• Journal of Korean Society of Forest Science
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• v.98 no.3
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• pp.319-323
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• 2009

One of the limitation of wood as building material is its flammability. The purpose of this paper is to examine the combustion properties of the pinus rigida and castanea savita which are grown in Korea and meet the desirable characteristics for use of construction materials. The cone calorimeter (ISO 5660-1) was used to determine the heat release rate (HRR) and fire smoke index, as well as CO and $CO_2$ production and smoke obscuration. The $HRR_{mean}$ of the castanea savita at $50kW/m^2$ was $160.7kW/m^2$ in comparison with $150.7kW/m^2$ for the pinus rigida. Castanea savita showed an increase of retardant properties attributed to char formation compared with that of pinus rigida. The castanea savita has high $CO_{peak}$ yield and high CO/$CO_2$ yield compared with that of pinus rigida.

• Nuclear Engineering and Technology
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• v.20 no.3
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• pp.189-196
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• 1988

This study investigates the effect of fuel pellet eccentricity on fuel rod thermal performance under the steady state condition. The governing equations in the fuel pellet and the cladding region are set up in 2-dimensional cylindrical coordinate (r, $\theta$) and are solved by finite element method. The angular-dependent heat transfer coefficient in the gap region is used in order to account for the asymmetry of gap width. Material propeties are used as a function of temperature and volumetric heat generation as a function of radial position. The results show the increase of maximum local heat flux at the cladding outer surface and the decrease of maximum and average fuel temperatures due to eccentricity. The former is expected to affect the uncertainties in the minimum DNBR calculation. The latter two are expected to reduce the possibility of fuel melting and the fuel stored energy. Also, the fuel pellet eccentricity introduces asymmetry in fuel pellet temperature and movement of the location of maximum fuel pellet temperature.

• Transactions of the Korean Society of Mechanical Engineers
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• v.17 no.1
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• pp.141-152
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• 1993

A generalized method is presented for shape design sensitivity analysis of axisymmetric thermal conducting solids. The shape sensitivity formula of a general performance functional arising in shape optimal design problem is derived using the material derivative concept and the adjoint variable method. The method for deriving the formula is based on standard axisymmetric boundary integral equation formulation. It is then applied to obtain the sensitivity formulas for temperature and heat flux constraints imposed over a small segment of the boundary. To show the accuracy of the sensitivity analysis, numerical implementations are done for three examples. Sensitivities calculated by the presented method are compared with analytic sensitivities for two examples with analytic solutions, and compared with sensitivies by finite difference for a cooling fin example.

• Proceedings of the Korean Vacuum Society Conference
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• 2010.08a
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• pp.249-249
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• 2010

핵융합로에서는 디버터의 열부하에 대한 안전성을 고려하기 위해 열전도도 및 열 저항성이 높은 텅스텐이 대면 물질로 고려되고 있으며, 경제적인 측면과 실용성 측면에서 텅스텐블록을 직접 제작하여 사용하는 것보다 텅스텐코팅이 효과적이라는 의견이 지배적이다. 또한 ASDEX Upgrade 에서는 탄소블럭에 텅스텐을 코팅하여 챔버 외벽 및 디버터 영역까지 구성하여 캠페인을 진행하였고, 재료적인 측면에서 안정성을 확인 하였다. 따라서 본 연구에서는 디버터 및 챔버외벽 등에 대한 대면물질을 구성하기 위해 상압 열플라즈마 제트를 이용하여 고온에서의 용융 및 냉각을 통해 모재에 텅스텐 피막을 적층하는 과정을 수행하고 있다. 기존의 연구를 통해 일부 공정 변수에 대해서는 이미 적정한 범위의 공정조건을 확보하였고, 기공도와 산화도 및 부착력 등의 물성치에 대한 추가적인 향상을 위해 주요 공정 변수에 집중하여 최적의 조건을 탐색하는 과정이 진행 중이다. 이를 위해 출력증가실험의 일환으로서 기존 36kW급 플라즈마 토치 전력을 한 단계 끌어 올려 48kW급 전력까지 단계적으로 상승시킴으로써 이에 따른 물성치 변화를 검증하고 있다. 현재 44kW 급까지 실험이 수행되었으며, 이를 통해 공극률 감소 및 미세구조 변화에 대한 결과를 얻었다. 실제로 토치의 출력을 증가시킴으로서 텅스텐 피막의 물성치가 변화하는 메커니즘은 플라즈마 제트의 중심부 온도 및 축방향 속도에 의해 결정된다. 중심부 온도가 상승하게 될수록 코팅을 위해 분사되는 분말의 용융률은 증가하지만 분말 외벽에 산화텅스텐이 형성될 가능성은 증가하게 되며, 플라즈마 제트의 모재를 향상 축방향 속도가 증가할수록 용융 된 분말이 모재에 증착 시 형성하는 형태가 원형에 가깝게 되므로 기공이 감소하는 효과가 발생한다. 특히 용융된 분말의 증착 형태는 모재의 온도 및 분말의 입사속도에 결정적이 영향을 받게 되며, 결국 모재와 분말사이의 습윤성에 의한 분말 분산속도가 분말의 입사속도에 버금갈 경우 분말은 모재 위에서 효과적으로 원형으로 전이하며 적층하게 된다. 이러한 전이 현상은 앞에서 언급한 모재의 온도 등에 의해 결정적으로 영향을 받게 되며, 모재의 온도가 전이온도 이하일 경우 폭파형태에서 원형으로 분말의 증착 형태가 전이하게 된다. 이외에 추가적으로 진행하고 있는 연구는 코팅 전처리에 해당하는 분말 효과이며, 특히 탄화텅스텐 분말을 통한 재료적 auto-shroud 효과와 미세분말을 이용한 분말 표면열속의 증가에 따른 용융률 증가효과를 연구에 포함할 계획이다. 이러한 연구는 열적, 그리고 재료적 해석을 바탕으로 해석적 접근을 통해 이루어진다.

• Korean Journal of Fisheries and Aquatic Sciences
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• v.36 no.5
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• pp.535-540
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• 2003

Based on the monthly weather report of Korea Meteorological Administration (KMA) and daily sea surface temperature (SST) data from National Fisheries Research and Development Institute (NFRDl) (1991-2001), mean heat fluxes were estimated at the Gunsan harbor Net heat flux was transported from the air to the sea surface during March to early September, and it amounts to $125\;Wm^{-2}$ in average daily during May to June. During the middle of September to February, the transfer of net heat flux was conversed from the sea surface to the air with $-125\;Wm^{-2}$ in mininum value in October. Short wave radiation was ranged from 50 to $248\;Wm^{-2}$ showing maxima in April to June. Long wave radiation was ranged from 25 to $92\;Wm^{-2}$ with mininum value in June to July. Sensible heat flux denoting negative values in April to August was ranged from -30 to $72\;Wm^{-2}.$ Latent heat flux was ranged from 15 to $82\;Wm^{-2}$ with maxima in August to September. The phase of heat exchange was changed from cooling to heating in the end of February, and from heating to cooling In the beginning of September. The advective term of heat flux showed minima in April to June and maxima in November. The ratio of temperature variations was 1.37 in the sea surface process and the horizontal process by advection. This indicates that the main factor in variation of temperature at Gunsan harbor is the heat exchange process through the sea surface from the air.

• Nuclear Engineering and Technology
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• v.25 no.1
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• pp.8-19
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• 1993

The natural convection model of the consolidated system has been developed to make sure the removal of decay heat generated in the spent fuel for the loss of forced cooling accident. The numerical technique employed was based on the ADI scheme. The calculation of heat generation rate in the spent fuel was peformed by the ANS-79 decay heat model, and the nonuniform surface heat flux is assumed with a chopped sine curve for the conservative decay heat generation input. The sensitivity study was performed to examine the possibility of the pool bulk boiling by varying the various parameters, i.e. inter-fuel spacing ratio, heat generation power, and radius of the fuel rod. The application results of this model show that the natural circulation flow through compacted spent fuel bundles enables the pool temperature to control in a safe and effective manner, after the required cooling time. The corresponding acceptance criteria of the cooling time for rearranging the spent fuel rods were also found.

• Transactions of the Korean Society of Mechanical Engineers
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• v.11 no.2
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• pp.314-321
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• 1987

Post weld heat treatment (PWHT) of weldment of the low alloy Cr-Mo steel, in general, is carried out not only to remove residual stress and hydrogen existing in weldment but to improve fracture toughness of weld heat affected zone (HAZ). There occur some problems such as toughness decrement and stress relief cracking (SRC) in the coarse grained region of weld HAZ when PWHT is practiced. Especially, embrittlement of structure directly relates to the mode of fracture and is appeared as the difference of fracture surface such as grain boundary failure. Therefore, in this paper, the effect of heating rate on PWHT embrittlement under the various kinds of stresses simulated residual stress in weld HAZ was evaluated by COD fracture toughness test and observation of fracture surface. Fracture toughness of weld HAZ decreased with increment of heating rate under no stress, but it was improved to increment of heating rate under the stress. Grain boundary failure didn't almost appear at the heating rate of 600.deg.C/hr but it appeared from being the applied stress of 294 MPa at 220.deg.C/hr and 196 MPa at 60.deg.C/hr.

• Fire Science and Engineering
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• v.24 no.1
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• pp.122-127
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• 2010

The combustion characteristics of phenol foam were analysed using variable external irradiation level (20, 25, 35, 50, and $70kW/m^2$) and in the mixture gas of oxygen/nitrogen. The oxygen index were carried out from the oxygen index tester (KS M ISO 4589-2) and ignition time, critical heat flux, and mass loss rate were carried out from the mass loss calorimeter (ISO 5660-1). As the results of this study, the critical heat flux and average mass loss rate were $28.99kW/m^2$ and $0.56{\sim}1.77g/m^2s$ respectively at the variable external irradiation level. And the limited oxygen index were 45.1% in mixture gas of oxygen/nitrogen. In conclusion, we knew that phenol foam had the best performance than other foam materials in fire safety from all data of this study.

• Nuclear Engineering and Technology
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• v.26 no.4
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• pp.526-535
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• 1994

For the evaluation of the corrosion behavior of the aluminum cladding in the KMRR(Korea Multipurpose Research Reactor) fuel, a modified Griess correlation was derived by introducing a heat flux factor derived from the comparison of the measured in-reactor corrosion data with the prediction of the Griess correlation. As a design criterion on the corrosion to maintain the KMRR fuel integrity, prevention of the oxide spallation was conservatively selected, which is conservatively assumed to occur when the temperature difference across the oxide layer exceeds 114$^{\circ}C$. A bounding power history of the KMRR fuel was determined by examining all the power histories of the KMRR fuel from cycle 1 to equilibrium cycle, and used to predict the maximum possible corrosion. Results of the corrosion prediction of the KMRR fuel with the bounding power history showed that the maximum local thickness of the oxide layer would be below 50$\mu$m and the design criterion on the oxide spallation would be satisfied with a factor of two margin. Therefore, it can be said that corrosion of the cladding will not impair the integrity of the KMRR fuel. Nevertheless, the applicability of the modified Griess correlation to the KMRR needs to be further verified through the KMRR fuel corrosion surveillance.

• Nuclear Engineering and Technology
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• v.22 no.1
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• pp.66-74
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• 1990

The thermal-hydraulic characteristics of the 17$\times$17 OFA (Optimized Fuel Assembly) used in the KNU 7&8 are analyzed and compared with that of the 17$\times$17 SFA (Standard Fuel Assembly) loaded in the KNU 5&6. The thermal-hydraulic characteristics analyzed are minimum DNBR, fuel centerline temperature and exit void fraction at normal operation and design over power transient. Additionally, local linear rod power, which will cause fuel centerline melting, is calculated. The DNBR sensitivity calculations are performed with respect to the reactor operating parameters. COBRA-IV-I code is used for these calculations. The modified W-3 correltion and the drift-flux model are applied for the critical heat flux calculation and the void fraction calculation, respectively. From the calculated results, it has been found that the possibility of DNB occurrence is higher in the OFA than in the SFA. The other hand, the local linear power resulting in fuel centerline moiling of the OFA is nearly equal to that of the SFA.