizenship, self-efficacy). Then, a structural equation model has been established on the basis of previous literature and tested with empirical data. In summary, this study has found that self-efficacy, usefulness, and operational support have an effect on the ERP usage. Self-efficacy is the strongest factor; Usefulness is the second; and the third is operational support. On the contrary to the previous literature, this study has not found a significant effect of organizational citizenship on the usage. The result confirms that an organization can increase the ERP usage by improving the usefulness of an ERP system to some extent. However, to boost the usage further, the result implies that organizations need to strengthen the self-efficacy of their members by reinforcing operational support, providing education and training steadily, and establishing an evaluation mechanism in relation with the ERP usage.

The Quality Characteristics of Bacsulgi with Sea Mustard((Undaria pinnatifida) powder (미역 가루를 첨가한 백설기의 품질특성)

  • Jun, Na-Young;Kim, Sung-Ok;Han, Jin-Suk
    • Korean journal of food and cookery science
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    • v.22 no.5 s.95
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    • pp.591-599
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    • 2006
  • The purpose of this study was to investigate the effect of the addition of various concentrations of sea mustard powder on the quality characteristics of Bacsulgi. The sea mustard powder was added to rice powder at ratios of 3, 5, 7, and 9%(w/w). The moisture contents and salinity of Bacsulgi were increased with the addition of sea mustard powder. The incorporation of sea mustard powder in Bacsulgi lowered the lightness values but increased the blueness and yellowness values. Rheology test showed that hardness was significantly (p<0.05) decreased with increasing sea mustard powder content. The springiness and cohesiveness were decreased, whereas the adhesiveness was increased, with increasing sea mustard powder content. Scanning electron microscopy showed that the size of the air cells increased and the surface of rice powder swelled with increasing sea mustard powder content. The result of sensory evaluation showed that there were significant (p<0.05) differences in the scores of smell and taste sensory characteristics among the samples. The overall eating quality was the highest in the control and decreased with increasing sea mustard powder level. The study results suggested that Bacsulgi prepared with up to 5% addition of sea mustard powder was as acceptable as Bacsulgi prepared without sea mustard powder.

IMPACT ANALYSES AND TESTS OF CONCRETE OVERPACKS OF SPENT NUCLEAR FUEL STORAGE CASKS

  • Lee, Sanghoon;Cho, Sang-Soon;Jeon, Je-Eon;Kim, Ki-Young;Seo, Ki-Seog
    • Nuclear Engineering and Technology
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    • v.46 no.1
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    • pp.73-80
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    • 2014
  • A concrete cask is an option for spent nuclear fuel interim storage. A concrete cask usually consists of a metallic canister which confines the spent nuclear fuel assemblies and a concrete overpack. When the overpack undergoes a missile impact, which might be caused by a tornado or an aircraft crash, it should sustain an acceptable level of structural integrity so that its radiation shielding capability and the retrievability of the canister are maintained. A missile impact against a concrete overpack produces two damage modes, local damage and global damage. In conventional approaches [1], those two damage modes are decoupled and evaluated separately. The local damage of concrete is usually evaluated by empirical formulas, while the global damage is evaluated by finite element analysis. However, this decoupled approach may lead to a very conservative estimation of both damages. In this research, finite element analysis with material failure models and element erosion is applied to the evaluation of local and global damage of concrete overpacks under high speed missile impacts. Two types of concrete overpacks with different configurations are considered. The numerical simulation results are compared with test results, and it is shown that the finite element analysis predicts both local and global damage qualitatively well, but the quantitative accuracy of the results are highly dependent on the fine-tuning of material and failure parameters.

Preliminary Evaluation of Radiological Impact for Domestic On-road Transportation of Decommissioning Waste of Kori Unit 1

  • Dho, Ho-Seog;Seo, Myung-Hwan;Kim, Rin-Ah;Kim, Tae-Man;Cho, Chun-Hyung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.18 no.4
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    • pp.537-548
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    • 2020
  • Currently, radioactive waste for disposal has been restricted to low and intermediate level radioactive waste generated during operation of nuclear power plants, and these radioactive wastes were managed and disposed of the 200 L and 320 L of steel drums. However, it is expected that it will be difficult to manage a large amount of decommissioning waste of the Kori unit 1 with the existing drums and transportation containers. Accordingly, the KORAD is currently developing various and large-sized containers for packaging, transportation, and disposal of decommissioning waste. In this study, the radiation exposure doses of workers and the public were evaluated using RADTRAN computational analysis code in case of the domestic on-road transportation of new package and transportation containers under development. The results were compared with the domestic annual dose limit. In addition, the sensitivity of the expected exposure dose according to the change in the leakage rate of radionuclides in the waste packaging was evaluated. As a result of the evaluation, it was confirmed that the exposure dose under normal and accident condition was less than the domestic annual exposure dose limit. However, in the case of a number of loading and unloading operations, working systems should be prepared to reduce the exposure of workers.

Policy Suggestions to Improve Patient Access to New Drugs in Korea (환자의 신약 접근성 강화 정책 제안)

  • Choi, Yoona;Lee, Howard
    • Korean Journal of Clinical Pharmacy
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    • v.31 no.1
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    • pp.1-11
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    • 2021
  • Objective: This study aimed to overview and assess the effectiveness of the policies and regulations that have governed new drug access in Korea, and to propose policies to enhance patient access to drugs, particularly for new innovative medicines. Methods: We approached drug access issues in two perspectives: approval lag (or availability) and reimbursement lag (or affordability). The issues were identified and evaluated through the review of literature, public documents, reports published by the government agencies and private organizations, and news articles. Results: To shorten approval lag, it is recommended to hire and train more reviewers at the Ministry of Food and Drug Safety. Increasing user fees to a realistic level can facilitate this process. To reduce reimbursement lag, flexible incremental cost-effectiveness ratio threshold, alternative cost-effectiveness evaluation, and establishment of funding source other than the national health insurance are identified as the areas to be improved. Conclusion: The current policies and regulations had to be supplemented by new systems to drastically promote patient accessibility to new drugs, consequently in order to promote national public health.

Evaluation of the Vibration Reduction Performance of a Cushioning Layer between Metal Blocks (금속 블록에 삽입된 감쇠층의 진동저감 성능 평가)

  • Yun, Seong-Ho
    • Journal of the Korean Society of Manufacturing Process Engineers
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    • v.21 no.7
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    • pp.71-76
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    • 2022
  • This study describes an evaluation of the vibration-level reduction effect of natural rubber inserted between two aluminum blocks, in which the modal parameters are predicted using two different damping systems. A numerical model with two degrees of freedom was established for both the cases. One was an eigenvalue problem analysis using a state space method and general viscous damping, whereas the other was a method using hysteretic damping. The modal parameters obtained from these two approaches were compared with those obtained from the finite element method using a commercial package. As a result, the natural frequencies observed in the complex frequency response curve were consistently less than the average of four percents. The damping ratios also showed good agreement within a reasonable range. However, the hysteretic damping system showed a relatively larger difference for all modal parameters. This suggests that the analysis procedure makes it easier to predict the vibration transmission characteristics of the shape and configuration of any cushioning layer.

Comprehensive validation of silicon cross sections

  • Czakoj, Tomas;Kostal, Michal;Simon, Jan;Soltes, Jaroslav;Marecek, Martin;Capote, Roberto
    • Nuclear Engineering and Technology
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    • v.52 no.12
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    • pp.2717-2724
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    • 2020
  • Silicon, especially silicon in the form of SiO2, is a major component of rocks. Final spent fuel storages, which are being designed, are located in suitable rock formations in the Earth's crust. Reduction of the uncertainty of silicon neutron scattering and capture is needed; improved silicon evaluations have been recently produced by the ORNL/IAEA collaboration within the INDEN project. This paper deals with the nuclear data validation of that evaluation performed at the LR-0 reactor by means of critical experiments and measurement of reaction rates. Large amounts of silicon were used both as pure crystalline silicon and SiO2 sand. The critical moderator level was measured for various core configurations. Reaction rates were determined in the largest core configuration. Simulations of the experimental setup were performed using the MCNP6.2 code. The obtained results show the improvement in silicon cross-sections in the INDEN evaluations compared to existing evaluations in major libraries. The new Thermal Scattering Law for SiO2 published in ENDF/B-VIII.0 additionally reduces the discrepancy between calculation and experiments. However, an unphysical peak is visible in the neutron spectrum in SiO2 obtained by calculation with the new Thermal Scattering Law.

Evaluation of developing efficiency on latent fingerprint (잠재지문 현출효율 평가에 대한 연구)

  • Kim, Man-Ki;Park, Sung-Woo;Ohgami, Yusuke
    • Analytical Science and Technology
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    • v.22 no.2
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    • pp.166-171
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    • 2009
  • Powder method is simple and very effective method for developing latent finger and palm print in crime scene. This technique has been actively studied to enhance effectiveness. In general, the evaluation for developing powder is mainly performed by the subjective opinion of researcher from comparison of the results obtained with existing and new one to develope finger and palm deposition. The purpose of this work is to present objective method of powder-treated latent fingerprint for evaluating method by developing efficiency. We indicated three evaluating methods of objective developing efficiency, which are measuring the number of minutiae in same sections on print, scattering level of developing reagent and contrast between developing reagent and background materials.

The effect of sensitive and non-sensitive parameters on DCGL in probability analysis for decommissioning of nuclear facilities

  • Hyung-Woo Seo;Hyein Kim
    • Nuclear Engineering and Technology
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    • v.55 no.10
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    • pp.3559-3570
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    • 2023
  • In the decommissioning of nuclear facilities, Derived Concentration Guideline Level (DCGL) derivation is necessary for the release of the facility after the site remediation, which also needs to be implemented in the stage of establishing a decommissioning planning. In order to derive DCGL, the dose assessment for the receptors can be conducted from residual radioactivity by using RESRAD code. When performing sensitivity analysis on probabilistic parameters, secondary evaluation is performed by assigning a single value for parameters classified as sensitive. However, several options may arise in the handling of nonsensitive parameters. Therefore, we compared the results of the first execution of RESRAD applying probabilistic parameters for each scenario with the results of the second execution applying a single value to sensitive parameters among the probabilistic parameters. In addition, we analyzed the effect of setting options for non-sensitive parameters. As a result, the effect on DCGL were different depending on the application scenario, the target radionuclides, and the input parameter selections. In terms of the overall evaluation period, the DCGL graph of the default option was generally shown as the most conservative except for some radionuclides. However, it will not necessarily be given priority in the aspect of the need to reflect site characteristics. The reason for selecting a probabilistic parameter is the availability of the parameter and the uncertainty of applying a single value. Therefore, as an alternative, it can be consistently applied to distribution as an option for non-sensitive parameters after sensitivity analysis.

The influence of air gaps on buffer temperature within an engineered barrier system

  • Seok Yoon;Gi-Jun Lee
    • Nuclear Engineering and Technology
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    • v.55 no.11
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    • pp.4120-4124
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    • 2023
  • High-level radioactive waste produced by nuclear power plants are disposed subterraneously utilizing an engineered barrier system (EBS). A gap inevitably exists between the disposal canisters and buffer materials, which may have a negative effect on the thermal transfer and water-blocking efficiency of the system. As few previous experimental works have quantified this effect, this study aimed to create an experimental model for investigating differences in the temperature changes of bentonite buffer in the presence and absence of air gaps between it and a surrounding stainless steel cell. Three test scenarios comprised an empty cell and cells partially or completely filled with bentonite. The temperature was measured inside the buffers and on the inner surface of their surrounding cells, which were artificially heated. The time required for the entire system to reach 100℃ was approximately 40% faster with no gap between the inner cell surface and the bentonite. This suggests that rock-buffer spaces should be filled in practice to ensure the rapid dissipation of heat from the buffer materials to their surroundings. However, it can be advantageous to retain buffer-canister gaps to lower the peak buffer temperature.