• Proceedings of the Korean Information Science Society Conference
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• 1999.10a
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• pp.391-393
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• 1999

자바빈 컴포넌트를 이용한 RAD 개발 도구들은 일반적으로 자바빈 컴포넌트를 시각적으로 배치하고, 속성 및 이벤트를 편집할 수 있는 개발 환경을 제공한다. RAD 개발 도구들은 배치된 컴포넌트에 대한 속성과 이벤트를 편집할 수 있는데 특히 이벤트는 개발자의 응용 논리가 포함된 부분으로 완전한 시각화를 통한 구현이 어렵다. 본 논문에서는 자바빈 컴포넌트 기반 개발 환경에서 자바 언어의 인트로스팩션(Introspection) 메커니즘을 이용한 자바 소스 코드 생성 기법을 제시한다. 자바 소스 코드의 생성은 태그로 표시된 템플릿 코드의 생성과 자바의 위임 이벤트 모델을 이용한 이벤트 처리 코드를 생성하여 템플릿 코드에 합성하는 방법을 따른다. 본 논문에서 제시하는 기법은 인트로스펙션에 의해 추출된 정보를 개발자에게 시각적으로 보여주며 개발자의 시각적 조작에 따라 이벤트에 대한 소스코드를 자동으로 생성해준다.

• Journal of the Korea Academia-Industrial cooperation Society
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• v.9 no.6
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• pp.1659-1665
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• 2008

In this paper, we propose a design and implementation of HTML Filter to provide wireless internet service efficiently. The HTML Filter translates the Web documents written by HTML into the WML documents for portable wireless equipments automatically that are suitable for the WAP environment. The HTML Filter consists of "the HTML lexical analyzer" which gathers HTML source into token units, "the HTML syntax analyzer" which takes the lexical units from the lexical analyzer and analyses grammar for the source, "the HTML abstract parser tree" which can represent meaning of HTML sources more effectively called an intermediate code, and "the target code generator" which can convert the abstract parser tree into WML documents. The proposed translating method using ordinary compiler technology provides more easy and effective than the existing converters, and will be applied to other wireless language translating methods on wireless internet.

• Journal of KIISE:Computing Practices and Letters
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• v.13 no.7
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• pp.442-453
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• 2007

A model-based integrated development tool for the development of USN application programs is proposed in this paper. The proposed tool has been implemented as a plug-in for Eclipse platform. The tool consists of Graphical User Interface, Modeler, Configuration Information Generator, Validity Checker, Source Code Generator and Templates Storage. Developers can implement USN applications from models of sensor networks using the tool. The developer can implement USN applications by automatic generation of execution code of each node in the sensor network after he/she designs a model of the sensor network. The configuration information of each node is automatically generated from the validated USN model. Then, the execution code is automatically generated using the configuration information and the predefined templates. Through the tool of this paper, developers can easily implement valid USN applications even if they do not know the details of low-level information. Also, a large number of application programs can be generated at once because application programs are generated from sensor network model instead of models of applications. Accordingly, the development effort of USN applications will be decreased and developers can consistently construct USN applications from USN models using the proposed tool.

• Nuclear Engineering and Technology
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• v.52 no.1
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• pp.19-26
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• 2020

Small nuclear reactor features higher power capacity, longer operation life than conventional power sources. It could be an ideal alternative of existing power source applied for special equipment for terrestrial or underwater missions. In this paper, a 25kWe heat pipe cooled reactor power source applied for multiple use is preliminary designed. Based on the design, a thermal-hydraulic analysis code for heat pipe cooled reactor is developed to analyze steady and transient performance of the designed nuclear reactor. For reactor design, UN fuel with 65% enrichment and potassium heat pipes are adopted in the reactor core. Tungsten and LiH are adopted as radiation shield on both sides of the reactor core. The reactor is controlled by 6 control drums with B₄C neutron absorbers. Thermoelectric generator (TEG) converts fission heat into electricity. Cooling water removes waste heat out of the reactor. The thermal-hydraulic characteristics of heat pipes are simulated using thermal resistance network method. Thermal parameters of steady and transient conditions, such as the temperature distribution of every key components are obtained. Then the postulated reactor accidents for heat pipe cooled reactor, including power variation, single heat pipe failure and cooling channel blockage, are analyzed and evaluated. Results show that all the designed parameters satisfy the safety requirements. This work could provide reference to the design and application of the heat pipe cooled nuclear power source.

• The Journal of Korean Institute of Communications and Information Sciences
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• v.25 no.6A
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• pp.848-854
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• 2000

Network management in TMN concerns to the operating system and communication equipments in network, and defines them as objects. GDMO(guidelines for the Definition of Managed Objects) is used to describe those objects. GDMO is not directly used for managing the network, but translated into a language with object-oriented paradigm. And GDMO refers to ASN.1(Abstract Syntax Notation One) for manage objects. This paper presents design and implementation techniques for the translator which automatically translates the specification of ASN.1 and GDMO to the object-oriented language for generating MIB(Managed object Instance Base). This system, unlike the existing source code generator, is designed to generate various object-oriented languages automatically, which are used to generate Managed object Instance Base(MIB). And the system includes various graphic user interface to enhance the development environment of ASn.1 and GDMO

• The Transactions of the Korea Information Processing Society
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• v.6 no.6
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• pp.1532-1541
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• 1999

In this paper, we built an Object Oriented Framework for Web collaboration system which contains high level analysis information and design knowledge for java applets and applications that enable web clients to communicate and collaborate each other. Components of framework contain design information, source codes and executable codes for reuse. We had defined a development method for domain framework in related works and built a web collaboration system framework following it. We defined subsystem of web collaboration system for the communication and collaboration between web clients. We also BBS, Q&A system, board service system for the communication and collaboration between web clients. We also developed visual tools for framework usability : source code generator, class editor, knowledge supporting tools.

• Journal of Radiation Protection and Research
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• v.24 no.4
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• pp.215-223
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• 1999

Characteristics of radiation field in the steam generator(S/G) water chamber of a PWR were investigated and the anticipated effective dose rates to the worker in the S/G chamber were evaluated by Monte Carlo simulation. The results of crud analysis in the S/G of the Kori nuclear power plant unit 1 were adopted for the source term. The MCNP4A code was used with the MIRD type anthropomorphic sex-specific mathematical phantoms for the calculation of effective doses. The radiation field intensity is dominated by downward rays, from the U-tube region, having approximate cosine distribution with respect to the polar angle. The effective dose rates to adults of nominal body size and of small body size(The phantom for a 15 year-old person was applied for this purpose) appeared to be 36.22 and 37.06 $mSvh^{-1}$) respectively, which implies that the body size effect is negligible. Meanwhile, the equivalent dose rates at three representative positions corresponding to head, chest and lower abdomen of the phantom, calculated using the estimated exposure rates, the energy spectrum and the conversion coefficients given in ICRU47, were 118, 71 and 57 $mSvh^{-1}$, respectively. This implies that the deep dose equivalent or the effective dose obtained from the personal dosimeter reading would be the over-estimate the effective dose by about two times. This justifies, with possible under- or over- response of the dosimeters to radiation of slant incidence, necessity of very careful planning and interpretation for the dosimetry of workers exposed to a non-regular radiation field of high intensity.

• Journal of Radiation Protection and Research
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• v.29 no.3
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• pp.187-196
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• 2004

The health effects resulting from severe accidents of typical 1,000MWe KSNP(Korea Standard Nuclear Plant) PWR and typical 600MWe CANDU(CANada Deuterium Uranium) plants were estimated and compared. The population distribution of the site extending to 80km for both site were considered. The releaese fraction for various source term categories(STC) and core inventories were used in the estimation of the health effects risks by using the MACCS2(MELCOR Accident Consequence Code System2) code. Individuals are assumed to evacuate beyond 16km from the site. The health effects considered in this comparative study are early and cancer fatality risk, and the results are presented as CCDF(Complementary Cumulative Distribution Function) curves considering the occurrence probability of each STC's. According to the results, the early and cancer fatality risks of PHWR plants we lower than those of PWR plants. This is attributed the fact that the amount of radioactive mateials that released to the atmosphere resulting from the postulated severe accidents of PHWR plants are smaller than that of PWR plants. And, the dominating initiating event of STC that shows maximum early and cancer fatality risk is SGTR(Steam Generator Tube Rupture) for both plants. Therefore, the appropriated actions must be taken to reduce the occurrence probability and the amounts of radioactive materials released to the environment in order to protect the public for both PWR and PHWR plants.

• Journal of the Korea Institute of Information Security & Cryptology
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• v.28 no.1
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• pp.25-39
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• 2018

NIST(National Institute of Standards and Technology) has recently published SP 800-90B second draft which is the document for evaluating security of entropy source, a key element of a cryptographic random number generator(RNG), and provided a tool implemented on Python code. In SP 800-90B, the security evaluation of the entropy sources is a process of estimating min-entropy by several estimators. The process of estimating min-entropy is divided into IID track and non-IID track. In IID track, the entropy sources are estimated only from MCV estimator. In non-IID Track, the entropy sources are estimated from 10 estimators including MCV estimator. The running time of the NIST's tool in non-IID track is approximately 20 minutes and the memory usage is over 5.5 GB. For evaluation agencies that have to perform repeatedly evaluations on various samples, and developers or researchers who have to perform experiments in various environments, it may be inconvenient to estimate entropy using the tool and depending on the environment, it may be impossible to execute. In this paper, we propose high-speed implementations and an efficient memory usage technique for min-entropy estimation algorithm of SP 800-90B. Our major achievements are the three improved speed and efficient memory usage reduction methods which are the method applying advantages of C++ code for improving speed of MultiMCW estimator, the method effectively reducing the memory and improving speed of MultiMMC by rebuilding the data storage structure, and the method improving the speed of LZ78Y by rebuilding the data structure. The tool applied our proposed methods is 14 times faster and saves 13 times more memory usage than NIST's tool.

• Journal of Environmental Impact Assessment
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• v.27 no.3
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• pp.251-266
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• 2018

This study predicted the effect of operation pattern of flood control dam on water quality. Flood control dam temporarily impound floodwaters and then release them under control to the river below the dam preventing the river ecosystem from the extreme flood. The Hydrological Simulation Program Fortran (HSPF) and the Environmental Fluid Dynamics Code (EFDC) were adapted to predict the water quality before and after the dam construction in the proposed reservoir. The non-point pollutant delivery load from the river basin was estimated using the HSPF, and the EFDC was used to predict the water quality using the provided watershed boundary conditions from the HSPF. As a result of water quality simulation, it is predicted that the water quality will be improved due to the decrease of pollution source due to submergence after dam construction and temporary storage during rainfall. There would be no major water quality issues such as the eutrophication in the reservoir since the dam would impound the floodwater for a short time (2~3 days). In the environmental impact assessment stage of a planned dam, there may be some limitations to the exact simulation because the model can not be sufficiently calibrated. However, if the reliability of the model is improved through the acquisition of actual data in the future, it will be possible to examine the influence of the water environment according to various operating conditions in the environmental impact assessment of the new flood control dam.