• Nuclear industry
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• v.23 no.6 s.244
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• pp.39-47
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• 2003

법령에 의하여 요구되는 주기적 안전성 평가를 위하여 인적 요소 평가 방법론을 개발하였다. 특히 평가 하위 업무간의 중복을 제거하여 업무의 효율을 향상시키고 반복적으로 수행되는 동일발전소, 혹은 타발전소의 결과를 충분히 활용할 수 있도록 하였다. 이 방법론은 인간 기계 연계 체제의 현상태 평가, 운전 이력 중심 평가, 시뮬레이션 활용 평가라는 3가지로 특정지어진다. 이 평가 방법을 적용하여 고리 3$\cdot$4호기에 대해서 부분 평가를 수행하였고 그 결과를 제시하였다.

• Proceedings of the Korean Environmental Sciences Society Conference
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• 2005.05a
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• pp.313-315
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• 2005

비이온성 계면활성제의 화학적 구조에 따른 리모넨의 유화분산시 입경변화와 세정성을 비교검토한 결과 리모넨과 계면활성제의 사용비가 30:1의 소량을 사용하여도 충분한 세정성을 보였으며, 에스테르 구조를 가진 계면활성제가 유화능력이 우수하여 에멀젼 입경이 작고 접착력은 크며, 접촉각이 작아 가장 우수한 세정성을 나타내었다. 그리고 에테르 구조의 계면활성제간 비교로부터 방향족 고리 구조보다 지방족 사슬구조가 에멀젼의 입경이 작고 세정성이 우수하였다. 에멀젼의 안전성은 에스테르계가 가장 우수하였다.

• Proceedings of the Korea Institutes of Information Security and Cryptology Conference
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• 2001.11a
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• pp.262-265
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• 2001

분산 시스템에서 사용자가 시스템에 로그인 상태에서 자신의 시스템에 존재하지 않는 자원을 이용하기 위한 방안으로 권한위임이 필수적이다. 이러한 권한위임은 다양하게 요구되는 정보보호 응용 서비스의 가용성을 증대시킨다. 본 논문에서는 권한위임을 처리하기 위해서 권한위임 인증서를 생성하여 안전하게 인증서를 중개자에게 전달해야한다. 개시자와 중개자 최종 목적지까지 다단계 권한위임이 발생하는 연결고리에서 PKI 기반 X.509의 공개키를 이용한 효율적이고 추적 및 검증이 가능한 프로토콜을 제안한다.

• Review of KIISC
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• v.22 no.7
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• pp.54-61
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• 2012

본고에서는 최근 클라우드 컴퓨팅이 갖고 있는 보안 기술 동향에 대하여 살펴본다. 특히 클라우드 컴퓨팅이 갖는 보안 위협들을 해결하기 위한 대응책으로 SecaaS(Security as a Service)에 관심이 집중되고 있다. SecaaS는 클라우드 컴퓨팅의 보안 솔루션을 클라우드 컴퓨팅 서비스의 한 형태로 제공하여 안전성과 신뢰성을 보장한다. CSA(Cloud Security Alliance)에서는 클라우드 컴퓨팅 환경의 보안 위협들에 대해 분석하여 클라우드 보안 가이드를 제시했으며, 최근 SecaaS 워킹그룹에서는 10개의 카테고리로 구분하여 보안 솔루션을 구현하기 위한 구체적인 가이드 제시하고 있다. 먼저 전반적인 클라우드 컴퓨팅의 보안 위협에 대해 살펴보고, 이에 대한 해결방안으로 제시되는 SecaaS 기술에 대해 살펴본다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.284-289
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• 1997

원자력발전소 금속파편감시계통(LPMS : Loose Parts Monitoring System)은 내각재계통 내부에 존재하는 금속파편물을 조기에 탐지하여 관련 구조물 파손을 방지하므로써 불필요한 검사 및 보수로 인한 작업자 방사선 피폭를 최소화하며 원전 안전성 및 경제성을 제고시킨다. 현재 국내 원전에서 가동중인 금속파편감시설비중 영광 1,2호기와 고리 3,4호기에서 운영중인 Westinghouse사의 금속파편감시설비(상품명: Digital Matal Impact Monitoring System)는 70년대에 개발되어 설치된 설비로 기능의 낙후와 장기간 운영에 따른 노후화로 인해 발생될 수 있는 문제점을 방지하고자 하드웨어 및 금속충격파 검출 및 판별 알고리즘을 개발하여 영광 1,2호기에서 기존 설비와 병렬운전중이다.

• The Journal of the Institute of Internet, Broadcasting and Communication
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• v.23 no.5
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• pp.89-95
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• 2023

The underground utility tunnel is an urban infrastructure that accommodates and manages important facilities such as water and sewage, electricity, and communication in the city, and is a national facility that needs to be protected from disasters such as fire, earthquake, and flooding. In establishing a disaster safety life cycle management system such as prediction, prevention, preparedness, response, and recovery, a disaster safety management platform for underground utility tunnel is being developed by utilizing digital twin technology in which advanced ICT technology and data are converged. In this paper, the maturity model for the disaster safety digital twin was reviewed, and the datasets necessary for implementing the digital twin at each stage were defined.

• Nuclear Engineering and Technology
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• v.14 no.4
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• pp.196-203
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• 1982

To transport the spent fuel assemblies of Korea Nuclear Unit 1, which is a Westinghouse type two loop pressurized water reactor, it has been found that steel is the most appropriate material for the design of a shipping cask in comparison with lead and depleted uranium. The proposed shipping cask will transport nine fuel assemblies at the same time and is well within the weight limit of transportation by unrestricted rail car. The cask requires 33cm thick steel shield and 27cm thick water region to satisfy the 3 feet apart dose rate limit set forth in 10 CFR 71, and 1.27cm thick steel boron fuel basket to hold the fuel elements inside the cask and control the effective multiplication factor. As a safety analysis, the fuel cladding and centerline temperatures were calculated under the accident condition of complete loss of water coolant, and it was found that the temperature was much lower than the limit of the melting point. k$_{eff}$ was calculated with fresh fuel assemblies, which was found to be well lower than 0.95. For shielding computation, the multipurpose Monte Carlo code MORSE-CG and one dimensional discrete ordinates transport code ANISN were used, and the Monte Carlo codes KENO and MORSE-CG were used for criticality calculation. The radiation source terms were calculated using ORIGEN-79.9.

• The Journal of the Institute of Internet, Broadcasting and Communication
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• v.23 no.6
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• pp.163-170
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• 2023

With the introduction of the law regarding severe penalties for major accidents, employers, management executives, and corporations have significantly increased the number of safety managers and invested extensively in acquiring ISO certifications to prevent accidents in industrial sites. Moreover, the implementation of the Smart Safety Management System (SSMS) has facilitated the management of personnel and safety equipment. While IoT-based management systems have been applied to safety gear such as helmets, safety harnesses, and protective clothing, the responsibility for safety shoes still primarily lies with on-site managers and individuals, leaving a vulnerability to accidents. In this study, we aim to implement a Raspberry Pi-based sensor device to proactively detect workers' safety shoe usage upon entering the site. The goal is to confirm the usage of safety shoes and prevent accidents that may occur due to non-compliance with safety shoes regulations.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.1
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• pp.51-58
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• 2006

Since 2002, more than 400 PWR spent nuclear fuel assemblies have been transported and stored on-site using transport casks in order to secure the storage capacity of PWR spent nuclear fuel of Kori nuclear power plant. The complete on-site transport system, which includes KN-12 transport casks, the related equipment and transport vehicles, had been developed and provided. KN-12 transport casks were designed, fabricated and licensed in accordance with Korean and IAEA's transport regulations, and the related equipment was also provided in accordance with the related regulations. The on-site transport and storage operation using two KN-12 casks and the related equipment has been conducted, and the strict Quality Control and Radiation Safety Management through the whole process has been carried out so as to achieve the required safety and reliability of the on-site transport of spent nuclear fuel.

• Nuclear Engineering and Technology
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• v.16 no.1
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• pp.11-17
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• 1984

Sample calculations were done for KORI-1 to develop a better understanding of what happens after very small LOCA ($\leq$0.05 ft$^2$). For a water-side break with the break size larger than 0.006 ft$^2$, fluid-loss through break exceeds the makeup. If the break size is larger than 0.008ft$^2$, decay heat can be completely removed through break. Based on these results, it was concluded that KORI-1 is fairly safe for the whole spectrum of sizes in very small LOCA. However, for the reactor with 900 MWe or 1200 MWe, a certain spectrum of sizes in very small LOCA should be carefully considered. In the accident sequence the transition from natural circulation to pool boiling or from pool boiling to natural circulation may be troublesome to the operator or in the safety analysis. Operator's intervention was discussed; primary pump shutoff, HPI pump shutoff, break isolation, and opening relief valve. It was proved that continuous operation of HPI pumps after shutdown will not threaten the integrity of the primary system.