• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.323-328
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• 1997

중소형 일체형 원자로의 MMIS(Man-Machine Interface System) 설계개발 과정에 활용할 목적으로 관계형 데이터베이스 기반의 인간공학 현안추적시스템을 개발하였다. 동 시스템은 MMIS의 설계 진행과정에서 발견되는 인간공학적 문제점들이 합당할만한 수준으로 해결될 때까지 추적하고 관리하는데 사용된다. NUREG-0711(HFEPRM : Human Factors Engineering Program Review Model)에서는 원자력발전소를 설계함에 있어서 인간공학 현안추적시스템을 유지하고 운영할 것을 요구하고 있다. 본 연구에서 개발한 시스템은 NUREG-0711의 요구사항을 수용할 뿐만 아니라 서류문서형태에 전적으로 의존하는 현안추적시스템을 운영할 때 발생할 수 있는 비효율성, 즉 시간과 경비의 소요, 문서관리의 부담, 중복된 문서내용 등과 같은 부작용을 해소시켜 준다. 또한, MMIS 설계와 관련된 설계조직 구성원들이 인간공학 현안의 내용과 해결 진척사항에 대한 전반적인 정보를 효과적으로 획득하게 지원한다.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05a
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• pp.369-373
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• 1998

증기발생기에서 부식에 의한 전열관 손상은 전열관과 관판사이의 틈새에서 대부분 발생되고 이 틈새에서의 수질환경에 좌우된다. 틈새에서는 과열도가 높아 미량의 불순물이 농축되면서 틈새수화학 (crevice chemistry)은 증기발생기 내부수 수화학과는 달라진다. 전열관 손상을 억제하기 위해서는 틈새수질을 적절히 제어하여야 하는데 이는 틈새수화학을 정확히 분석평가할 수 있는 기술을 기반으로 하여야 한다. .기존의 틈새수질을 계산하는 방법으로는 증기발생기 내부수에 비해 틈새에서 화학종들이 얼마나 농축되는지를 가정하는 농축도 (concentration factor) 방법이 있으나 가정에 의한 불확실성으로 인해 틈새수질을 정확히 해석할 수 없었다. 그러나 원전 증기발생기의 잠복불순물 방출시험 자료로부터 틈새수질을 보다 정확히 평가할 수 있는 새로운 개념의 몰비지수(molar ratio index) 방법이 최근 EPRI에서 제시되었고 EPRI 산하의 많은 발전소에서 적용중이다. 본 연구에서는 PWR 원전 증기발생기의 틈새수화학을 평가할 수 있는 기술을 개발하기 위해 잠복불순물 방출시험 자료로부터 틈새에서의 몰비지수를 계산할 수 있는 CRAP (CRevice-chemistry Analysis Program) 전산프로그램을 작성하였다 CRAP를 국내원전에 적용하여 증기발생기 및 그 틈새에서의 수화학을 평가하였다.

• Nuclear Engineering and Technology
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• v.17 no.2
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• pp.105-115
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• 1985

The axial height-dependent transverse buckling is derived from 3-dimensional depletion file in steadystate conditions. For transient conditions a physical correlation is developed based on the linear relationship existing between the responses of in-core and ex-core detectors. The use of this model greatly improves the reliability of a 1-dimensional diffusion theory program in Predicting the axial power transients accompanying large variations of control rod positions.

• Nuclear Engineering and Technology
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• v.30 no.4
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• pp.298-307
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• 1998

In order to design mutual communication between a distributed control system and a function test facility, we used the Inter-Process Communication(IPC) in two systems and Transmission Control Protocol/Internet Protocol(TCP/IP) protocol. The data from the function test facility are put in the shared memory using an IPC, which is then accessed by the distributed control system through an Application Program Interface(API). The server in the function test facility includes two processes(one for sending and one for receiving), which are generated by the fork function from the client signal. The client in the distributed control system includes two separate programs(one for receiving and one for sending).

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05d
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• pp.404-404
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• 1996

In order to ensure a concrete expansion anchor is suitable for a given application, the load resistance behavior of the anchor must be known. ASTM E488 provides a standard method of testing expansion anchors for static and dynamic loads. Due to the many types of anchors available commercially and the large variability of applications, the ASTM does not delineate all details or requirements necessary to comprehensively determine the dynamic load behavior of concrete expansion anchors. A test program is presented in this paper which was developed and implemented to determine the cyclic load behavior of wedge-type concrete expansion anchors. Test results are also presented along with a discussion of the behavior of anchors, and their suitability for use.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.10a
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• pp.152-157
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• 1997

To test the viability of CANFLEX-SEU bundles in an existing CANDU 6 reactor, core follow-up simulation has been carried out using the reactor fueling simulation program of the CANDU 6, RFSP computer code, and a lattice physics code, WIMS-AECL. During the core follow-up, bundle and channel powers and zone levels have been checked against their operating limits at each simulation. It is observed from the simulation results that an equilibrium core loaded with 0.9 w/o CANFLEX-SEU bundles could be refueled ,and maintained for 550 FPD without any significant violations in the channel and bundle power limits and the permissible operating range of the liquid zone controllers.

• Fire Science and Engineering
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• v.21 no.4
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• pp.99-104
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• 2007

Recently keeping pace with globalization, many international conferences and athletic games are being held in Korea. After 911 terror in New York in 2001, Korean government dispatched Zaytun Division in Iraq and this fact has also led to voice concerns that Korea should be prepared to protect from terrors of chemical, biological, radiological, nuclear, and explosive(CBRNE) emergency as soon as possible. It is important to develop the CBRNE emergency medical training for fire officers in Korea. So I propose the curriculum.

• Proceedings of the KSME Conference
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• 2004.04a
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• pp.264-267
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• 2004

Wall thinning of carbon steel pipe components due to Flow-Accelerated Corrosion (FAC) is one of the most serious threats to the integrity of steam cycle piping systems in Nuclear Power Plants (NPP). Since the mid-1990s, secondary side piping systems in Korean NPPs have experienced wall thinning, leakages and ruptures caused by FAC. Korea Electric power Research Institute (KEPRI) and Korea Hydro & Nuclear Power Co., LTD. (KHNP) have conducted a study to develop the methodology for systematic pipe management and established the Korean Thinned Pipe Management Program (TPMP). To effectively maintain the integrity of piping system, FAC engineer should understand the criterions of the structural integrity evaluation and the safety margin assessment for the thinned pipe component. This paper describes the technical items of TPMP, and shows the example of the integrity evaluation and safety margin assessment for three thinned pipe component of a NPP.

• Nuclear Engineering and Technology
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• v.36 no.6
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• pp.571-581
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• 2004

A methodology is proposed for the evaluation of a steam explosion load on a reactor scale by evaluating the steam explosion model against the experimental data. Being part of the OECD/SERENA program,, appropriate data was selected by international experts and the analytical model of TEXAS-V was chosen. The procedure consists of two steps. the pre-mixing model was verified against the FARO L-14 and FARO L-28 data. The explosion model was verified against the experimental data of KROTOS-44, FARO L-33, TROI-13, and TROI-34. The capabilities and deficiencies of the fundamental models of the TEXAS-V are reviewed in terms of their adequacy in a simulation of steam explosion on a reactor scale.

• Strategy21
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• s.37
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• pp.32-64
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• 2015

This paper examines the types and trends of North Korea's military provocations and regional maritime threats against South Korea, and is focusing on the Republic of Korea's naval development and modernizations by the Republic of Korea Navy (ROKN) on future actions, what directions of the ROKN has taken thus far in response, as well as an examination of how the ROKN might respond to vulnerabilities identified throughout modern history. Importantly, this paper does not consider the domestic, bilateral, multilateral, regional and global political dimensions of the situation on the Korean Peninsula; nor does it consider the North Korea's transitional power politics, but including North Korea's nuclear program and submarine-launched ballistic missile developments, as a caveat, this paper is based on open sources in Korean and English language, and thus information concerning provocations is indicative only.