• 제목/요약/키워드: The Components for Assessment

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중소기업 정보보호관리 모델의 개발: 실증 연구 (Developing Information Security Management Model for SMEs: An Empirical Study)

  • 이정우;박준기;이준기
    • Asia pacific journal of information systems
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    • 제15권1호
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    • pp.115-133
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    • 2005
  • This study is to develop an information security management model(ISMM) for small and medium sized enterprises(SMEs). Based on extensive literature review, a five-pillar twelve-component reference ISMM is developed. The five pillars of SME's information security are: centralized decision making, ease of management, flexibility, agility and expandability. Twelve components are: scope & organization, security policy, resource assessment, risk assessment, implementation planning, control development, awareness training, monitoring, change management, auditing, maintenance and accident management. Subsequent survey designed and administered to expose experts' perception on the importance of these twelve components revealed that five out of tweleve components require relatively immediate attention than others, especially in SME's context. These five components are: scope and organization, resource assessment, auditing, change management, and incident management. Other seven components are policy, risk assessment, implementation planning, control development, awareness training, monitoring, and maintenance. It seems that resource limitation of SMEs directs their attention to ISMM activities that may not require a lot of resources. On the basis of these findings, a three-phase approach is developed and proposed here as an SME ISMM. Three phases are (1) foundation and promotion, (2) management and expansion, and (3) maturity. Implications of the model are discussed and suggestions are made for further research.

Investigation on failure assessment method for nuclear graphite components

  • Gao, Yantao;Tsang, Derek K.L.
    • Nuclear Engineering and Technology
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    • 제52권1호
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    • pp.206-210
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    • 2020
  • Super fine-grained graphite is a type of advanced nuclear graphite which was developed for Molten Salt Reactor (MSR). It is necessary to establish a failure assessment method used for nuclear graphite components in MSR. A modified assessment approach based on ASME BPVC-III-5_2017 is presented. The new approach takes a new parameter, KIC, into account and abandons the parameter, grain size, which is unrealistic for super fine-grained graphite as the computation is enormous if we use conventional methods. Three methodologies (KTA 3232, ASME, New approach) were also evaluated by theoretical prediction and experimental verification. The results indicated the new developed code can be used for design and failure assessment of super fine-graphite components and has more extensive applicability.

초고압 시스템의 안전성 확보에 대한 연구 (A Study of Safety Acquirement for an Assessment of Ultra High Pressure System)

  • 이기천;김형의;김재훈
    • 한국안전학회지
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    • 제25권5호
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    • pp.7-14
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    • 2010
  • Ultra high pressure system, which can be generally increased over 1,000bar, needs to have sealing mechanism to protect leakage and selection of the materials used in the intensifier. Components such as pressure vessel, hydraulic hose assembly, accumulator, hydraulic cylinder, hydraulic valve, pipe, etc., are tested under the impulse-pressure conditions. Components need to be tested under 1.5 to 3 times of rated pressure to check the tolerance even though rated pressure range of these components are not ultra high pressure. So, the ultra high pressure system needs to be equiped to test components. In this study, safety assessments of ultra high pressure system which are using failure analysis of components, changing the types of the control system, and finite element analysis with static condition, are investigated.

Fragility curves for the typical multi-span simply supported bridges in northern Pakistan

  • Waseem, Muhammad;Spacone, Enrico
    • Structural Engineering and Mechanics
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    • 제64권2호
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    • pp.213-223
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    • 2017
  • Bridges are lifeline and integral components of transportation system that are susceptible to seismic actions, their vulnerability assessment is essential for seismic risk assessment and mitigation. The vulnerability assessment of bridges common in Pakistan is very important as it is seismically very active region and the available code for the seismic design of bridges is obsolete. This research presents seismic vulnerability assessment of three real case simply supported multi-span reinforced concrete bridges commonly found in northern Pakistan, having one, two and three bents with circular piers. The vulnerability assessment is carried through the non-linear dynamic time history analyses for the derivation of fragility curves. Finite element based numerical models of the bridges were developed in MIDAS CIVIL (2015) and analyzed through with non-linear dynamic and incremental dynamic analyses, using a suite of bridge-specific natural spectrum compatible ground motion records. Seismic responses of shear key, bearing pad, expansion joint and pier components of each bridges were recorded during analysis and retrieved for performance based analysis. Fragility curves were developed for the bearing pads, shear key, expansion joint and pier of the bridges that first reach ultimate limit state. Dynamic analysis and the derived fragility curves show that ultimate limit state of bearing pads, shear keys and expansion joints of the bridges exceed first, followed by the piers ultimate limit state for all the three bridges. Mean collapse capacities computed for all the components indicated that bearing pads, expansion joints, and shear keys exceed the ultimate limit state at lowest seismic intensities.

CSRP 시험데이터를 사용한 베이시안 추정모델 기반 K-1 방독면 저장수명 분석 (Bayesian Estimation based K-1 Gas-Mask Shelf Life Assessment using CSRP Test Data)

  • 김종환;정치정;김현정
    • 한국군사과학기술학회지
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    • 제21권1호
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    • pp.124-132
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    • 2018
  • This paper presents a shelf life assessment for K-1 military gas masks in the Republic of Korea using test data of Chemical Materiels Stockpile Reliability Program(CSRP). For the shelf life assessment, over 2,500 samples between 2006 and 2015 were collected from field tests and analyzed to estimate a probability of proper and improper functionality using Bayesian estimation. For this, three stages were considered; a pre-processing, a processing and an assessment. In the pre-processing, major components which directly influence the shelf life of the mask were statistically analyzed and selected by applying principal component analysis from all test components. In the processing, with the major components chosen in the previous stage, both proper and improper probability of gas masks were computed by applying Bayesian estimation. In the assessment, the probability model of the mask shelf life was analyzed with respect to storage periods between 0 and 29 years resulting in between 66.1 % and 100 % performances in accuracy, sensitivity, positive predictive value, and negative predictive value.

독서토론의 수행평가 도구 개발에 관한 연구 (A Study on the Development of Performance Assessment Tool in Reading Debate)

  • 정종기
    • 한국도서관정보학회지
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    • 제37권1호
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    • pp.353-373
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    • 2006
  • 본 연구는 독서능력과 토론능력에 대한 개념 및 구성요소를 명확히 살펴보고 이를 바탕으로 평가도구와 평가기준을 개발하여 학교도서관의 독서토론수업에서 학습자에 대한 객관적인 수행평가를 실행할 수 있는 평가 방법을 제안하는데 그 목적이 있다. 이를 위해서 먼저 학교도서관 독서토론수업의 관점에서 독서토론과 평가의 필요성을 살펴보고, 기존의 독서능력과 토론능력에 대한 선행연구를 중심으로 독서능력과 토론능력의 개념과 그 구성요소들을 고찰하였다. 독서능력과 토론능력의 구성요소를 추출하고 학교도서관의 독서토론수업 수행평가에 포함되어야 할 구성요소를 기초로 하여 사서교사와 교과교사 즉, 교육평가자 관점의 평가도구와 평가기준을 개발하였다.

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고온 기기의 크리프-피로 균열성장 평가 (Assessment of Creep-Fatigue Crack Growth for a High Temperature Component)

  • 이형연;김종범;이재한
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2008년도 추계학술대회A
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    • pp.264-268
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    • 2008
  • An assessment of creep-fatigue crack behavior is required to ensure the structural integrity for high temperature components such as fast breeder reactor structures or thermal power plant components operating at an elevated temperature. In this study, an evaluation of creep-fatigue crack growth has been carried out according to the French assessment guide of the RCC-MR A16 for austenitic stainless steel structures. The assessment procedures for creep-fatigue crack growth in the recent version of the A16 (2007 edition) have been changed considerably from the previous version (2002 edition) and the material properties (RCC-MR Appendix A3) have been changed as well. The impacts of those changes on creep-fatigue crack growth behavior are quantified from the assessments with a structural model. Finally the assessment results were compared with the observed images obtained from the structural tests of the same structural specimen.

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Development of the Assessment Indicators for Railway Safety

  • Song, Bo-Young;Moon, Dae-Seop;Lee, Hi Sung
    • International Journal of Railway
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    • 제5권4호
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    • pp.175-181
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    • 2012
  • This study proposes a model for railway safety assessment with which the safety of whole railway system can be evaluated. The purpose of the assessment model is to generate safety indicators which quantitatively represent the degree of railway safety. Safety indicators were proposed as three indicators according to their functions; accident indicators, safety management indicators, and safety culture indicators. This paper describes the first result on the safety target which will be a key starting point toward the development of safety assessment model. It is recommended that the safety target to be composed of several sub-targets are apportioned to constituent components. It is concluded that the classification of safety target has influence on deciding components or attributes that constitute each sub-indicators; accident indicators, safety management indicators, and safety culture indicators. Based on this study, a railway safety assessment model will be developed in the following study.

중수로 사용후핵연료 처분시스템의 방사선 안전성 평가 (Radiation Safety Assessment of CANDU Spent Fuel Disposal System)

  • 국동학;조동건;최희주
    • Journal of Radiation Protection and Research
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    • 제35권4호
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    • pp.142-150
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    • 2010
  • 중수로 사용후핵연료의 처분 효율을 높이기 위하여 새롭게 제안된 처분 시스템에 대한 방사선량을 MCNPX를 사용하여 계산함으로써 이 시스템의 방사선 안전성을 예비적으로 평가하고자 하였다. 이를 위해서 처분시스템의 각 요소에 대한 구성, 제원, 재질 등을 분석하였으며, 그에 상응하는 모델링을 수행하였다. 선량평가는 주요 구성요소에 대하여 수행하였으며, 평가결과 내부 구성요소에 대해서는 방사선량이 높은 편이었으나, 최종적인 처분시스템은 방사선에 대한 안전성이 높은 것으로 나타났다.

Quality Assessment of Curcuma longa L. by Gas Chromatography-Mass Spectrometry Fingerprint, Principle Components Analysis and Hierarchical Clustering Analysis

  • Li, Ming;Zhou, Xin;Zhao, Yang;Wang, Dao-Ping;Hu, Xiao-Na
    • Bulletin of the Korean Chemical Society
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    • 제30권10호
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    • pp.2287-2293
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    • 2009
  • Gas Chromatography-Mass Spectrometry (GC-MS) fingerprint analysis, Principle Components Analysis (PCA), and Hierarchical Cluster Analysis (HCA) were introduced for quality assessment of Curcuma longa L. (C. longa). The GC-MS fingerprint method was developed and validated by analyzing 33 batches of samples of C. longa from different geographic locations. 18 chromatographic peaks were selected as characteristic peaks and their relative peak areas (RPA) were calculated for quantitative expression. Two principal components (PCs) were extracted by PCA. C. longa collected from Guizhou and Fujian were separated from other samples by PC1, capturing 71.83% of variance. While, PC2 contributed for their further separation, capturing 11.13% of variance. HCA confirmed the result of PCA analysis. Therefore, GC-MS fingerprint study with chemometric techniques provides a very flexible and reliable method for quality assessment of C. longa.