• Nuclear Engineering and Technology
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• v.41 no.8
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• pp.1015-1024
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• 2009

The presence of a non-condensable gas can considerably reduce the level of condensation heat transfer. The non-condensable gas effect is a primary concern in some passive systems used in advanced design concepts, such as the Passive Residual Heat Removal System (PRHRS) of the System-integrated Modular Advanced ReacTor (SMART) and the Passive Containment Cooling System (PCCS) of the Simplified Boiling Water Reactor (SBWR). This study examined the capability of the Multi-dimensional Analysis of Reactor Safety (MARS) code to predict condensation heat transfer in a vertical tube containing a non-condensable gas. Five experiments were simulated to evaluate the MARS code. The results of the simulations showed that the MARS code overestimated the condensation heat transfer coefficient compared to the experimental data. In particular, in small-diameter cases, the MARS predictions showed significant differences from the measured data, and the condensation heat transfer coefficient behavior along the tube did not match the experimental data. A new method for calculating condensation heat transfer coefficient was incorporated in MARS that considers the interfacial shear stress as well as flow condition determination criterion. The predictions were improved by using the new condensation model.

• Nuclear Engineering and Technology
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• v.46 no.4
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• pp.481-488
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• 2014

An analysis of the uncertainty quantification related to LBLOCA using the Monte-Carlo calculation has been performed and compared with the tolerance level determined by the Wilks' formula. The uncertainty range and distribution of each input parameter associated with the LOCA phenomena were determined based on previous PIRT results and documentation during the BEMUSE project. Calulations were conducted on 3,500 cases within a 2-week CPU time on a 14-PC cluster system. The Monte-Carlo exercise shows that the 95% upper limit PCT value can be obtained well, with a 95% confidence level using the Wilks' formula, although we have to endure a 5% risk of PCT under-prediction. The results also show that the statistical fluctuation of the limit value using Wilks' first-order is as large as the uncertainty value itself. It is therefore desirable to increase the order of the Wilks' formula to be higher than the second-order to estimate the reliable safety margin of the design features. It is also shown that, with its ever increasing computational capability, the Monte-Carlo method is accessible for a nuclear power plant safety analysis within a realistic time frame.

• Nuclear Engineering and Technology
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• v.13 no.2
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• pp.73-84
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• 1981

B$\Phi$rrensen proposed a coarse mesh, three-dimensional one-and-half group diffusion scheme for computing the gross power distribution in light water reactors as an alternative to the conventional fine mesh finite difference approach in dealing with three dimensional problems, which require a prohibitively long computing time. The method reported takes extremely small execution time. However, its computational accuracy has not been investigated yet. The B$\Phi$rrensen method is revised in this work and both efficiency and accuracy are examined by applying it to IAEA benchmark problem and RIS$\Phi$ benchmark problem. It is found that two modifications on core-reflector boundary conditions and B$\Phi$rrensen's model constants may improve computational accuracy of power distribution calculation.

• Journal of the Korea Institute of Information and Communication Engineering
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• v.10 no.2
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• pp.360-367
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• 2006

In this paper, we design the complementary code keying (CCK) modulation/demodulation structure that is proposed in the IEEE 820.11b and IEEE 802.11g. And, this paper proposes the CCK Rake receiver to be fitted for the large delay spread case like the inter-vehicle communications. The channel estimation of each path in the multipath Rayleigh fading channel is done using the packet preamble and, the combining of the multipath signals in the coherent CCK Rake receiver is achieved as the symbol level combining type. In this paper, in order to validate the utilization of CCK modem for the inter-vehicle communications of the telematics communications, we suggest the CCK modem performance that is made for the multipath Rayleigh fading channel with the mobile speed of 300km/h.

• Nuclear Engineering and Technology
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• v.18 no.2
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• pp.71-77
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• 1986

A one dimensional neutron kinetics program, BIK which is applicable to the safety analyses of PWR's is developed to analyze the reactor core in axial dimension. The BIK employs the finite difference technique in space and $\theta$-time integration method in time. Detailed models for the Doppler and moderator feedbacks and control rod motion are included. The benchmark of the nuclear model is carried out through the ANL benchmark problem and the time dependent nuclear power change in the rod ejection accident of KNU1 is calculated by BIK code. The results indicate that the BIK can predict the neutron dynamics with fair accuracy within the limits of one dimensional analysis and it is useful for the safety analyses of PWR's.

• The Journal of Korean Medicine Ophthalmology and Otolaryngology and Dermatology
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• v.5 no.1
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• pp.45-59
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• 1992

I have been studied the tinnitus. The results are summarized as follows. 1. The etiologies of tinnitus is classified the Zang fa endogenous factors of the Jong-Maek-Hae and exogenous factors of the Oun-Gi, in the Nei Ching. 2. In the endogenous factors the etiologies of the Zang fa is mostly hased deficiency of the kidney, which is concerned with Sim-Hae Gan-Darn-Hae and Bi-Wae-Hae, the etiologies of the phlegm fire is fire is divided into Sin-Hae, Om-Ju-Hu-Mi and No-Gi-Oaek-Sang. 3. The etiologies of the Jong-Maek-Hae is divided into deficiency of the stomach xu of both gi am blood and xu of the kidney. 4. In Nei ching,the etiologies of Oun-Gi divided into Gul-Eum-Pung-Mok and So-Yang-Sang-Hwa of the exgeous factors is regarded to wind and fire as following generations is regrded to wind the endogenous factors caused Sin-Hae Gi-Hae. 5. In the Nei ching, Since the O-Mi-Bo-Sa-Bub is uttered main treated of tinnitus is friquently used Bo-Sin Young-Sim-Sun-Gi and Choung-Gan-Sul- You1 as Zang-Fu Choung-Dam-Gang-Hwa as the Phlegm fire Bo-bi-Sin as the Jong Maek Hae and Gye-Pung-San-Hwa as the Oun-Gi.

• Nuclear Engineering and Technology
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• v.51 no.5
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• pp.1470-1476
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• 2019

The nuclear power plants in South Korea have been designed in accordance with the U.S. Regulatory Guide 1.60 (R.G 1.60) design spectrum of which the peak frequency range is 2-10 Hz. The characteristics of the earthquakes at the Korea nuclear power plant sites were observed to be closer to that of Central and Eastern United States (CEUS) than the R.G 1.60, which is a lower amplification in a low frequency range, and a higher amplification in a high frequency range. The possibility of failure for sensitive power plant components in the high frequency range has been considered and evaluated. In this study, in order to improve the reliability of nuclear plant and administrative control procedures, seismic tests of an emergency diesel generator (EDG) were conducted using a shaking table under both high and low frequency ranges. From the tests, oil/lubricant leaks from the bolt connections, the fuel filter and the fuel inlet were observed. Therefore, the check list of nuclear plant components after an earthquake should include bolt connections of EDG as well as anchor bolts.

• Nuclear Engineering and Technology
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• v.51 no.2
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• pp.561-572
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• 2019

In the design criterion for the nuclear power plant piping system, the limit state of the piping against an earthquake is assumed to be plastic collapse. The failure of a common piping system, however, means the leakage caused by the cracks. Therefore, for the seismic fragility analysis of a nuclear power plant, a method capable of quantitatively expressing the failure of an actual piping system is required. In this study, it was conducted to propose a quantitative failure criterion for piping system, which is required for the seismic fragility analysis of nuclear power plants against critical accidents. The in-plane cyclic loading test was conducted to propose a quantitative failure criterion for steel pipe elbows in the nuclear power plant piping system. Nonlinear analysis was conducted using a finite element model, and the results were compared with the test results to verify the effectiveness of the finite element model. The collapse load point derived from the experiment and analysis results and the damage index based on the stress-strain relationship were defined as failure criteria, and seismic fragility analysis was conducted for the piping system of the BNL (Brookhaven National Laboratory) - NRC (Nuclear Regulatory Commission) benchmark model.

• The Southeast Asian review
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• v.27 no.2
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• pp.273-295
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• 2017

The Philippines in 2016 showed the highest GDP growth rate among Southeast Asian countries, in spite of domestic and international turbulence caused by the war on drugs and unexpected foreign policies after Duterte's presidency. The social contexts and political dynamics behind 'Duterte phenomenon' have raised key questions and issues to other countries including Korea, as to democracy and politics in current neoliberal challenges. The Philippines' choices for independent foreign policy and challenges against existing hegemony would continue to draw attention, particularly on whether this would end in an experiment of a country or initiate an alternative power block among neighboring countries and ASEAN communities.

• Proceedings of the Korean Society of Disaster Information Conference
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• 2023.11a
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• pp.305-306
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• 2023

지반 침하 및 액상화 등에 따른 과도한 상대변위로 인한 매립배관 시스템의 손상을 저감시키기 위해 종종 벨로우즈 신축이음관은 사용된다. 벨로우즈 신축이음관의 성형과정에서 회선의 벽두께 감소와 같은 구조적인 불확실성이 발생할 수 있으며 특히, 벽두께 감소는 벨로우즈 신축이음관의 성능에 영향을 미칠 수 있다. 매립배관 시스템의 효율적인 유지관리를 위해 회선의 벽두께 감소에 의한 벨로우즈 신축이음관의 성능평가는 필요하다. 하지만 회선의 벽두께 감소가 벨로우즈 신축이음관의 성능에 미치는 영향을 조사하는 연구는 미미하다. 따라서 본 연구는 기초적인 연구로써 고충실도 유한요소 모델을 이용하여 단조하중을 받는 벨로우즈 신축이음관의 벽두께 감소에 의한 성능을 평가하고 민감도 분석을 수행하였다. 각 회선의 벽두께 감소를 20%로 적용하였을 때 최대하중은 약 3% 감소하는 것으로 나타났으며 2번 회선의 벽두께 감소가 최대하중 감소에 비교적 큰 영향을 미치는 것으로 나타났다.