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A Study on the Analysis and Solutions of the Blockchain Security Issues
노시완,이경현 한국인터넷정보학회 2019 인터넷정보학회논문지 Vol.20 No.4
A Blockchain-based access control technology is one of the various use cases of blockchain and is used in many areas to transparently transfer and manage ownership of data between users without the trusted third party. The characteristics of transparency, Irreversibility, and decentralization provided by the public blockchain help to offer new benefits that existing access control technologies did not offer. However, various security issues facing the current blockchain are raising the issue of the safety of the technology. Therefore, in this paper, we analyze an overview of the blockchain-based access control technology and solutions of the security challenges faced. Moreover, we further present solutions that are not affected by the blockchain trilemma and models of access control technology based on them.
안전한 블록체인 기반 서비스를 위한 개인키 관리 가이드라인
노시완,이경현 한국정보보호학회 2022 정보보호학회논문지 Vol.32 No.5
블록체인 기반 탈중앙 서비스는 참여자들의 합의에 기반하여 시스템을 운영함으로써 중앙화된 서버 없이도 신뢰할 수 있는 서비스를 사용자에게 제공할 수 있다. 참여자들은 디지털서명 메커니즘을 사용하여 블록체인과 상호작용할 수 있지만 개인키 관리와 관련된 이슈는 여전히 해결되지 않는 문제로 남아있다. NIST SP800-57 암호키 관리 권고안 등에서는 사용자의 개인키 관리에 관한 내용을 기술하고 있지만, 이는 탈중앙 서비스 환경을 고려하지 않았기에 블록체인 환경에 적용하기에는 적절하지 않다. 본 논문에서는 개인키 관리와 관련된 지갑 애플리케이션의 기능을 정의하고 NIST SP800-57을 반영한 블록체인 개인키 관리 방안과 이를 만족하기 위한 관련 기술을 제시한다. 마지막으로 논문에서 정의한 내용을 바탕으로 퍼블릭 블록체인에서 일반 사용자를 대상으로 하는 개인키 관리 가이드라인을 제안한다. A blockchain-based decentralized service can offer reliable services without the centralized server by operating the system based on the consensus among byzantine participants. Participants can interact with the blockchain network through a digital signature mechanism but the private key management issue remains unresolved. NIST SP800-57 provides a key-management guidance but this guidance is not appropriate for blockchain-based services because it does not consider a decentralized environment. In this paper, we define the core functions of the blockchain wallet application for private key management and present security protections according to NIST SP800-57, as well as related techniques to satisfy them. Finally, we propose the private key management guideline for secure blockchain-based decentralized services.
PRELIMINARY ESTIMATION OF ACTIVATED CORROSION PRODUCTS IN THE COOLANT SYSTEM OF FUSION DEMO REACTOR
노시완,이재기,신창호,권태제,김종경,이영석 대한방사선방어학회 2012 방사선방어학회지 Vol.37 No.2
The second phase of the national program for fusion energy development in Korea starts from 2012 for design and construction of the fusion DEMO reactor. Radiological assessment for the fusion reactor is one of the key tasks to assure its licensability and the starting point of the assessment is determination of the source terms. As the first effort, the activities of the coolant due to activated corrosion product (ACP) were estimated. Data and experiences from fission reactors were used, in part, in the calculations of the ACP concentrations because of lack of operating experience for fusion reactors. The MCNPX code was used to determine neutron spectra and intensities at the coolant locations and the FISPACT code was used to estimate the ACP activities in the coolant of the fusion DEMO reactor. The calculated specific activities of the most nuclides in the fusion DEMO reactor coolant were 2‐15 times lower than those in the PWR coolant, but the specific activities of 57Co and 57Ni were expected to be much higher than in the PWR coolant. The preliminary results of this study can be used to figure out the approximate radiological conditions and to establish a tentative set of radiological design criteria for the systems carrying coolant in the design phase of the fusion DEMO reactor.
Development of Probabilistic Internal Dosimetry Computer Code
노시완,권태은,이재기 한국물리학회 2017 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.70 No.3
Internal radiation dose assessment involves biokinetic models, the corresponding parameters, measured data, and many assumptions. Every component considered in the internal dose assessment has its own uncertainty, which is propagated in the intake activity and internal dose estimates. For research or scientific purposes, and for retrospective dose reconstruction for accident scenarios occurring in workplaces having a large quantity of unsealed radionuclides, such as nuclear power plants, nuclear fuel cycle facilities, and facilities in which nuclear medicine is practiced, a quantitative uncertainty assessment of the internal dose is often required. However, no calculation tools or computer codes that incorporate all the relevant processes and their corresponding uncertainties, i.e., from the measured data to the committed dose, are available. Thus, the objective of the present study is to develop an integrated probabilistic internal-dose-assessment computer code. First, the uncertainty components in internal dosimetry are identified, and quantitative uncertainty data are collected. Then, an uncertainty database is established for each component. In order to propagate these uncertainties in an internal dose assessment, a probabilistic internal-dose-assessment system that employs the Bayesian and Monte Carlo methods. Based on the developed system, we developed a probabilistic internal-dose-assessment code by using MATLAB so as to estimate the dose distributions from the measured data with uncertainty. Using the developed code, we calculated the internal dose distribution and statistical values (e.g. the 2.5th, 5th, median, 95th, and 97.5th percentiles) for three sample scenarios. On the basis of the distributions, we performed a sensitivity analysis to determine the influence of each component on the resulting dose in order to identify the major component of the uncertainty in a bioassay. The results of this study can be applied to various situations. In cases of severe internal exposure, the causation probability of a deterministic health effect can be derived from the dose distribution, and a high statistical value (e.g., the 95th percentile of the distribution) can be used to determine the appropriate intervention. The distribution-based sensitivity analysis can also be used to quantify the contribution of each factor to the dose uncertainty, which is essential information for reducing and optimizing the uncertainty in the internal dose assessment. Therefore, the present study can contribute to retrospective dose assessment for accidental internal exposure scenarios, as well as to internal dose monitoring optimization and uncertainty reduction.