• 한국수소및신에너지학회논문집
• /
• 제11권1호
• /
• pp.43-49
• /
• 2000

현재 증기나 온수에 의한 열수송은 배관을 통하여 열손실 및 마찰손실 등이 발생하므로 수송거리는 3 내지 5km가 한계이다. 그러나 대부분의 공단이 도시지역에서 10km 이상 떨어져 있으므로 이들 지역에서 발생되는 폐열을 적절히 활용하기 위해서는 새로운 열수송 시스템이 개발되어야 한다. 수소저장합금은 수소를 흡수 또는 방출하면서 발열반응과 흡열반응을 일으키는 특성을 가지고 있으므로 산업공단지역의 폐열로부터 수소저장합금의 수소를 방출시키고, 이 수소를 인근 도시지역에 파이프라인으로 수송한 후 필요시 또 다른 수소저장합금과 반응시켜 열을 얻을 수 있다. 이 시스템에서는 난방의 목적 외에도 수소의 흡수 방출온도가 낮은 합금을 이용하여 냉열을 얻을 수도 있다. 따라서 수소저장합금은 폐열의 저장이나 열수송의 수단으로 활용할 수 있다. $MmNi_{4.5}Al_{0.5}Zr_{0.003}$, $LaNi_5$, $Zr_{0.9}Ti_{0.1}Cr_{0.6}Fe_{1.4}$, $MmNi_{4.7}Al_{0.1}Fe_{0.1}V_{0.1}$ 합금들이 열수송에 적합한 합금으로 선정되어 그 특성을 검토하였으며, 열수송시스템의 설계 및 제어기술에 대하여 검토하였다.

• Ocean and Polar Research
• /
• 제37권1호
• /
• pp.23-35
• /
• 2015

A 450 m-long sediment section was recovered from Hole U1359D located at the eastern levee of the Jussieau submarine channel on the Wilkes Land continental rise (East Antarctica) during IODP Expedition 318. The age model for Hole U1359D was established by paleomagnetic stratigraphy and biostratigraphy, and the ages of core-top and core-bottom were estimated to be about 5 Ma and 13 Ma, respectively. Biogenic opal content during this period varied between 3% and 60%. In the Southern Ocean, high biogenic opal content generally represents warm climate characterized by the increased light availability due to the decrease of sea-ice distribution. The surface water productivity change in terms of biogenic opal content at about 10.2 Ma in the Wilkes Land continental rise was related to the development of Northern Component Water. After about 10.2 Ma, more production of Northern Component Water in the North Atlantic caused to increase heat transport to the Southern Ocean, resulting in the enhanced diatom production. Miocene isotope events (Mi4~Mi7), which are intermittent cooling intervals during the Miocene, appeared to be correlated to the low biogenic opal contents, but further refinement was required for precise correlation. Biogenic opal content decreased abruptly during 6 Ma to 5.5 Ma, which most likely corresponds to the Messinian salinity crisis. Short-term variation of biogenic opal content was related to the extent of sea-ice distribution associated with the location of Antarctic Polar Front that was controlled by glacial-interglacial paleoclimate change, although more precise dating and correlation will be necessary. Diatom production in the Wilkes Land continental rise increased during the interglacial periods because of the reduced sea-ice distribution and the southward movement of Antarctic Polar Front.

• 한국수자원학회논문집
• /
• 제33권5호
• /
• pp.603-610
• /
• 2000

토양침식에 영향을 미치는 기후 인자로는 강우, 기온, 바람, 습도 및 태양열 복사 등이 있다. 이들 인자 중 강우는 토양침식에 직접적인 영항을 미친다. 강우의 운동에너지는 토립자의 이탈을 유발하며 강우로 인해 발생하는 흐름은 이탈 토립자를 연행시킨다. 토양침식을 예측하는데 있어 이러한 강우의 영향을 나타내는 지표의 설정은 중요한다. 본 연구에서는 범용토양유실공식(USLE)과 개정공식(RUSLE)의 강우침식도 R의 추정을 위해 1973년부터 1996년 까지 24년간 전국 53개 기상청 관측소의 강우 자료를 이용하였다. 본 연구에서 이용한 강우자료는 모든 관측소에 대해 동일 기간이며, 최근 24년간의 자료를 바탕으로 하고 있다. 본 연구의 최종 결과는 우리 나라의 등강우침식도로 나타내었다.

• 한국의류학회지
• /
• 제29권12호
• /
• pp.1546-1553
• /
• 2005

비 이온계 계면활성제인 Span 20, Tween 20,40, 60, 80, 21, 61, 81, 65, 85 수용액이 PET직물의 습윤특성에 미치는 영향을 연구하였다. 5종류의 PET직물이 사용되었는데, PET 1, 2, 3은 밀도, 두께 등이 서로 다르고 가공은 되어 있지 않고, PET 4와 PET 5는 물리적 특성이 PET 2와 비슷한데 PET 4는 heat set가 공이 되어 있고 PET 5는 rewetting agent가 첨가되어 있다. PET직물의 습윤특성은 비이온계 계면활성제가 첨가되면 크게 향상되며, 수분 보유량은 $cos{\theta}$와 adhesion tension과 정의 상관관계를 보여준다. 친유기가 짧은 친수성 계면활성제나 불포화탄화수소 친유기 구조를 가진 계면활성제가 PET직물의 습윤특성 향상에 효과적이다. 계면활성제가 없을 경우 수분 보유량비(W/H)는 실 간 간격이 넓은 PET직물이 작은 직물보다 컸으나, 비이올계 계면활성제를 첨가할 경우 W/H는 실 간 간격에 관계없이 유사해졌다. 물리적 특성이 비슷해도 heat set가공이 되어 있는 직물은 가공이 되어 있지 않은 직물보다 W/H 값이 작았고, rewetting agent가 첨가된 직물은 W/H 값이 컸다.

• 공업화학
• /
• 제32권4호
• /
• pp.442-448
• /
• 2021

고분자전해질 연료전지에서 분리판 유로 형상은 유체 공급과 물 및 열 확산, 접촉 저항 등에 영향을 주는 중요한 요소이다. 본 연구에서는 25 cm² 단위 전지를 이용하여 공기극에 구리폼을 적용한 분리판을 이용하여 연료전지 성능 평가를 수행하였다. 압력과 상대습도 조건에 대한 영향을 분극 곡선과 전기화학적 임피던스 분광법을 이용하여 분석하였다. 구리폼의 ohmic 저항이 높아 사형유로형상 보다 연료전지 성능은 낮았지만, 다공성 구조로 인한 균일한 연료 분포로 활성화 손실과 물질전달 손실이 적은 것을 확인하였다. 구리폼의 소수성이 높아 물 배출이 유리한 장점이 있지만, 저가습 조건에서는 사형유로에 비하여 전해질막 수화도가 낮은 것을 확인하였다. 다공성 금속 분리판은 균일한 압력 분포와 효과적인 수분 배출로 연료전지 성능을 개선할 수 있을 것으로 판단되며, 저항을 최소화할 수 있도록 금속폼의 물성에 대한 연구가 수행되어야 할 것이다.

• 공업화학
• /
• 제31권5호
• /
• pp.568-574
• /
• 2020

기체확산층은 유로에서 전극으로 반응물을 전달하고, 반응으로 생성되는 물을 배출하는 통로이며 열 배출과 전극 지지대 등의 역할을 하는 고분자전해질 연료전지의 핵심 구성요소이다. 본 연구에서는 국내외 기체확산층 상용 제품인 39BC와 JNT30-A3에 대한 연료전지의 성능 평가를 수행하였다. 25 ㎠ 단위 전지를 이용하여 유량, 상대습도 조건에 대한 분극 곡선을 측정하였고, empirical equation을 이용하여 운전 조건에 대한 성능 인자를 도출하였다. 기체확산층의 PTFE 함량이 높을수록 저항이 증가하였고, 미세다공층의 크랙은 물의 이동 통로로서 농도 손실에 영향을 미쳤다. 또한 상대습도가 낮을수록 Ohmic 저항이 증가하였지만, 전류밀도가 증가할수록 이온전도도가 증가하여 Ohmic 저항이 감소하였다. Empirical equation을 이용한 fitting curve을 통하여 기체확산층의 운전 조건에 대한 성능 인자 경향을 해석할 수 있었다.

• 콘크리트학회논문집
• /
• 제17권5호
• /
• pp.857-868
• /
• 2005

This paper deals with the accumulated damage in concrete structures due to the cyclic freeze-thaw as an environmental load. The cyclic ice body nucleation and growth processes in porous systems are affected by the thermo-physical and mass transport properties, and gradients of temperature and chemical potentials. Furthermore, the diffusivity of deicing chemicals shows significantly higher value under cyclic freeze-thaw conditions. Consequently, the disintegration of concrete structures is aggravated at marine environments, higher altitudes, and northern areas. However, the properties of cyclic freeze-thaw with crack growth and diffusion of chloride ion effects are hard to be identified in tests, and there has been no analytic model for the combined degradations. The main objective is to determine the driving force and evaluate the reduced strength and stiffness by freeze-thaw. For the development of computational model of those coupled deterioration, micro-pore structure characterization, pore pressure based on the thermodynamic equilibrium, time and temperature dependent super-cooling with or without deicing salts, nonlinear-fracture constitutive relation for the evaluation of internal damage, and the effect of entrained air pores (EA) has been modeled numerically. As a result, the amount of ice volume with temperature dependent surface tensions, freezing pressure and resulting deformations, and cycle and temperature dependent pore volume has been calculated and compared with available test results. The developed computational program can be combined with DuCOM, which can calculate the early aged strength, heat of hydration, micro-pore volume, shrinkage, transportation of free water in concrete. Therefore, the developed model can be applied to evaluate those various practical degradation cases as well.

• Journal of Advanced Marine Engineering and Technology
• /
• 제8권1호
• /
• pp.85-99
• /
• 1984

The stability of the two-phase flow in a heated channel is of great importance in the design and operation of the boilers and light water nuclear reactors, because it can cause flow oscillations and lead to a violation of thermal limits with resultant overheating of the channels and cladding. This paper presents a systematic evaluation to the variation effects of the basic four (4) dimensionless parameters in a homogeneous equilibrium model. The flow stability is examined on the ground of static characteristic curves. The complicated transfer function of flow dynamics which gives consideration to the transport lag of density wave is derived, and the transient flow stability is analysed by applying the Nyquist stability criterion in control engineering. The analysis results summed up as follows 1. The coolant flow becomes stable in large friction number and specific flow, while it is unstabale in small friction number and flow. 2. Large phase-change number and Froude number destabilize the two-phase flow, but small numbers stabilize it. The effect to variation of phase-change number is more dominant compared with Froude number. 3. The dynamic analysis is required to hold the sufficient safety of heated channels since only static results does not keep it. The special attention could be payed in the design and operation of heat engines, because the unstaable region exists within the stable boundary at small and middle phase-change number and Froude number.

• Nuclear Engineering and Technology
• /
• 제32권1호
• /
• pp.57-66
• /
• 2000

The RELAP5 code has been developed for best-estimate simulation of transients and accidents for pressurized water reactors and their associated systems, but it has not been fully assessed for those of CANDU reactors. However, a previous study suggested that the RELAP5 code could be applicable to simulate the transients and accidents for CANDU reactors. Nevertheless, it is indicated that there are some works to be resolved, such as modeling of headers and multi-channel simulation for the reactor core, etc. Therefore, this study has been initiated with an aim to identify the code applicability for all the postulated transients and accidents in CANDU reactors. In the present study, the small inlet header break experiment (B8604) in the RD-14 test facility was simulated with RELAP5/MOD3.2 code. The RELAP5 results were also compared with both experimental data and those of CATHENA analyses performed by AECL and the analyses demonstrated the code's capability to predict major . phenomena occurring in the transient with sufficient accuracy for both Qualitative and quantitative viewpoint However, some discrepancies in the depressurization of the primary heat transport system after the break and the consequent time delay of the major phenomena were also observed.

• Nuclear Engineering and Technology
• /
• 제48권5호
• /
• pp.1273-1279
• /
• 2016

Production of iodine-131 by neutron activation of tellurium in tellurium dioxide ($TeO_2$) material requires a target that meets the safety requirements. In a radiopharmaceutical production unit, a new lid for a can was designed, which permits tight sealing of the target by using tungsten inert gaswelding. The leakage rate of all prepared targets was assessed using a helium mass spectrometer. The accepted leakage rate is ${\leq}10^{-4}mbr.L/s$, according to the approved safety report related to iodine-131 production in the TRIGA Mark II research reactor (TRIGA: Training, Research, Isotopes, General Atomics). To confirm the resistance of the new design to the irradiation conditions in the TRIGA Mark II research reactor's central thimble, a study of heat effect on the sealed targets for 7 hours in an oven was conducted and the leakage rates were evaluated. The results show that the tightness of the targets is ensured up to $600^{\circ}C$ with the appearance of deformations on lids beyond $450^{\circ}C$. The study of heat transfer through the target was conducted by adopting a one-dimensional approximation, under consideration of the three transfer modes-convection, conduction, and radiation. The quantities of heat generated by gamma and neutron heating were calculated by a validated computational model for the neutronic simulation of the TRIGA Mark II research reactor using the Monte Carlo N-Particle transport code. Using the heat transfer equations according to the three modes of heat transfer, the thermal study of I-131 production by irradiation of the target in the central thimble showed that the temperatures of materials do not exceed the corresponding melting points. To validate this new design, several targets have been irradiated in the central thimble according to a preplanned irradiation program, going from4 hours of irradiation at a power level of 0.5MWup to 35 hours (7 h/d for 5 days a week) at 1.5MW. The results showthat the irradiated targets are tight because no iodine-131 was released in the atmosphere of the reactor building and in the reactor cooling water of the primary circuit.