• 한국해양학회지:바다
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• 제28권1호
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• pp.19-40
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• 2023

여름철 제주해협 물성 분포의 특성과 제주해협 수괴가 연안에 미치는 영향을 확인하기 위하여 2019년 6월, 7월, 8월에 완도와 제주도 사이에서 수온과 염분을 관측하였다. 여름철 계절 수온약층 아래에서 15℃의 저온수가 관측되었으며, 이 저온수는 관측시기에 따라 다르지만 수심이 깊은 제주해협 남쪽 골보다는 주로 제주해협 중앙의 중층과 북쪽 사면에 분포하였다. 이 저온수를 구성하는 근원 수괴를 알아보기 위하여 제주해협에서 관측된 해수를 구성하는 주변 근원 수괴들의 혼합비(mixing ratio)를 계산하였다. 여름철 제주해협 중앙 중층과 북쪽 사면에 나타나는 저온수는 평균적으로 쿠로시오 아표층수가 54% 그리고 황해저층냉수가 33% 비율로 혼합된 해수였다. 이 중층 저온수는 제주해협 전 수층에서 가장 낮은 수온을 갖는 해수임에도 상대적으로 고온고염인 쿠로시오아표층수가 큰 구성비율을 갖고 있다. 중층 저온수가 제주해협에서 가장 낮은 수온의 분포를 갖게 된 이유는 다른 제주해협 해수에 비해 황해저층냉수의 기여도가 높기 때문이다. 제주해협 중층 저온수의 기원을 살펴보기 위하여 황해, 동중국해, 대한해협에서 2019년 여름철에 관측한 광역 수온과 염분 자료를 분석하였다. 제주도 남서쪽 동중국해 계절 수온약층 아래에서 쿠로시오 기원의 해수와 황해저층냉수가 열염전선을 형성하였고, 이 열염전선을 가로지르는 수괴의 관입에 의해 해수의 혼합이 발생하였다. 동중국해에서 형성된 이 혼합수는 제주해협에서 관측된 중층 저온수와 거의 같은 혼합비율을 가졌다. 이런 결과들을 종합하였을 때 제주해협에서 여름철에 관측된 중층 저온수는 동중국해에서 쿠로시오 아표층수와 황해저층냉수의 혼합으로 만들어진 저온수가 해류를 따라 이동한 것이다. 제주해협 중앙과 북쪽 사면으로 이동한 중층 저온수는 제주해협 중앙의 중층에서 수온역전을 만들고, 한국 남해안 연안의 표층 수온 변동에도 큰 영향을 미친다.

• 한국농림기상학회지
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• 제13권4호
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• pp.176-184
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• 2011

본 연구에서는 폐쇄집수역의 냉기호 현상을 기존의 냉기집적효과와 연계하여 일 최저기온 분포를 모의할 수 있는 방법을 제시하였다. 집수역 내 찬 공기가 담길 '그릇'의 용적을 계산하고 '그릇'안에 집적되는 냉기량을 고도에 따라 표현하였다. 기존의 계곡지형 냉기류에 냉기호를 합산하여 냉기집적으로 인한 기온하강분을 계산하였다. 이때 냉기호의 '수면'은 일교차 조건에 따라 변화시켰다. 이 방법을 검증하기 위해 경남 하동군 악양계곡의 200m 이하 냉기호 형성지역에 기상관측기 10대에서 1분 단위로 기온을 측정하였다. 5월 17일 새벽에는 형제봉 정상에서 적외선 영상 복사계로 지면온도분포를 획득하였다. 개선된 소기후 모형을 적용하여 0530 LST의 기온 분포를 30m 해상도로 추정한 결과 그 양상이 적외선 열영상 분포와 유사하였다. 10개 기상관측지점에 해당하는 격자의 기온추정값을 추출하여 실측값과 비교한 결과, MAE는 1.01에서 0.60으로, RMSE 1.30에서 0.71으로 감소하여 집수역 출구에 가까운 저지대 평야부분에서 발생하는 기존 방법에 의한 오차가 개선되었다.

• Nuclear Engineering and Technology
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• 제56권3호
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• pp.1052-1065
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• 2024

Advanced Pressurized Water Reactors (APWRs) and Boiling Water Reactors (BWRs) employ a suppression pool as a heat sink to prevent containment overpressure. Steam can be discharged into the pool through multi-hole spargers or blowdown pipes in both normal and accident conditions. Direct Contact Condensation (DCC) creates sources of momentum and heat. The competition between these two sources determines the development of thermal stratification or mixing of the pool. Thermal stratification is of safety concern as it reduces the cooling capability compared to a completely mixed pool condition. In this work we develop a scaling approach to prediction of the thermal stratification in a water pool induced by steam injection through spargers. Experimental data obtained from large-scale pool tests conducted in the PPOOLEX and PANDA facilities, as well as simulation results obtained using validated codes are used to develop the scaling. Two injection orientations, namely radial injection through multi-hole Sparger Head (SH) and vertical injection through Load Reduction Ring (LRR), are considered. We show that the erosion rate of the cold layer can be estimated using the Richardson number. In this work, scaling laws are proposed to estimate both the (i) transient erosion velocity and (ii) the stable position of the thermocline. These scaling laws are then implemented into a 1D model to simulate the thermal behavior of the pool during steam injection through the sparger.

• 한국산학기술학회논문지
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• 제11권11호
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• pp.4671-4676
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• 2010

화점높이 변화에 따른 풀 화재의 연소특성을 알아보기 위하여 인화성액체인 메탄올과 노르말 헵탄을 $100mm{\times}100mm{\times}50mm$ 크기의 사각형 용기에 내에 넣고 연소실험을 하였다. 용기의 재질은 스테인레스를 사용하였다. 연소시간, 질량감소속도, 화염온도, 화염높이 및 외부에서 화염으로의 공기유입속도 등을 측정하였으며 연소시 화염의 거동은 비디오카메라를 이용하여 촬영하였다. 실험을 통해서 화점의 높이가 증가할수록 외부에서 화염으로 유입되는 차가운 공기의 유입량이 증가하여 풀 화재의 연소특성이 감소함을 확인 할 수 있었다.

• 한국농림기상학회:학술대회논문집
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• 한국농림기상학회 2011년도 학술발표회
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• pp.35-35
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• 2011

• 한국진공학회:학술대회논문집
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• 한국진공학회 2015년도 제49회 하계 정기학술대회 초록집
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• pp.104-104
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• 2015

Due to the demand of the cold neutron flux in the neutron science and beam utilization technology, the cold neutron source (CNS) has been constructed and operating in the nuclear research reactor all over the world. The majority of the heat load removal scheme in the CNS is two-phase thermosiphon using the liquid hydrogen as a moderator. The CNS moderates thermal neutrons through a cryogenic moderator, liquid hydrogen, into cold neutrons with the generation of the nuclear heat load. The liquid hydrogen in a moderator cell is evaporated for the removal of the generated heat load from the neutron moderation and flows upward into a heat exchanger, where the hydrogen gas is liquefied by the cryogenic helium gas supplied from a helium refrigeration system. The liquefied hydrogen flows down to the moderator cell. To keep the required liquid hydrogen stable in the moderator cell, the CNS consists of an in-pool assembly (IPA) connected with the hydrogen system to handle the required hydrogen gas, the vacuum system to create the thermal insulation, and the helium refrigeration system to provide the cooling capacity. If one of systems is running out of order, the operating research reactor shall be tripped because the integrity of the CNS-IPA is not secured under the full power operation of the reactor. To prevent unscheduled reactor shutdown during a long time because the research reactor has been operating with the multi-purposes, the introduction of the standby cooling system (STS) can be a solution. In this presentation, the design considerations are considered how to design the STS satisfied with the following objectives: (a) to keep the moderator cell less than 350 K during the full power operation of the reactor under loss of the vacuum, loss of the cooling power, loss of common electrical power, or loss of instrument air cases; (b) to circulate smoothly helium gas in the STS circulation loop; (c) to re-start-up the reactor within 1 hour after its trip to avoid the Xenon build-up because more than certain concentration of Xenon makes that the reactor cannot start-up again; (d) to minimize the possibility of the hydrogen-oxygen reaction in the hydrogen boundary.

• 대한기계학회논문집B
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• 제25권12호
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• pp.1887-1897
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• 2001

Korea Atomic Energy Research Institute (KAERI) launched an intermediate scale steam explosion experiment named "Test for Real Corium Interaction with water (TROI)" using reactor material to investigate whether the molten reactor material would lead to energetic steam explosion when interacted wish cold water at low pressure. The melt-water interaction experiment is performed in a pressure vessel with the multi-dimensional fuel and water pool geometry. The novel concept of cold crucible technology, where powder of the reactor material in a water-cooled cafe is heated by high frequency induction, is firstly implemented for the generation of molten fuel. In this paper, the lest facility and cold crucible technology are introduced and the results or the first series of tests were discussed. The 5 kg of molten ZrO$_2$jet was poured into the 67cm deep water pool at 30 ∼ 95 $\^{C}$. Either spontaneous steam explosions or quenching was observed. The morphology of debris and pressure wave profiles clearly indicate the differences between the two cases.

• Journal of Photoscience
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• 제12권1호
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• pp.33-39
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• 2005

Plants possess the ability to dissipate the excitation energy for the protection of photosynthetic apparatus from absorbed excess light. Heat dissipation is regulated by xanthophyll cycle in thylakoid membranes of chloroplasts. We investigated the mechanistic aspects of xanthophyll cycle-dependent photoprotection against low-temperature photoinhibition in plants. Using barley and rice as chilling-resistant species and sensitive ones, respectively, chilling-induced chlorophyll fluorescence quenching, composition of xanthophyll cycle pigments and mRNA expression of the zeaxanthin epoxidase were examined. Chilled barley plants exhibited little changes in chlorophyll fluorescence quenching either of photochemical or non-photochemical nature and in the photosynthetic electron transport, indicating low reduction state of PS II primary electron acceptor. In contrast to the barley, chilled rice showed a marked decline in those parameters mentioned above, indicating the increased reduction state of PS II primary electron acceptor. In addition, barley plants were shown to have a higher capacity to elevate the pool size of xanthophyll cycle pigments in response to cold stress compared to rice plants. Such species-dependent regulation of xanthophyll cycle activity was correlated with the gene expression level of cold-induced zeaxanthin epoxidase. Chilled rice plants depressed the gene expression of zeaxanthin epoxidase, whereas barley increased its expression in response to cold stress. We suggest that chilling-induced alterations in the pool size of xanthophyll cycle pigments related to its capacity would play an important role in regulating plant's sensitivity to chilling stress.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 춘계학술대회논문집E
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• pp.57-62
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• 2001

Korea Atomic Energy Research Institute (KAERI) launched an intermediate scale steam explosion experiment named Test for Real cOrium Interaction with water (TROI) using reactor material to investigate whether the corium would lead to energetic steam explosion when interacted with cold water at low pressure. The melt-water interaction is confined in a pressure vessel with the multi-dimensional fuel and water pool geometry. The cold crucible technology, where the mixture of powder in a water-cooled cage is heated by high frequency induction, is employed. In this paper, results of the first series of tests ($TROI-1{\sim}5$) were discussed. The ZrO2 jets with 5kg mass and 5cm diameter were poured into the 67cm deep water pool at $30{\sim}95^{\circ}C$. Either spontaneous steam explosions or quenching was observed. The morphology of debris and pressure wave profiles clearly indicates the each case.

• Nuclear Engineering and Technology
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• 제41권10호
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• pp.1323-1332
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• 2009

The IHX (Intermediate Heat eXchanger) for a pool-type SFR (Sodium-cooled Fast Reactor) system transfers heat from the primary high temperature sodium to the intermediate cold temperature sodium. The upper structure of the IHX is a coaxial structure designed to form a flow path for both the secondary high temperature and low temperature sodium. The coaxial structure of the IHX consists of a central downcomer and riser for the incoming and outgoing intermediate sodium, respectively. The IHX of a pool-type SFR is supported at the upper surface of the reactor head with an IHX support structure that connects the IHX riser cylinder to the reactor head. The reactor head is generally maintained at the low temperature regime, but the riser cylinder is exposed in the elevated temperature region. The resultant complicated temperature distribution of the co-axial structure including the IHX support structure may induce a severe thermal stress distribution. In this study, the structural feasibility of the current upper support structure concept is investigated through a preliminary stress analysis and an alternative design concept to accommodate the IHTS (Intermediate Heat Transport System) piping expansion loads and severe thermal stress is proposed. Through the structural analysis it is found that the alternative design concept is effective in reducing the thermal stress and acquiring structural integrity.