• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 춘계학술발표회논문집(1)
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• pp.184-189
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• 1997

A prompt fission gas release model incorporating the resistance to gas flow in the gap was developed and the effects of gap resistance and failure location on prompt fission gas release from the cladding breach were assessed. The process of prompt fission gas release from the plenum and gap into the coolant was modeled in accordance with three major phenomena: (1) transient gas flow in the gap, (2) the growth of the fission gas bubble while it is still attached to the breach, and (3) the detachment of the fission gas bubble from the breach and mixing with the coolant. The cumulative mass release fraction by the present model was calculated for the case of Young-Gwang 3 & 4 nuclear fuel rod as a typical example. The results showed that the release behavior of prompt fission gas with time was different from the frictionless model which has frequently been used in a simplified approach, and that the location of cladding failure was another key factor for the prompt fission gas release process due to the resistance in the gap.

• 한국재료학회지
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• 제9권10호
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• pp.1000-1005
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• 1999

Zr-0.8Sn합금의 재결정에 미치는 V, Sb의 영향을 조사하기 위해 냉간 압연 후 여러 온도 조건에서 열처리된 시편의 미세조직을 편광광학현미경, SEM, TEM으로 관찰하였고 미소경도계로 경도값을 측정하였다. 미세조직을 관찰한 결과 V과 Sb의 첨가에 의해 재결정이 지연되었으며, 재결정 완료 후의 결정립 성장도 억제됨이 관찰되었다. 특히 Sb는 V보다 재결정을 완료하는데 필요한 온도를 상승시키므로 재결정을 지연시키는 효과가 더욱 큰 것으로 생각된다. 이 처럼 첨가원소가 증가함에 따라 재결정에 늦어지고 결정립이 미세화 되는 것은 V이나 Sb 첨가에 의해 형성된 석출물이 전위나 입계의 이동을 방해하기 때문인 것으로 사료된다.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 춘계학술논문요약집
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• pp.80-81
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• 2018

• 시스템엔지니어링학술지
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• 제13권1호
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• pp.33-39
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• 2017

This paper describes the system engineering approach for the heat transfer analysis of plus7 fuel rod for APR1400 using, a commercial software, ANSYS. The fuel rod is composed of fuel pellets, fill gas, end caps, plenum spring and cladding. The heat is transferred from the pellet outward by conduction through the pellet, fill gas and cladding and further by convection from the cladding surface to the coolant in the flow channel. The goal of this paper is to demonstrate the temperature and heat flux change from the fuel centerline to the cladding surface when having maximum fuel centerline temperature at 100% power. This phenomenon is modelled using the ANSYS FEM code and analyzed for steady state temperature distribution across the fuel pellet and clad and the results were compared to the standard values given in APR1400 SSAR. Specifically the applicability of commercial software in the evaluation of nuclear fuel temperature distribution has been accounted. It is note that special codes have been used for fuel rod mechanical analysis which calculates interrelated effects of temperature, pressure, cladding elastic and plastic behavior, fission gas release, and fuel densification and swelling under the time-varying irradiation conditions. To satisfactorily meet this objective we apply system engineering methodologies to formulate the process and allow for verification and validation of the results acquired. The close proximity of the results obtained validated the accuracy of the FEM analysis of the 2D axisymmetric model and 3D model. This result demonstrated the validity of commercial software instead of proprietary in-house code that is more costly to develop and maintain.

• 대한기계학회논문집A
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• 제41권4호
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• pp.299-305
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• 2017

최근 심각한 환경오염과 경제 불황으로 인해 리엔지니어링에 대한 관심이 증가하고 있다. 조선분야에 대한 리엔지니어링은 꾸준히 진행되어 왔으나 국내에서의 선박 수리 및 유지보수 산업의 기술력과 인지도는 조선해양산업에 비해 떨어진다. 이러한 문제를 해결하기 위해 기술개발의 일환으로 레이저 클래딩을 주목할 수 있다. 레이저 클래딩은 희석률이 낮고, 기공이 거의 존재하지 않는 우수한 클래드 층을 형성하므로 본 연구는 선박용 배기밸브 페이스에 레이저 클래딩 적용을 위한 기초연구로써 다양한 공정변수에 따른 1패스 클래드 층의 특성을 조사하였다. 그 결과, 출력이 증가할수록 클래드 층의 폭은 넓어지고 높이는 감소하였다. 또한 클래드 층의 경도를 측정했을 때 경도 값이 점차 감소하였으며 EDS 성분 분석을 통해 클래드 층 전체가 희석되는 것을 확인할 수 있었다.

• 대한금속재료학회지
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• 제47권10호
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• pp.621-628
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• 2009

Thermomechanical processes were carried out to evaluate their effects on the mechanical and the microstructural property of a ferritic-martensitic steel. Modified 9Cr-1Mo steels were hot-rolled at a temperature of either $780^{\circ}C$ or $850^{\circ}C$ after normalizing at $1050^{\circ}C$ and then were air-cooled. Continuous annealing at $850^{\circ}C$ for 2 hours immediately after the hot rolling was also performed and they were compared to the specimens without thermomechanical process. The result showed that there were little differences between the hot rolled specimens in terms of the precipitation density and size. However, V content inside the MX precipitates increased in the case of the specimen rolled at $850^{\circ}C$. The application of the continuous annealing induced coarsening of the Nb-rich MX precipitation as well as an increase in the amount of V-rich MX precipitation, which is expected to enhance high temperature mechanical properties of the ferritic-martensitic steel.

• Nuclear Engineering and Technology
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• 제51권1호
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• pp.238-248
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• 2019

In the high-temperature and high-pressure irradiation environments, the multi-field coupling processes of hydrogen diffusion, hydride precipitation and mechanical deformation in Zircaloy cladding tubes occur. To simulate this hydrogen-induced complex behavior, a multi-field coupling method is developed, with the irradiation hardening effects and hydride-precipitation-induced expansion and hardening effects involved in the mechanical constitutive relation. The out-pile tests for a cracked cladding tube after irradiation are simulated, and the numerical results of the multi-fields at different temperatures are obtained and analyzed. The results indicate that: (1) the hydrostatic stress gradient is the fundamental factor to activate the hydrogen-induced multi-field coupling behavior excluding the temperature gradient; (2) in the local crack-tip region, hydrides will precipitate faster at the considered higher temperatures, which can be fundamentally attributed to the sensitivity of TSSP and hydrogen diffusion coefficient to temperature. The mechanism is partly explained for the enlarged velocity values of delayed hydride cracking (DHC) at high temperatures before crack arrest. This work lays a foundation for the future research on DHC.

• 대한용접접합학회:학술대회논문집
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• 대한용접접합학회 2000년도 특별강연 및 춘계학술발표대회 개요집
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• pp.131-134
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• 2000

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 추계학술발표회요약집
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• pp.226-226
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• 1998

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2002년도 추계학술발표회요약집
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• pp.262.1-262
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• 2002