• Journal of KIISE:Software and Applications
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• v.31 no.11
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• pp.1439-1454
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• 2004

Recently, Levels of Information Systems Interoperability (LISI) that are used for assessing the information systems interoperability are defined according to the importance of interoperability among information systems. At that time, it is necessary to the construction of an assessment information repository to store and retrieve the interoperability assessment data efficiently. An LISI repository constructed for storing and retrieving an assessment information should support assessment systems that are developed in various Platforms and provide its functions by a standardized way. Business logics of LISI repository should be developed as distributed components, and we need to modify existing software design methods to show characteristics of LISI repository in addition to the standardized LISI data expression. Also a concrete method to recognize various implementation technologies and to apply them to implementation of LISI repository is needed. This paper provides a design method for developing an LISI repository that is considering the characteristics of LISI repository by three concerns, and an implementation scheme that can apply to the integration of the various repository implementation technologies systematically, as the LISI repository development framework for constructing the LISI repository. These help developers to construct the LISI repository effectively by providing concrete guidelines for considerations and appliable methods to construct the LISI repository.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.18 no.spc
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• pp.63-74
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• 2020

The operational safety assessment is an important part of a safety case for the deep geological repository of spent fuels. It consists of different stages such as the identification of initiating events, event tree analysis, fault tree analysis, and evaluation of exposure doses to the public and radiation workers. This study develops a probabilistic safety assessment method for the operational safety assessment and establishes an assessment framework. For the event and fault tree analyses, we propose the advanced information management system for probabilistic safety assessment (AIMS-PSA Manager). In addition, we propose the Radiological Safety Analysis Computer (RSAC) program to evaluate exposure doses to the public and radiation workers. Furthermore, we check the applicability of the assessment framework with respect to drop accidents of a spent fuel assembly arising out of crane failure, at the surface facility of the KRS⁺ (KAERI Reference disposal System for SNFs). The methods and tools established through this study can be used for the development of a safety case for the KRS⁺ system as well as for the design modification and the operational safety assessment of the KRS⁺ system.

• Nuclear Engineering and Technology
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• v.31 no.6
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• pp.23-38
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• 1999

This study addresses the reference spent fuel and its characteristics for developing a geological repository concept. As a disposal capacity of the reference repository system to be developed, spent fuel inventories were projected based on the basis of the Nuclear Energy Plan of the Long-term National Power Program. The reference spent fuel encompassing a variability in characteristics of all existing and future spent fuels of interest was defined. Key parameters in the reference fuel screening processes were the nuclear and mechanical design parameters and the burnup histories for existing spent fuels as of 1996 and for future spent fuels with the more extended burnup the initial enrichment and its expected turnup. The selected reference fuel was characterized in terms of initial enrichment, bumup, dimension, gross weight and age. Also the isotopic composition and the radiological properties are quantitatively identified. This information provided in this study could be used as input for repository system development and performance assessment and applied in fuel material balance evaluation for the various types of back-end fuel cycle studies.

• Journal of Radiation Industry
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• v.17 no.1
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• pp.33-44
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• 2023

The deep geological repository of high-level radioactive waste shall be designed to meet the safety objective set in the form of radiation dose or corresponding risk to protect human and the environment from radiation exposure. Engineering feasibility and conformity with the safety objective of the facility conceptual design can be demonstrated by comparing the assessment result using the computational model for scenario(s) describing the radionuclide release and transport from repository to biosphere system. In this study, as the preliminary study for developing the high-level radioactive waste disposal facility in Korea, we reviewed and analyzed the entire list of FEPs and how to handle each FEP from a general point of view, which are selected for the geosphere region in the radiological safety assessment performed for the license application of the KBS-3 type deep geological repository in Finland and Sweden. In Finland, five FEPs (i.e., stress redistribution, creep, stress redistribution, erosion and sedimentation in fractures, methane hydrate formation, and salt exclusion) were excluded or ignored in the radionuclide release and transport assessment. And, in Sweden, six FEPs (i.e., creep, surface weathering and erosion, erosion/sedimentation in fractures, methane hydrate formation, radiation effects (rock and grout), and earth current) were not considered for all time frames and earthquake out of a total of 25 FEPs for the geosphere. Based on these results, an FEP list (draft) for the geosphere was derived, and the relative importance of each item was evaluated for conducting the radiological safety assessment of the domestic deep geological disposal facility. Since most of information on the disposal facility in Korea has not been determined as of now, it is judged that all FEP items presented in Table 3 should be considered for the radiological safety assessment, and the relative importance derived from this study can be used in determining whether to apply each item in the future.

• Nuclear Engineering and Technology
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• v.51 no.6
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• pp.1561-1574
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• 2019

A standard form of six stylized human intrusion scenarios for a near-surface disposal facility (e.g. the planned Korean repository, Gyeongju Phase II) is proposed through re-categorization of totally thirty-one past cases reported in public literature. A reference assessment framework for inadvertent human intrusion is newly developed using GENII Version 2 conforming to the ICRP Publication 60 and thereafter. Calculated dose from the assessment framework is verified by comparing with hand calculation results for simplified model equations independently derived. Results from GENII Version 2 and 1.485 show inevitable differences, which is mainly attributed to the difference in the external dose assessment model. If intake dose coefficients in GENII Version 1.485 are modified, the difference can be reduced but still exist to an extent. Through deterministic and probabilistic sensitivity analysis, most affecting four parameters are derived and uncertainties of the parameters are quantified. It is expected that the reference assessment framework together with representative stylized scenarios can be used to do a human intrusion impact assessment for a specific repository using site-specific information. Especially, the past practice of human intrusion impact assessment using GENII Version 1.485 with or without modification may be replaced with the new assessment framework developed in this study.

• International Journal of Knowledge Content Development & Technology
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• v.7 no.2
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• pp.41-51
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• 2017

Nowadays, research data repositories (RDR) have become progressively widespread all over the world. To expand repository services and build up inbound linking strategy, organizations list their repositories with so called Global Registries. Accordingly, such registries should be carefully described by the related data. In this study, I explore the metadata schema of re3data.org. I collect and analyze descriptions from the listed repositories, and come up with some suggestions concerning possible improvements to the metadata schema. To accomplish this, I develop a crawler program, which collects necessary data from the re3data.org. Based on the analysis results, I have identified two issues that required elements is missing, one issue that required element value is missing when the corresponding property is applied, five inconsistency issues with re3data controlled vocabulary, six issues with undescribed optional elements, and two inconsistency issues between the elements and their attributes which do not pair with. I believe this discussion can facilitate improvements to the existing re3data.org schema and further help researchers who analyze data repository trends.

• Journal of Korean Library and Information Science Society
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• v.36 no.3
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• pp.85-107
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• 2005

The purpose of this study is to develop an evaluation indicator of institutional repositories to be used by participating university libraries of dCollection. Based on the literature reviews of digital library evaluation, core evaluation measures and criteria were identified. In order to verify the applicability and appropriateness of those evaluation criteria for institutional repositories, two methods were employed: A case study with sixteen university libraries and a Delphi study with twenty university libraries. The results of both studies led the development of an evaluation model which consisted of four evaluation dimensions and 29 criteria. This evaluation model should be utilized as tools for objective assessment and guidelines for improving institutional repository services by universities libraries in which the dCollection is currently Implemented or the future plan of the dCollection is underway.

• Journal of Radiation Industry
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• v.17 no.1
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• pp.45-59
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• 2023

The transport calculation for a wide variety of radionuclides contained in high-level radioactive waste, especially spent nuclear fuel, is computationally difficult, and input data collection for this also take a considerable amount of time. Accordingly, considering limited resources, it is possible to reduce the calculation time while minimizing impact on accuracy by including only radionuclides important to calculation result through applying some criteria among potential radiation source terms that may release into environment. In this paper, therefore, we reviewed and analyzed the screening process performed to select radionuclides to be considered in the safety assessment for the KBS-3 type repository in Sweden and Finland. In both countries, it was confirmed that a list of radionuclides was selected by comprehensively considering screening criteria such as radioactivity inventory, half-life, radiotoxicity, risk quotient, and transport properties, and etc. A comparison of radionuclides included in the radiological safety assessment in both countries suggests that most of nuclides are considered in common, and a few nuclides considered only in one country are due to differences in decay chain treatment or spent fuel types. As of now, since most of information on the disposal facility in Korea has not been determined, it is necessary to comprehensively model release and transport of all radionuclides considered in Sweden and Finland when performing the radiological safety assessment. Based on these results, we derived the screening concept of selecting a list of radionuclides to be considered in the radiological safety assessment for the domestic KBS-3 type geological disposal facility, and this result is expected to be used as technical basis for confirming conformity with the safety objective. In a more detailed evaluation reflecting domestic characteristics in the future, it would be desirable to consider only radionuclides selected in accordance with the screening procedure. However, further research should be conducted to determine the quantitative limit for each criteria.

• Journal of the Korea Society of Computer and Information
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• v.22 no.2
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• pp.81-87
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• 2017

Nowadays wine is increasingly enjoyed by a wider range of consumers, and wine certification and quality assessment are key elements in supporting the wine industry to develop new technologies for both wine making and selling processes. There have been many attempts to construct a more methodical approach to the assessment of wines, but most of them rely on objective decision rather than subjective judgement. In this paper, we propose a data mining approach to predict human wine taste preferences that is based on easily available analytical tests at the certification step. We used sequential forward selection and decision tree for this purpose. Experiments with the wine quality dataset from the UC Irvine Machine Learning Repository demonstrate the accuracies of 76.7% and 78.7% for red and white wines respectively.

• The Transactions of the Korea Information Processing Society
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• v.4 no.8
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• pp.1948-1960
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• 1997

Quality of a new system is closly related to the quality of components in reuse repository. Quality assessment is essential to construct a reuse library. Definition of quality and method of assessment are totally different in reuse environments. User interface, functionality, performance are main factor in non-reuse development environment. However, reuse environment needs more reusability, extensibility, generality, and maintainability in quality assessment. This paper describes a development of quality assessment tool for multimedia object reuse conponents. Tool gets reuse components described by C++ or IDL, and analyses style, structure, coupling, strength, complexity, understandability, etc. Ultimatly the tool generate quality satisfaction degree for reuse programmers. Quality assessment services are supported in distributed object architecture, CORBA.