• Journal of Radiation Protection and Research
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• 제42권2호
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• pp.114-129
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• 2017

Background: The purpose of this paper is to confirm the event timings and the magnitude of fission product aerosol release from the Fukushima accident. Over a few hundreds of technical papers have been published on the environmental impact of Fukushima Daiichi accident since the accident occurred on March 11, 2011. However, most of the research used reverse or inverse method based on the monitoring of activities in the remote places and only few papers attempted to estimate the release of fission products from individual reactor core or from individual spent fuel pool. Severe accident analysis code can be used to estimate the radioactive release from which reactor core and from which radionuclide the peaks in monitoring points can be generated. Materials and Methods: The basic material used for this study are the initial core inventory obtained from the report JAEA-Data/Code 2012-018 and the given accident scenarios provided by Japanese Government or Tokyo Electric Power Company (TEPCO) in official reports. In this research a forward method using severe accident progression code is used as it might be useful for justifying the results of reverse or inverse method or vice versa. Results and Discussion: The release timing and amounts to the environment are estimated for volatile radioactive fission products such as noble gases, cesium, iodine, and tellurium up to 184 hours (about 7.7 days) after earthquake occurs. The in-plant fission product behaviors and release characteristics to environment are estimated using the severe accident progression analysis code, MELCOR, for Fukushima Daiichi accident. These results are compared with other research results which are summarized in UNSCEAR 2013 Report and other technical papers. Also it may provide the physically based arguments for justifying or suspecting the rationale for the scenarios provided in open literature. Conclusion: The estimated results by MELCOR code simulation of this study indicate that the release amount of volatile fission products to environment from Units 1, 2, and 3 cores is well within the range estimated by the reverse or inverse method, which are summarized in UNSCEAR 2013 report. But this does not necessarily mean that these two approaches are consistent.

• 정보보호학회논문지
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• 제23권3호
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• pp.479-490
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• 2013

최근 삼성 갤럭시 노트 및 갤럭시 탭 10.1 등 안드로이드 기반 상용 모바일 단말을 대상으로 정상 어플리케이션인 것처럼 오픈 마켓에 배포된 악성 어플리케이션에 의한 공격들이 급증하고 있다. 공격자는 정상적인 어플리케이션에 악성코드를 삽입하여 상용 모바일 단말에 대한 루팅(Rooting) 공격을 수행한 후, 단말 내 저장된 사용자의 SMS, 전화번호부 등 개인정보와 공인인증서 등과 같은 금융정보를 외부 서버로 유출시키는 공격을 수행하게 된다. 따라서 상용 모바일 단말에 대한 악성코드 감염 여부를 판별하고 루팅 공격을 탐지 및 대응하기 위한 기법이 필요하다. 이에 본 논문에서는 안드로이드 기반 상용 모바일 단말에 대한 루팅 공격 기법에 대해 분석하고 이를 토대로 모니터링 데몬(Daemon)을 이용하여 상용 단말 내 공격 이벤트를 추출 및 수집하여 악성 어플리케이션으로 인한 공격에 능동적으로 대응하는 기법을 제시하였다.

• Nuclear Engineering and Technology
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• 제41권7호
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• pp.945-952
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• 2009

The Three Mile Island Unit 2 (TMI-2) accident provides unique full scale data, thus providing opportunities to check the capability of codes to model overall plant behavior and to perform a spectrum of sensitivity and uncertainty calculations. As part of the TMI-2 analysis benchmark exercise sponsored by the Organization for Economic Cooperation and Development Nuclear Energy Agency (OECD NEA), several member countries are continuing to improve their system analysis codes using the TMI-2 data. The Republic of Korea joined this benchmark exercise in November 2005. Seoul National University has analyzed the TMI-2 accident as well as the currently proposed alternative scenario along with a sensitivity study using the Modular Accident Analysis Program Version 4.03 (MAAP4.03) code in collaboration with the Korea Hydro and Nuclear Power Company. Two input files are required to simulate the TMI-2 accident with MAAP4: the parameter file and an input deck. The user inputs various parameters, such as volumes or masses, for each component. The parameter file contains the information on TMI-2 relevant to the plant geometry, system performance, controls, and initial conditions used to perform these benchmark calculations. The input deck defines the operator actions and boundary conditions during the course of the accident. The TMI-2 accident analysis provided good estimates of the accident output data compared with the OECD TMI-2 standard reference. The alternative scenario has proposed the initial event as a loss of main feed water and a small break on the hot leg. Analysis is in progress along with a sensitivity study concerning the break size and elevation.

• 해양환경안전학회지
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• 제26권1호
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• pp.39-46
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• 2020

사고는 사후조치보다 사전예방이 더 중요하며 이는 하인리히의 법칙을 그 이론적 배경으로 들 수 있다. 준해양사고제도는 유사사고를 사전에 방지할 수 있는 매우 의미 있는 제도로 국제해양사고조사코드(CI Code)의 발효에 따라 우리나라에서는 2010년에 도입되어 오늘에 이르고 있다. 이에 선박소유자나 선박운항자는 준해양사고 발생 시 지정된 통보서식에 따라 중앙수석조사관에게 통보하도록 되어있으나 아직까지 자발적인 통보건수는 미미한 실정이다. 이에 본 연구에서는 이러한 문제의 한 원인으로 현재 준해양사고제도의 통보절차와 통보서식이 미흡하다는 점에 주목하여 이를 심층적으로 분석하여 개선방향을 제시하고자 한다. 이를 위하여 관련규정, 영국과 싱가포르 등 선진해운국의 사례, 항공 및 철도 등 국내 유사교통기관의 사례와 국내 주요 해운선사의 준해양사고 통보절차 및 통보서식을 분석하였고, 이를 바탕으로 개선방향을 제안하였다. 통보절차의 주요개선방안에는 준해양사고의 자율보고로의 전환, 보고주체의 확대, 통보자의 신분보장의 명기 등이 포함되며, 통보서식 개정의 주요내용은 통보라는 용어대신 보고라는 용어의 사용, 통보서식에 신분보장의 대한 내용 반영, 선택형 기입항목의 확대를 통한 통계적 가치 증대 등이 포함된다.

• 한국지진공학회:학술대회논문집
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• 한국지진공학회 2002년도 춘계 학술발표회 논문집
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• pp.284-293
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• 2002

Using the life cycle cost concept, optimum maintenance and retrofit planning for reliable seismic performance is suggested the overall life cycle cost to be minimized including the initial cost, the costs of inspection, repair, and failure. Limit states of the bridges are defined. And failure probabilities are computed through crossing theory. The effect of maintenance and retrofit is represented using the probability of damage detection and event tree analysis. Optimization of maintenance and retrofit planning method proposed from this research was applied to numerical examples. The analysis incorporates the acceleration and site conditions prescribed in the code, and the quality of inspection methods.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 춘계학술대회논문집D
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• pp.813-820
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• 2001

The Safety depressurization System(SDS) of KNGR prevents RCS from overpressurization by discharging high pressure and temperature coolant through the I-sparger into the IRWST during an accident. If IRWST water temperature rise locally, around the sparger, beyond $200_{\circ}$2000 F by the discharged coolant, unstable steam condensation can cause large pressure load on the IRWST wall. To investigate whether this condition can be avoided for the design basis event IOPOSRV(Inadvertent Opening of one Pilot Operated Safety Relief Valve), the flow and temperature distribution of water in the IRWST is calculated by using CFX 4.3 computational fluid dynamic code. According to the results, since pool water temperature does not exceeds temperature limit within 50 seconds after the opening of one POSRV, it can be assured that the integrity of IRWST wall is maintained.

• 한국IT서비스학회지
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• 제10권3호
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• pp.203-212
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• 2011

In the every day life of the people, the Internet is widely used. Currently over 1.9 billion people have one or more email addresses and over 600 million people use the Facebook. People are collaborating via the Internet more and more. When people are collaborating through the Internet, the differences of the message delivery delay are the biggest problem that disturbs the collaborative work over the network. To solve the differences of the message delivery delay, we introduce the delay-gap method. An experimental code have been implemented and the efficiency of the delay-gap is presented through the results from the experiment that have many participants.

• 한국압력기기공학회 논문집
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• 제12권1호
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• pp.56-61
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• 2016

After Japanese Fukushima nuclear power plant accident caused by the beyond design basis earthquake and tsunami, it has turned to be a major challenge for nuclear safety. IAEA, US NRC and EU have provided new safety design standards for beyond design basis event, Domestic regulatory bodies have also enacted guidances for licensees and applicants on additional methods related to beyond design basis events. This paper describes several evaluation methods for applying to nuclear power plants piping for beyond design basis earthquake. As a results, energy method based on the absorbed energy on nuclear power plant, deterministic method following design code and theory, experience method considering past earthquake data and information and probabilistic methods similar to probabilistic risk assessment were reviewed.

• Nuclear Engineering and Technology
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• 제31권6호
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• pp.51-65
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• 1999

The present review report introduces the existing analysis codes and physical modeling of two-phase flow associated with initiating event of HCDA in Liquid Metal Reactors for the effective study in the future, because the related research has not been systematically carried out in Korea compared with other areas. The description in this report is specifically addressed to the results yielded from careful review of the technical concepts on the two-phase flow modeling in the SAS2A code which was developed in ANL. The report is prepared in 2 parts based on the definite physical phenomena. The liquid slug and gas behavior models are main representations in the part (I) and (II), respectively. In this regard, it is expected that this report provide a fundamental knowledge on the two-phase flow model in LMR and, thus, contribute to establishment of the necessary HCDA analysis technology concerned with the LMR development in Korea.

• 제어로봇시스템학회논문지
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• 제15권10호
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• pp.967-973
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• 2009

The model matching problem of asynchronous sequential machines is to design a corrective controller such that the stable-state behavior of the closed-loop system matches that of a prescribed model. In this paper, we address model matching when the external input set consists of controllable inputs and uncontrollable ones. Like in the frame of supervisory control of Discrete-Event Systems (DES), uncontrollable inputs cannot be disabled and must be transmitted to the plant without any change. We postulate necessary and sufficient conditions for the existence of a corrective controller that solves model matching despite the influence of uncontrollable events. Whenever a controller exists, the algorithm for its design is outlined. To illustrate the physical meaning of the proposed problem, the closed-loop system of an asynchronous machine with the proposed control scheme is implemented in VHDL code.